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Sample records for apr1400 computerized procedure

  1. Improved Design of Crew Operation in Computerized Procedure System of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Seong, No Kyu; Jung, Yeon Sub; Sung, Chan Ho [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    The operators perform the paper-based procedures in analog-based conventional main control room (MCR) depending on only communications between operators except a procedure controller such as a Shift Supervisor (SS), however in digital-based MCR the operators can confirm the procedures simultaneously in own console when the procedure controller of computerized procedure (CP) opens the CP. The synchronization and a synchronization function between procedure controller and other operators has to be considered to support the function of crew operation. This paper suggests the improved design of crew operation in computerized procedure system of APR1400. This paper suggests the improved design of APR1400 CPS. These improvements can help operators perform the crew procedures more efficiently. And they reduce a burden of communication and misunderstanding of computerized procedures. These improvements can be applied to CPS after human factors engineering verification and validation.

  2. Progress of Design Improvements for APR1400 Computerized Procedure System from HFE V and V results and Design Experience

    International Nuclear Information System (INIS)

    Lee, Sungjin; Seong, Nokyu

    2015-01-01

    This study shows major already improved design features from the above three processes and a design proposal for to-be-improving items. APR1400 CPS has been verified and validated by the HFE process, internal design review and site acceptance tests. APR1400 Computerized Procedure System (CPS) has been applied to Shin-Kori Nuclear Power Plant (SKN) 3 and 4 units, Shin-Hanul Nuclear Power Plant (SHN) 1 and 2 units and Baraka Nuclear Power Plant (BNPP) 1, 2, 3 and 4 units. Since APR1400 CPS is a first-of-a-kind (FOAK) human machine interface (HMI) for executing a computerized procedure in the nuclear power plant's main control room in South Korea, it has been continuously improved through a) the human factor engineering (HFE) verification and validation (V and V), b) the internal design review and c) prototype tests. Human engineering discrepancies (HEDs) can be identified by the HFE V and V activity. Some HEDs of APR1400 CPS for SKN 3 and 4 and SHN 1 and 2 have been adopted as a role of design improvement in the CPS system while others were regarded as an operator training requirement or part of task contents. Various requests for improving the CPS have been collected from those results. A HMI system should be improved continuously for removing potential defects. Some of introduced design features in this paper has been adopted for APR1400 nuclear power plants. Some of them are under the review in the CPS design team of KHNP

  3. The Development of CPSES Plug-in(CPMP) for APR1400 Computerized Procedure Effective Maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Seong, No Kyu; Park, Jin Kyun; Jung, Yeon Sub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The Computerized Procedure System (CPS) is one of the Man Machine Interface (MMI) resources of the Shin-Kori 3 and 4 nuclear power plants. The CPS is a computerized operator support system that enables operating crew to execute procedures in an accurate and fast manner. The Computerized Procedure (CP) is the XML data file in executable format that can be installed in the Procedure eXecution System (PXS) for execution. The CP contains specific information related to a particular procedure (i.e. LOCA). These computerized procedures such as Alarm Response Procedures (ARP) are separated into individual alarm procedure to maximize function interface between CPS and DCS. E.g. 'Procedure open by alarm list'. The procedure writer's burden to manage many procedures has been increased because of separated procedures. This paper introduces Computerized Procedure System Engineering System (CPSES) plug-in that is computerized procedure management program (CPMP) to reduce procedure writer's burden. This paper introduces the main features of CPMP. CPMP reduces procedure writer's or CPX maintainer's burden. This program is implemented and tested by program design requirement.

  4. Improvements in Logic Diagram of Computerized Procedure System of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Sungkweon; Seong, Nokyu [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The Computerized Procedure System (CPS) has been improved since it is installed in Shin-Kori 3 and 4 Nuclear Power Plants. It is one of operating support systems of digital Main Control Room (MCR) and provides many functions to operators in executing the procedure. CPS can effectively remove the human errors by supporting the procedure flow and logic diagram. This paper describes the logic diagram of CPS of reference power plant and shows the improved logic diagram of CPS of Shin-Kori unit 5 and 6. This paper describes the current logic diagram of CPS and suggests improved design for logic diagram. The improved logic diagram shall be validated through human factors engineering verification and validation. The improved design will help operators execute the computerized procedure fast and remove the human error.

  5. A study on Requirements of Data Base Translator for APR1400 Computerized Procedure System at Shin-Hanul unit 1 and 2

    International Nuclear Information System (INIS)

    Seong, Nokyu; Lee, Sungjin

    2015-01-01

    The CPS is one of the Man Machine Interface (MMI) resources and the CPS can directly display plant graphic objects which are in the Digital Control System (DCS). And the CPS can send a request to DCS to provide DCS screen which is called step support display through DCS link button on a computerized procedure. The procedure writers can insert DCS graphic information to computerized procedure through data base which is provided by CPS Editing System (CPSES). The data base which is provided by CPSES conforms to the naming rule of DCS graphic objects. The naming rule of DCS graphic objects is defined by vendor thus status of DCS graphic objects which are in computerized procedure at Shin-Kori plant cannot be displayed on CPS at Shin-Hanul plant. To use computerized procedure which is written by other plant procedure writer, DCS graphic objects shall be translated by its plant data base. This paper introduces requirements of data base translator to reduce translation and re-inserting graphic objects burden. This paper introduces the requirements of data base translator of CPSES for APR1400 CPS at Shin-Hanul unit 1 and 2. The translator algorithms shall be tested to update data base of CPSES effectively. The prototype of translator is implemented and is being tested using real plant DB. This translator can be applied to Shin- Hanul unit1 and 2 through software V and V

  6. A study on Requirements of Data Base Translator for APR1400 Computerized Procedure System at Shin-Hanul unit 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Seong, Nokyu; Lee, Sungjin [KHNP, Daejeon (Korea, Republic of)

    2015-05-15

    The CPS is one of the Man Machine Interface (MMI) resources and the CPS can directly display plant graphic objects which are in the Digital Control System (DCS). And the CPS can send a request to DCS to provide DCS screen which is called step support display through DCS link button on a computerized procedure. The procedure writers can insert DCS graphic information to computerized procedure through data base which is provided by CPS Editing System (CPSES). The data base which is provided by CPSES conforms to the naming rule of DCS graphic objects. The naming rule of DCS graphic objects is defined by vendor thus status of DCS graphic objects which are in computerized procedure at Shin-Kori plant cannot be displayed on CPS at Shin-Hanul plant. To use computerized procedure which is written by other plant procedure writer, DCS graphic objects shall be translated by its plant data base. This paper introduces requirements of data base translator to reduce translation and re-inserting graphic objects burden. This paper introduces the requirements of data base translator of CPSES for APR1400 CPS at Shin-Hanul unit 1 and 2. The translator algorithms shall be tested to update data base of CPSES effectively. The prototype of translator is implemented and is being tested using real plant DB. This translator can be applied to Shin- Hanul unit1 and 2 through software V and V.

  7. Developing Optimal Procedure of Emergency Outside Cooling Water Injection for APR1400 Extended SBO Scenario Using MARS Code

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Jong Rok; Oh, Seung Jong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    In this study, we examined optimum operator actions to mitigate extended SBO using MARS code. Particularly, this paper focuses on analyzing outside core cooling water injection scenario, and aimed to develop optimal extended SBO procedure. Supplying outside emergency cooling water is the key feature of flexible strategy in extended SBO situation. An optimum strategy to maintain core cooling is developed for typical extended SBO. MARS APR1400 best estimate model was used to find optimal procedure. Also RCP seal leakage effect was considered importantly. Recent Fukushima accident shows the importance of mitigation capability against extended SBO scenarios. In Korea, all nuclear power plants incorporated various measures against Fukushima-like events. For APR1400 NPP, outside connectors are installed to inject cooling water using fire trucks or portable pumps. Using these connectors, outside cooling water can be provided to reactor, steam generators (SG), containment spray system, and spent fuel pool. In U. S., similar approach is chosen to provide a diverse and flexible means to prevent fuel damage (core and SFP) in external event conditions resulting in extended loss of AC power and loss of ultimate heat sink. Hence, hardware necessary to cope with extended SBO is already available for APR1400. However, considering the complex and stressful condition encountered by operators during extended SBO, it is important to develop guidelines/procedures to best cope with the event.

  8. Evaluation of Coolant Injection Procedure in the Severe Accident Management Strategy of APR1400

    International Nuclear Information System (INIS)

    Cho, Yongjin; Lim, Kukhee; Song, Sungchu; Lee, Sukho; Hwang, Taesuk

    2013-01-01

    A coolant injection strategy in the severe accident management guideline (SAMG) of APR1400 relates to immediate coolant injection into RCS (Reactor Coolant System) or injection following the recovery of secondary coolant inventory. This strategy could play important role in accident mitigation and radiological consequences. In this study, appropriateness of the strategy was evaluated using MELCOR1.8.6 and several sensitivity studies of the key parameters were performed. Analysis for APR1400 using MELCOR 1.8.6 was performed to evaluate the effectiveness of accident management strategies and the following conclusions were identified. Sequential operation of secondary and RCS injection may not be the best strategy and the simultaneous injection of secondary and RCS injection could be more preferable. At least, the RCS injection should start before complete drainage of water in the safety injection tank using mobile pumps. In this study, the effectiveness of timing of operator action has been examined and the amount of injection flowrate needs to be studied in the future

  9. Diagnostic Strategy in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dongyoung; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-05-15

    These features may bring out changes in operator tasks, changing the characteristics of tasks, or creating new tasks. Diagnostic strategy for identifying anomaly may be different especially in APR1400 from that in the analog control room due to the change of human-system interface, i.e. alarm system and display system. Since the first plant of APR1400 is being built at this moment, it is not known what strategies the operators will adopt in diagnosis tasks in the new operating environment. In this light, this paper aims at investigating operator's diagnostic strategies which are appropriate for APR1400. In order to collect data, several different approaches which are complementary are used to identify diagnostic strategies in the digital control room: analysis on audio/video recording of operation, observation in the simulator, and interview with the operators. The result shows that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of strategies, mostly, by getting more support from the computerized system. This paper investigated how the digitalized control room may influence operator's diagnostic strategies. Several different approaches, i. e., audio/video record, observation of training, and the interview with operators, were used to gather information about the operator's behaviors. As a conclusion, this paper figured out that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of the strategies, mostly, by getting more support from the computerized system. The operators interviewed also commented that the diagnosis in the APR1400 is quicker, more correct, and easier, compared with the analog control room.

  10. Diagnostic Strategy in APR1400

    International Nuclear Information System (INIS)

    Kim, Dongyoung; Kim, Jonghyun

    2013-01-01

    These features may bring out changes in operator tasks, changing the characteristics of tasks, or creating new tasks. Diagnostic strategy for identifying anomaly may be different especially in APR1400 from that in the analog control room due to the change of human-system interface, i.e. alarm system and display system. Since the first plant of APR1400 is being built at this moment, it is not known what strategies the operators will adopt in diagnosis tasks in the new operating environment. In this light, this paper aims at investigating operator's diagnostic strategies which are appropriate for APR1400. In order to collect data, several different approaches which are complementary are used to identify diagnostic strategies in the digital control room: analysis on audio/video recording of operation, observation in the simulator, and interview with the operators. The result shows that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of strategies, mostly, by getting more support from the computerized system. This paper investigated how the digitalized control room may influence operator's diagnostic strategies. Several different approaches, i. e., audio/video record, observation of training, and the interview with operators, were used to gather information about the operator's behaviors. As a conclusion, this paper figured out that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of the strategies, mostly, by getting more support from the computerized system. The operators interviewed also commented that the diagnosis in the APR1400 is quicker, more correct, and easier, compared with the analog control room

  11. Development of an improved installation procedure and schedule of RVI modularization for APR1400

    International Nuclear Information System (INIS)

    Ko, Do Young

    2011-01-01

    The construction technology for reactor vessel internals (RVI) modularization is one of the most important factors to be considered in reducing the construction period of nuclear power plants. For RVI modularization, gaps between the reactor vessel (RV) core-stabilizing lug and the core support barrel (CSB) snubber lug must be measured using a remote method from outside the RV. In order to measure RVI gaps remotely at nuclear power plant construction sites, certain core technologies must be developed and verified. These include a remote measurement system to measure the gaps between the RV core-stabilizing lug and the CSB snubber lug, an RVI mockup to perform the gap measurement tests, and a new procedure and schedule for RVI installation. A remote measurement system was developed previously, and a gap measurement test was completed successfully using the RVI mockup. We also developed a new procedure and schedule for RVI installation. This paper presents the new and improved installation procedure and schedule for RVI modularization. These are expected to become core technologies that will allow us to shorten the construction period by a minimum of two months compared to the existing installation procedure and schedule

  12. Constructibility assessment of APR1400

    International Nuclear Information System (INIS)

    Cho, Sung Jae; Kang, Yong Chul; Lee, Jae Gon; Lim, Woo Sang

    2003-01-01

    APR1400 (formerly KNGR) development is one of national G-7 projects sponsored by government and KHNP (Korea Hydro and Nuclear Power Co., LTD). It is an evolutionary standard reactor with the thermal output of 4000MWt and has been adopted for Shin-Kori Unit 3 and 4. The government organizations, research institutes, universities and industries have participated in the project since 1992 along with KHNP, and the standard design certification program was issued in May 2002. The project set up the top-tier requirements about the safety, economy, operability and maintainability, and constructibility in the early design stage. The requirements have been evaluated periodically during the design process, and the results were reflected to the design. This paper describes the methods for constructibility enhancement and the results of schedule analysis to assure meeting construction duration target, which is set to 48 months from the first concrete pouring to the commercial operation on the condition that learning effects are maximized at Nth plant. To meet the target schedule, the design characteristics and constructibility studies such as new construction methods and construction schedule analysis were performed. The new construction methods presented here are over the top method for NSSS components, deck plate and steel from for concrete wall and slab, automatic welding for large bore piping, and modularization of components and structure, etc. (author)

  13. APR1400 Fluidic Device Sensitivity Test

    International Nuclear Information System (INIS)

    Choi, Nam Hyun; Chu, In Cheol; Min, Kyong Ho; Song, Chul Hwa

    2005-12-01

    In the safety injection tank at the emergency core cooling system of APR1400, a new safety design feature, passive fluidic device is equipped which includes no active driving system. It is essential to evaluate the new design feature with various experiments. For this reason, three categories of sensitivity tests have been performed in the present study. As the first sensitivity experiment, the effect of the height of the stand pipe was investigated. The second sensitivity test was conducted with removing the insert plate gasket to examine its effect. The effect of the expansion of the control nozzle width was ascertained from the third sensitivity test. The results of each test showed that the passive fluidic device which will be equipped in the SIT tank of APR1400 has great integrity and repeatability

  14. Radiation exposure reduction in APR1400

    International Nuclear Information System (INIS)

    Bae, C. J.; Hwang, H. R.; Matteson, D. M.

    2002-01-01

    The primary contributors to the total occupational radiation exposure in operating nuclear power plants are operation and maintenance activities during refueling outages. The Advanced Power Reactor 1400 (APR1400) includes a number of design improvements and plans to utilize advanced maintenance methods and robotics to minimize the annual collective dose. The major radiation exposure reduction features implemented in APR1400 are a permanent refueling pool seal, quick opening transfer tube blind flange, improved hydrogen peroxide injection at shutdown, improved permanent steam generator work platforms, and more effective temporary shielding. The estimated average annual occupational radiation exposure for APR1400 based on the reference plant experience and an engineering judgment is determined to be in the order of 0.4 man-Sv, which is well within the design goal of 1 man-Sv. The basis of this average annual occupational radiation exposure estimation is an eighteen (18) month fuel cycle with maintenance performed to steam generators and reactor coolant pumps during refueling outage. The outage duration is assumed to be 28 days. The outage work is to be performed on a 24 hour per day basis, seven (7) days a week with overlapping twelve (12) hour work shifts. The occupational radiation exposure for APR1400 is also determined by an alternate method which consists of estimating radiation exposures expected for the major activities during the refueling outage. The major outage activities that cause the majority of the total radiation exposure during refueling outage such as fuel handling, reactor coolant pump maintenance, steam generator inspection and maintenance, reactor vessel head area maintenance, decontamination, and ICI and instrumentation maintenance activities are evaluated at a task level. The calculated value using this method is in close agreement with the value of 0.4 man-Sv, that has been determined based on the experience and engineering judgement

  15. MELCOR code modeling for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Young; Park, S. Y.; Kim, D. H.; Ahn, K. I.; Song, Y. M.; Kim, S. D.; Park, J. H

    2001-11-01

    The severe accident phenomena of nuclear power plant have large uncertainties. For the retention of the containment integrity and improvement of nuclear reactor safety against severe accident, it is essential to understand severe accident phenomena and be able to access the accident progression accurately using computer code. Furthermore, it is important to attain a capability for developing technique and assessment tools for an advanced nuclear reactor design as well as for the severe accident prevention and mitigation. The objective of this report is to establish technical bases for an application of the MELCOR code to the Korean Next Generation Reactor (APR1400) by modeling the plant and analyzing plant steady state. This report shows the data and the input preparation for MELCOR code as well as state-state assessment results using MELCOR code.

  16. Development of Reactor Coolant Pump for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Sang-Youn; Chu, Sung-Min; Chang, Jin-Young [Doosan Heavy Industries and Construction, Changwon (Korea, Republic of)

    2015-10-15

    The development was focused on the performance requirements for APR1400 and to achieve the goals of the safety, reliability and adaptability for APR1400 system design. In addition, APR1400 RCP design was customized considering convenience of installation, operation and maintainability. This paper describes the details of the development process, improved design feature and type test results. Based on development of core technology of RCP, DOOSAN supplies the localized and improved APR1400 RCP to Shin-Hanul 1 and 2 Project. This would be good experience that the RCP core technology can break foreign monopoly in supplying the domestic nuclear industry. Also, there expect APR1400 RCP can be sustainable revenue models in nuclear industry. Moreover, development of RCP will be a catalyst to enhance design capacity for equipment and system of nuclear power plant as well as evaluation and verification skills of Korean nuclear industry.

  17. The APR1400 Core Design by Using APA Code System

    International Nuclear Information System (INIS)

    Choi, Yu Sun; Koh, Byung Marn

    2008-01-01

    The nuclear design for APR1400 has been performed to prepare the core model for Automatic Load Follow Operation Simulation. APA (ALPHA/ PHOENIXP/ ANC) code system is a tool for the multi-cycle depletion calculations for APR1400. Its detail versions for ALPHA, PHOENIX-P and ANC are 8.9.3, 8.6.1 and 8.10.5, respectively. The first and equilibrium core depletion calculations for APR1400 have been performed to assure the target cycle length and confirm the safety parameters. The parameters are satisfied within limitation about nuclear design criteria. This APR1400 core models will be based on the design parameters for APR1400 Simulator

  18. ITAAC Development for APR1400 NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Jin Kwon; Kim, Myoung Ki

    2013-01-01

    ITAAC (Inspections, Tests, Analyses and Acceptance Criteria) is essential document for Design Certification, which is certified by NRC and ruled as the Appendix of the 10 CFR Part 52. Approximately 870 ITAAC items were selected for APR1400 Design Certification to be submitted to NRC. In this paper, the code and standard related to ITAAC and process of ITACC development are discussed to seek the way to complete the best ITAAC to get the Design Certification of APR1400 from NRC through the lessons learned from other competitive applicants. For saving the time and manpower to complete ITAAC of APR1400 NRC DC and reduction of the RAIs (Request Additional Information) from NRC, we took advantage of the lessons learned from the competitive designs like US-APWR and AP1000 based on KNGR ITAAC. Finally new and different ITAAC from ITAAC of KNGR was developed for APR1400 DC from NRC. RG 1.206 and SRPs were applied first in Korea to the APR1400 DCD preparation. For testability and acceptability check, ITAAC V and V table was completed by the system designers. APR1400 DCD will be submitted by the end of September this year and we hope that NRC issues lees RAIs on ITAAC document

  19. Development of Reference Source Terms for EU-APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, ByungIl; Lee, Chonghui; Lee, Dongsu; Ko, Heejin; Kang, Sangho [KEPCO Engineering and Construction Co. Inc., Yongin (Korea, Republic of)

    2014-05-15

    These source terms are developed for the typical U. S. NPP and do not reflect the design characteristics of EU-APR1400 (1,400 MWe PWR) which will be applied for the EUR certification in European countries. The process of developing the RST for EU-APR1400 is to undergo a similar process that NUREG-1465 had gone through when it came out with its proposed source terms. The purpose of this study is to develop the EU-APR1400 design-specific RST complied with the EUR. The Large LOCA is the reference equence used in the NUREG-1465 evaluation, whereas the EUAPR1400 risk-significant sequences are dominated by small LOCA and non-LOCA sequences. Moreover, when considering the EU-APR1400 has many design features to mitigate the consequences of severe accident phenomena, it is not surprising that the aspects of both release fractions and durations are distinctly different from NUREG-1465. This RST will be continuously updated to reflect to the design features of EU-APR1400, and then, be used as the reference for design purposes such as criteria satisfaction of radioactivity releases, equipment survivability, control room habitability for severe accident, and so on.

  20. APR1400 CEA Withdrawal at Power Accident Analysis using KNAP

    International Nuclear Information System (INIS)

    Lee, Dong-Hyuk; Yang, Chang-Keun; Kim, Yo-Han; Sung, Chang-Kyung

    2006-01-01

    KEPRI (Korea Electric Power Research Institute) has been developing safety analysis methodology for non- LOCA (Loss Of Coolant Accident) analysis of OPR1000 (Optimized Power Reactor 1000, formerly KSNP). The new methodology, named KNAP (Korea Non-LOCA Analysis Package), uses RETRAN as the main system analysis code. RETRAN code is a non- LOCA safety analysis code developed by EPRI. The new methodology will replace existing CE (Combustion Engineering) supplied codes and methodologies currently used in non-LOCA analysis of OPR1000. In this paper, we apply KNAP methodology to APR1400 (Advanced Power Reactor 1400). The CEA (Control Element Assembly) withdrawal at power accident is one of the 'reactivity and power distribution anomalies' events and the results are typically described in the chapter 15.4.2 of SAR (Safety Analysis Report). The APR1400 has been designed to generate 1,400MWe of electricity with advanced features for greatly enhanced safety and economic goals. The CEA withdrawal at power analysis in APR1400 SSAR (Standard Safety Analysis Report) is analyzed with CESEC-III computer code. In this study, to confirm the applicability of the KNAP methodology and code system to APR1400, CEA withdrawal at power accident is analyzed using RETRAN code and it is compared with results from APR1400 SSAR

  1. Verification of SAMG entry condition for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Junghyun; Kim, Taewan; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    In the wake of the Fukushima accident, severe accident management has become important more than ever. While Emergency Operating Procedures (EOPs) focuses on cooling down the core during a design basis accident, the prime objective of severe accident management guideline (SAMG) is to prevent the release of radioactive material into the environment during a severe accident. Only one fixed value of core exit temperature (CET) has been applied for several decades to different types of nuclear power plants (NPPs) in Korea. Although the different types of NPPs have different cladding materials and system designs, the identical CET, i. e., 650 .deg. C, is applied as the entry condition to the SAMG of all the NPPs (except CANDU plants), i. e., Westinghouse type, OPR1000, and APR1400. In this paper, the transition point is re-evaluated for dominant severe accident sequences; station black-out (SBO), small break loss of coolant accident (SBLOCA), and me dium break loss of coolant accident (MBLOCA). In cases of SBO and SBLOCA, the current SAMG entry condition seems proper, while it needs to be reconsidered for MBLOCA case.

  2. Study on Applicability of 10 CFR Part 21 to APR1400 DC Project

    International Nuclear Information System (INIS)

    Shin, He Young; Lee, Do Hwan; Lim, Jae Yong

    2014-01-01

    The tools such as NCR (non conformance report), CAR (corrective action request) and CAP (corrective action program) are widely used for that purpose based upon the rule of 10 CFR Part 50 Appendix B and the ASME Code NQA-1 requirements. These are the tools for a utility, as a purchaser taking over related basic components and services, to ensure strong quality assurance. During the conduct of the project for the acquisition of the standard design certification for APR1400 nuclear power plants from the U. S. NRC (APR1400 DC Project), a new CAP procedure that is appropriate to conduct this unique project was developed. However, it was also recommended to comply with the requirements under 10 CFR Part 21 which enhances nuclear safety quality assurances. Consequently, a new QA procedure is developed in order to deal with the 10 CFR Part 21 issues and this is integrated to the CAP procedure In this paper, the current corrective action program for the APR1400 DC project is introduced and the result of the study on the applicability of 10 CFR Part 21 to the project is indicated. In addition, further improving aspects to be considered are identified. As a frontier project to obtain the standard design certification for APR 1400 model from the U. S. NRC, a modified CAP procedure is developed and enhanced to deal with safety concerning issues in accordance with 10 CFR Part 21. In addition, the newly established QA procedure to directly control the reportability on 10 CFR Part 21 is interfaced into the existing CAP procedure

  3. APR1400 Locked Rotor Transient Analysis using KNAP

    International Nuclear Information System (INIS)

    Lee, Dong-Hyuk; Kim, Yo-Han; Ha, Sang Jun

    2007-01-01

    KEPRI (Korea Electric Power Research Institute) has developed safety analysis methodology for non-LOCA (Loss Of Coolant Accident) analysis of OPR1000 (Optimized Power Reactor 1000, formerly KSNP). The new methodology, named KNAP (Korea Non-LOCA Analysis Package), uses RETRAN as the main system analysis code for most transients. For locked rotor transient DNBR analysis, UNICORN-TM code is used. UNICORN-TM is the unified code of RETRAN, MASTER and TORC. The UNICORN-TM has 1-D and 3-D neutron kinetics calculation capability. For locked rotor DNBR analysis, 1-D neutron kinetics is used. In this paper, we apply KNAP methodology to APR1400 (Advanced Power Reactor 1400) locked rotor analysis and compare the results with those in the APR1400 SSAR(Standard Safety Analysis Report). The locked rotor transient is one of the 'decrease in reactor coolant system flow rate' events and the results are typically described in the chapter 15.3.3 of SAR (Safety Analysis Report). In this study, to confirm the applicability of the KNAP methodology and code system to APR1400, locked rotor transient is analyzed using UNICORN-TM code and the results are compared with those from APR1400 SSAR

  4. System Response Analysis of LOCV for APR1400 Using KNAP

    International Nuclear Information System (INIS)

    Kim, Yo-Han; Sung, Chang-Kyung; Jun, Hwang-Yong

    2006-01-01

    Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has been developed the non-loss-of-coolant accident (non-LOCA) analysis methodology, called as the Korea Non-LOCA Analysis Package (KNAP), for the typical Optimized Power Reactor 1000 (OPR1000) plants. Considering current licensing methodology conducted by ABB-CE, however, the KNAP could be applied to Advanced Power Reactor 1400 (APR1400). In spite of some difference in components of two plant types, there is a close resemblance between their nuclear steam supply systems (NSSS). So, in this study, the loss of condenser vacuum (LOCV) event were analyzed using KNAP for APR1400 to estimate the feasibility of the application and the results were compared with those given in APR1400 Standard Safety Analysis Report (SSAR), which were calculated using the CESEC-III code of ABB-CE. Through the study, it was concluded that the KNAP could be applicable to APR1400 on the view point of LOCV event

  5. Functional Requirement Analysis and Function Allocation for APR 1400

    International Nuclear Information System (INIS)

    Nuraslinda, Anuar; Florah, Kamanja; Noloyiso, Mtoko and others

    2013-01-01

    This paper intends to fulfill the FRA and FA of the HFE as required in Chapter 4 of NUREG-0711 rev. 3 for APR1400 to satisfy both plant safety and power generation objectives. This paper aims to evaluate the FRA and FA for APR1400. The allocation of function is done at the system level for all processes for both the power generation and safety goals, following the NUREG/CR-3331 guideline. As a conclusion, this paper has successfully implemented the requirements and methodology specified in NUREG-0711 for APR 1400. The Functional Requirement Analysis (FRA) and Function Allocation (FA) are required by the regulation in the Human Factors Engineering (HFE) program. The FRA defines the functions, processes, and system for plant safety and power generation. The FA allocates the functions to human operator, automation, or a combination of two. The FRA and FA for APR1400 have been performed in the very early stage of development but only for the plant safety. However, the analysis did not include the goal of power generation and also did not fully satisfy the latest revision of NUREG-0711

  6. APR1400 Locked Rotor Transient Analysis using KNAP

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong-Hyuk; Kim, Yo-Han; Ha, Sang Jun [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    KEPRI (Korea Electric Power Research Institute) has developed safety analysis methodology for non-LOCA (Loss Of Coolant Accident) analysis of OPR1000 (Optimized Power Reactor 1000, formerly KSNP). The new methodology, named KNAP (Korea Non-LOCA Analysis Package), uses RETRAN as the main system analysis code for most transients. For locked rotor transient DNBR analysis, UNICORN-TM code is used. UNICORN-TM is the unified code of RETRAN, MASTER and TORC. The UNICORN-TM has 1-D and 3-D neutron kinetics calculation capability. For locked rotor DNBR analysis, 1-D neutron kinetics is used. In this paper, we apply KNAP methodology to APR1400 (Advanced Power Reactor 1400) locked rotor analysis and compare the results with those in the APR1400 SSAR(Standard Safety Analysis Report). The locked rotor transient is one of the 'decrease in reactor coolant system flow rate' events and the results are typically described in the chapter 15.3.3 of SAR (Safety Analysis Report). In this study, to confirm the applicability of the KNAP methodology and code system to APR1400, locked rotor transient is analyzed using UNICORN-TM code and the results are compared with those from APR1400 SSAR.

  7. Implementation and Analysis for APR1400 Soft Control System

    International Nuclear Information System (INIS)

    2015-01-01

    Due to the rapid advancement of digital technology, the definite technical advantages of digital control system compared to analog control system are accelerating the implementation of advanced distributed digital control system in the nuclear power plant. One of the major advantages of digital control system is the capability of Soft Control System. The design of Soft Control System for Advanced Power Reactor 1400 (APR1400) plant of Man-Machine Interface System (MMIS) is based on full digital technologies to enhance reliability, operability and maintainability. Computer-based compact workstation has been adopted in the APR1400 Main Control Room (MCR) to provide convenient working environment. This paper introduces the approaches and methodologies of Soft Control System for the Advanced Control Room (ACR). This paper also explains major design features for operation and display of the Soft Control System and its implementation to cope with regulatory requirements. (authors)

  8. Verbal Communication in the APR1400 Advanced Control Room

    International Nuclear Information System (INIS)

    Kim, Jong Hyun; Shin, Young Cheol

    2007-01-01

    This paper introduces the characteristics of communication in advanced main controlghd rooms (MCRs) and some observations from a case study performed for APR1400 MCR. In advanced MCRs, operators need not maintain the same communication patterns as they do in conventional ones. For example, a senior reactor operator (SRO) does not have to rely on board operators for information acquisition and can get any information from his/her own workstation. This situation may also bring about new problems in MCRs such as lack of shared situation awareness and collaboration between MCR operators. To cope with these problems, the APR1400 MCR adapts several approaches in design and training for encouraging operators to communicate with each other. This paper introduces the possible changes of communication patterns and the countermeasures in design and training. Some findings from an integrated system validation for Shin Kori Units 3 and 4 are also presented

  9. Preliminary Results Of LOCA Problem For APR1400 Reactor

    International Nuclear Information System (INIS)

    Le Dai Dien; Hoang Minh Giang; Le Thi Thu; Vo Thi Huong; Le Van Hong

    2011-01-01

    Several features of NPP with APR1400 nuclear reactor during a loss of coolant accident (LOCA) are investigated in this study. The report describes some main design characteristics of an engineering safety systems of APR1400 and the thermal hydraulic calculation results for steady-state using MARS and RELAP/SCDAPSIM codes. Large Break LOCA accident has been analyzed and evaluated based on acceptable criteria for ECCS given by US NRC. The results from cold leg break LOCA with broken area of 0.0465 m 2 in case of high pressure safety injection system (HPSI) failed to operate or 2 and 4 HPSI pumps are activated. The preliminary results of this work is a part of collaboration between INST researchers and KAERI experts in using RELAP tool for safety analysis of NPPs. (author)

  10. Design features of Advanced Power Reactor (APR) 1400 steam generator

    International Nuclear Information System (INIS)

    Park, Tae-Jung; Park, Jun-Soo; Kim, Moo-Yong

    2004-01-01

    Advanced Power Reactor 1400 (APR 1400) which is to achieve the improvement of the safety and economical efficiency has been developed by Korea Hydro and Nuclear Power Co., Ltd. (KHNP) with the support from industries and research institutes. The steam generator for APR 1400 is an evolutionary type from System 80 + , which is the recirculating U-tube heat exchanger with integral economizer. Compared to the System 80 + steam generator, it is focused on the improved design features, operating and design conditions of APR 1400 steam generator. Especially, from the operation experience of Korean Standard Nuclear Power Plant (KSNP) steam generator, the lessons-learned measures are incorporated to prevent the tube wear caused by flow-induced vibration (FIV). The concepts for the preventive design features against FIV are categorized to two fields; flow distribution and dynamic response characteristics. From the standpoint of flow distribution characteristics, the egg-crate flow distribution plate (EFDP) is installed to prevent the local excessive flow loaded on the most susceptible tube to wear. The parametric study is performed to select the optimum design with the efficient mitigation of local excessive flow. ATHOS3 Mod-01 is used and partly modified to analyze the flow field of the APR 1400 steam generator. In addition, the upper tube bundle support is designed to eliminate the presence of tube with a low natural frequency. Based on the improved upper tube bundle support, the modal analysis is performed and compared with that of System 80 + . Using the results of flow distribution and modal analysis, the two mechanisms of flow-induced vibration are investigated; fluid-elastic instability (FEI) and random turbulence excitation (RTE). (authors)

  11. Non-Integrated Standalone Tests of APR1400 Simulator

    International Nuclear Information System (INIS)

    Hwang, Su Hyun; Lee, Jeong Ik; Hong, Soon Joon; Lee, Byung Chul; Seo, Jeong Gwan; Lee, Myung Soo

    2007-01-01

    APR1400 being developed for the construction of New Kori 3 and 4 Units has improved safety and more economical efficiency compared with previous PWR. The ESF(Engineered Safety Features) newly introduced to enhance safety are as follows: DVI (Direct Vessel Injection), Fluidic Device, IRWST (In-containment Refueling Water Storage Tank). So the transient pattern of anticipated accidents will show different characteristics from previous PWR. There are multidimensional flow phenomena like as emergency core cooling coolant bypass discharge in the downcomer, downcomer boiling, and different safety injection characteristics due to fluidic device during LBLOCA. Also there is the phenomenon of critical flow due to the open of pressurizer POSRV (Pilot Operated Safety Relief valve) connected to IRWST and safety depressurization system and the prediction of discharge flow is very important. KEPRI is developing APR1400 simulator using RELAP-RT . RELAP-RT was developed by DS and S (Data systems and Solutions) based on RELAP5/MOD3.2. The improved features of RELAP-RT to function as a simulator are as follows: Add simulator functionality - Control by simulator executive - IC snap and reset capability - Back-track snap and reset capability - Fast time capability. Fast time capability(examples) - The rate of condensation has been limited. - Fictional choking model has been developed for internal junctions. - Wall heat transfer coefficients and heat fluxes has been limited. In this study, various NISTs (Non-Integrated Standalone Tests) were performed to verify the capability of RELAP-RT as APR1400 simulator by the comparison with RELAP5/MOD3.3

  12. Quality Control of Concrete Structure For APR1400 Construction

    International Nuclear Information System (INIS)

    Seo, Inseop; Song, Changhak; Kim, Duill

    2012-01-01

    Nuclear structure shall be constructed to protect internal facilities in the normal operation against external accidents such as the radiation shielding, earthquakes and to be leak-proof of radioactive substances to the external environment in case of loss of coolants. containment and auxiliary building of nuclear power plants are built in reinforced concrete structures to maintain these protection functions. Nuclear structures shall be designed to ensure soundness in operation since they are located on the waterfront where is easy do drain the cooling water and so deterioration and damage of concrete structures caused by seawater can occur. Durability is ensured for concrete structures of APR1400, a Korea standard NPP, in compliance with all safety requirements. In particular, owners perform quality control directly on the production and pouring of cast in place concrete for the concrete structure construction to make sure concrete structures established with quality homogeneity and durability. This report is to look into the quality control standard and management status of cast in place concrete for APR1400 construction

  13. Vibration Analysis for Steam Dryer of APR1400 Steam Generator

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sung-heum; Ko, Doyoung [KHNP CRI, Daejeon (Korea, Republic of); Cho, Minki [Doosan Heavy Industry, Changwon (Korea, Republic of)

    2016-10-15

    This paper is related to comprehensive vibration assessment program for APR1400 steam generator internals. According to U.S. Nuclear Regulatory Commission, Regulatory Guide 1.20 (Rev.3, March 2007), we conducted vibration analysis for a steam dryer as the second steam separator of steam generator internals. The vibration analysis was performed at the 100 % power operating condition as the normal operation condition. The random hydraulic loads were calculated by the computational fluid dynamics and the structural responses were predicted by power spectral density analysis for the probabilistic method. In order to meet the recently revised U.S. NRC RG 1.20 Rev.3, the CVAP against the potential adverse flow effects in APR1400 SG internals should be performed. This study conducted the vibration response analysis for the SG steam dryer as the second moisture separator at the 100% power condition, and evaluated the structural integrity. The predicted alternating stress intensities were evaluated to have more than 17.78 times fatigue margin compared to the endurance limit.

  14. Application of Nuclear Application Programs to APR1400 Simulator

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Myeong Soo; Hong, Jin Hyuk

    2012-01-01

    Advanced Power Reactor 1400MWe (APR1400) simulator has been developed and installed at Kori Training Center for operators of ShinKori no.3, 4 nuclear power plant by Korea Hydro and Nuclear Power,s Central Research Institute (KHNP CRI). NAPS (Nuclear Application Programs) is a computerbased system which provides operators with past and real-time information for monitoring and controlling NSSS (Nuclear Steam Supply System), BOP (Balance Of Plant) and Electric system. NAPS consists of several programs such as COLSS (Core Operating Limit Supervisory System), SPADES+ (Safety Parameter Display and Evaluation System), CEA (Control Element Assembly) Application Program, and so on. Each program makes calculations based on its own algorithm and provides information available for operation. In order to use NAPS programs with a simulator even though they are being used in a real plant, they should be modified to add several simulation functions such as reset, snap, run/freeze and backtrack required by ANSI/ANS-3.5 to the original NAPS functionality. On top of that, interfacing programs should be developed for the data communication between respective NAPS programs and simulator sever. The purpose of this paper is to provide the overall architecture of the communication system between NAPS and simulator model, and to describe the method to apply NAPS to APR1400 simulator

  15. Application of Standardized ITAAC to the APR1400 Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Deogji; Kim, Yunho [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Design certification applications (DCAs) submitted pursuant to 10 CFR Part 52 contain two tiers of information, Tier 1 and Tier 2. Tier 1 contains information that is to be certified through rulemaking, and includes the inspections, tests, analyses, and acceptance criteria (ITAAC). Tier 2 contains more detailed information and is the source for information included in Tier1. DC applicants have developed the ITAAC with their own format and contents. This has caused the ineffectiveness of the review process by Nuclear Regulatory Commission (NRC) at the design certification stage. Standardizing the format and content of Tier 1 and ITAAC will achieve greater efficiency and effectiveness for Tier 1 and ITAAC development and NRC review, and for ITAAC implementation and verification. NRC provided the proposed standardized ITAAC for APR1400, and KHNP is considering the application of the proposed ITAAC. The strategy for application of the NRC proposed standardized ITAAC to the APR1400 design certification is now under developing, and a meeting with NRC to review the NRC proposed standardized ITAAC is expected to be held in the near future. In this review process, establishment of industry position on the NRC proposed standardized ITAAC is very important. The support from NEI and US industry is expected to be gained.

  16. Application of Standardized ITAAC to the APR1400 Design Certification

    International Nuclear Information System (INIS)

    Kang, Deogji; Kim, Yunho

    2016-01-01

    Design certification applications (DCAs) submitted pursuant to 10 CFR Part 52 contain two tiers of information, Tier 1 and Tier 2. Tier 1 contains information that is to be certified through rulemaking, and includes the inspections, tests, analyses, and acceptance criteria (ITAAC). Tier 2 contains more detailed information and is the source for information included in Tier1. DC applicants have developed the ITAAC with their own format and contents. This has caused the ineffectiveness of the review process by Nuclear Regulatory Commission (NRC) at the design certification stage. Standardizing the format and content of Tier 1 and ITAAC will achieve greater efficiency and effectiveness for Tier 1 and ITAAC development and NRC review, and for ITAAC implementation and verification. NRC provided the proposed standardized ITAAC for APR1400, and KHNP is considering the application of the proposed ITAAC. The strategy for application of the NRC proposed standardized ITAAC to the APR1400 design certification is now under developing, and a meeting with NRC to review the NRC proposed standardized ITAAC is expected to be held in the near future. In this review process, establishment of industry position on the NRC proposed standardized ITAAC is very important. The support from NEI and US industry is expected to be gained

  17. Analysis of a 12-Finger Rod Drop using RETRAN/MASTER Code System for APR1400

    International Nuclear Information System (INIS)

    Yu, Keuk Jong; You, Sung Chang; Kim, Han Gon

    2009-01-01

    The Optimized Power Reactor 1000 (OPR1000) has 4-finger and 12-finger Control Element Assemblies (CEAs). When the 12-finger CEA is dropped, Core Protection Calculator System (CPCS) shuts down the reactor to prevent fuel damage that could occur from the sudden reactor power peaking. By contrast, the improved CPCS of Advanced Power Reactor 1400 (APR1400), which has systems similar to those of the OPR1000, decreases reactor power rapidly using its Reactor Power Cutback System (RPCS) to avoid unwanted reactor trips caused by the CPCS during a 12- finger CEA drop event. RETRAN is a best-estimate code for transient analysis of Non-LOCA. The RETRAN control logic, which includes the function of reducing reactor power during a 12-Finger CEA drop, has been developed for the APR1400. A MATRAN program has also been developed. MATRAN is the interface program for realtime processing to connect RETRAN with MASTER code which is a nuclear analysis and design code. MATRAN supplies adequate feedback reactivities from the MASTER code to RETRAN code. The purpose of this study is to analyze the behavior of a nuclear reactor core and its primary system using conventional RETRAN analysis procedure and MATRAN program analysis procedure during a 12- finger CEA drop. In addition, the axial power distribution and Axial Shape Index (ASI) are produced by the MATRAN program and they are confirmed as within operation limits

  18. Extended Station Blackout Analyses of an APR1400 with MARS-KS

    International Nuclear Information System (INIS)

    Kim, WoongBae; Jang, HyungWook; Oh, Seungjong; Lee, Sangyong

    2016-01-01

    The Fukushima Dai-ichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electricity required for essential systems during a station blackout is provided from the emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6 and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating of extended station blackout scenarios, the best estimate MARS-KS was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study was performed on reactor coolant pump seal leakage

  19. Extended station blackout analyses of an APR1400 with MARS-KS

    Directory of Open Access Journals (Sweden)

    Kim Woongbae

    2016-01-01

    Full Text Available The Fukushima Daiichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electric energy required for essential systems during a station blackout is provided from emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6, and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating extended station blackout scenarios, the best estimate MARS-KS computer code was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study on reactor coolant pump seal leakage was carried out.

  20. Extended Station Blackout Analyses of an APR1400 with MARS-KS

    Energy Technology Data Exchange (ETDEWEB)

    Kim, WoongBae; Jang, HyungWook; Oh, Seungjong; Lee, Sangyong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    The Fukushima Dai-ichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electricity required for essential systems during a station blackout is provided from the emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6 and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating of extended station blackout scenarios, the best estimate MARS-KS was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study was performed on reactor coolant pump seal leakage.

  1. Analysis of Turbine Load Rejection for APR1400 using SPACE

    International Nuclear Information System (INIS)

    Kim, Sang Jin; Park, Chan Eok; Choi, Jong Ho; Lee, Gyu Cheon

    2016-01-01

    Turbine Load Rejection event is one of the Performance Related Design Basis Event (PRDBE) that can be stabilized using plant control systems without any safety system actuation. The initiation of the event is turbine load rejection from 100% to 5% in 0.019 seconds. The NSSS control systems of APR1400 is composed of the Power Control System (PCS) and the Process-Component Control System (P-CCS). The PCS includes Reactor Regulating System (RRS), Reactor Power Cutback System (RPCS) and Digital Rod Control System (DRCS). The P-CCS includes the Pressurizer Pressure Control System (PPCS), the Pressurizer Level Control System (PLCS), the Feedwater Control System (FWCS) and the Steam Bypass Control System (SBCS). Turbine load rejection results in the increase of secondary pressure due to sudden blocking of steam flow to turbine. Then the Reactor Coolant System (RCS) cooling through steam generators is decreased rapidly and the RCS temperature will be increased. Turbine load rejection is a typical event to test NSSS control systems since it requires the automatic response of all major NSSS control systems. It is shown that the NSSS control systems of APR1400 have the capability to stabilize the plant without any safety system actuation for turbine load rejection event. This analysis results show that SPACE code has the capability to analyze the turbine load rejection event. However, further validation is necessary for other PRDBEs such as Two Main Feedwater Pumps Trip, Turbine Load Step Change and Turbine Load Ramp Down (5%/min) to verify the capability of SPACE for the full range of performance analyses

  2. Analysis of Turbine Load Rejection for APR1400 using SPACE

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Jin; Park, Chan Eok; Choi, Jong Ho; Lee, Gyu Cheon [KEPCO Engineering and Construction Co. Ltd., Deajeon (Korea, Republic of)

    2016-10-15

    Turbine Load Rejection event is one of the Performance Related Design Basis Event (PRDBE) that can be stabilized using plant control systems without any safety system actuation. The initiation of the event is turbine load rejection from 100% to 5% in 0.019 seconds. The NSSS control systems of APR1400 is composed of the Power Control System (PCS) and the Process-Component Control System (P-CCS). The PCS includes Reactor Regulating System (RRS), Reactor Power Cutback System (RPCS) and Digital Rod Control System (DRCS). The P-CCS includes the Pressurizer Pressure Control System (PPCS), the Pressurizer Level Control System (PLCS), the Feedwater Control System (FWCS) and the Steam Bypass Control System (SBCS). Turbine load rejection results in the increase of secondary pressure due to sudden blocking of steam flow to turbine. Then the Reactor Coolant System (RCS) cooling through steam generators is decreased rapidly and the RCS temperature will be increased. Turbine load rejection is a typical event to test NSSS control systems since it requires the automatic response of all major NSSS control systems. It is shown that the NSSS control systems of APR1400 have the capability to stabilize the plant without any safety system actuation for turbine load rejection event. This analysis results show that SPACE code has the capability to analyze the turbine load rejection event. However, further validation is necessary for other PRDBEs such as Two Main Feedwater Pumps Trip, Turbine Load Step Change and Turbine Load Ramp Down (5%/min) to verify the capability of SPACE for the full range of performance analyses.

  3. Transversal of Procedure Elements in a Computerized Procedure System

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Yeonsub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    APR1400 MCR(Main Control Room) has introduced CPS(Computerized Procedure System). APR400 CPS is framed with overview pane, step detail pane, and monitoring pane. The overview shows the step in one dimensional array. Diagram in the step detail pane is called as flowlogic diagram. The flowlogic diagram has advantage of being intuitive and not being segmented so that the interfaces are easy to follow and understand. While developing CPS software or training operators these interfaces, however, there is still areas to refine behaviors of flowlogic diagram. If flowlogic diagram has contingency instructions, it is sometime difficult to interpret it properly. Therefore this paper is trying to explain behavior of flowlogic diagram in view of procedure elements. Procedure execution can be called as transversal of steps and instructions in flowlogic diagram. Both hierarchy of procedures elements and flowlogic diagram provides useful framework to test transversal with completeness. Navigation button behaviors are interpreted in view of flowlogic diagram. The framework and flowlogic diagram can be further applied to improve CPS user interfaces.

  4. Development of Core Simulator (CoSi) for APR1400 And Analysis of LPPT Result using APR1400-CoSi

    International Nuclear Information System (INIS)

    Moon, Sang-Rae; Kim, Yong-Bae; Lee, Eun-Ki

    2014-01-01

    According to NRC guidelines, Low Power Physics Test (LPPT) is required to be performed in low temperature/low pressure (160 .deg. C/42.2 kg/cm 2 ) as well as NOT/NOP (291.3 .deg. C/158.2 kg/cm 2 ) because Shin-Kori Unit 3 is FOAK nuclear power plant. Low Power Physics Test (LPPT) is essential to verify the nuclear design and robustness of reactor safety. LPPT consists of initial criticality, Point of Adding Heat (POAH), All Rod Out (ARO) Boron Concentration, Isothermal Temperature Coefficient (ITC), Control Rod Worth measurements and so on. KHNP-CRI has developed the Core Simulator for APR1400 (APR1400-CoSi) in order to improve the ability performing the LPPT. Especially, APR1400-CoSi has enhanced capability to calculate the full Core neutronic parameters by revising RAST-K that is three dimensional real time core kinetic program. APR1400-CoSi has been developed for education-training of Low Power Physics Test(LPPT). Particularly, APR1400-CoSi has an enhanced capability to calculate the full core neutronic parameters by revising RAST-K which is a three dimensional real time core kinetics program. Low Power Physics Test (LPPT) was performed using APR1400-CoSi and the results showed very similar values with the predicted ones. In other words, the initial core model of Shin-Kori Unit 3 in APR1400-CoSi system has been verified to be appropriate enough. Also, it was confirmed that the test range of Low Power Physics Test (LPPT) reamains effective even though the largest incremental bank reactivity is inserted in core by analyzing the power change during the rod SWAP test

  5. Analysis on Containment Response Following a LBLOCA of APR1400

    International Nuclear Information System (INIS)

    Han, Kyu Hyun

    2016-01-01

    The predictions are in good agreements with the final safety analysis report, which implies the containment integrity is maintained during or after an accident like loss of coolant accident. In this study, the CONTEMPT-LT/028 was used to calculate the pressure and temperature, and in the follow-up study, CONTAIN 2.0 will be used for the pressure and temperature predictions in APR1400 reactors. Shin-Hanul Units 1 and 2 may possess different characteristics of peak pressure and temperature in containment following a large break loss-of-coolant-accident. To assess the important performance independently and to compare with prediction results presented in the final safety analysis report (FSAR) of Shin-Hanul Units 1 and 2 might be helpful to regulatory review for identifying validity of the FSAR. The end of blowdown (EOB) time during a LOCA could largely affect the peak pressure and temperature in the containment. This paper provides CONTEMPT-LT/028 prediction of the peak pressure and temperature of Shin-Hanul Units 1 and 2 following a large break loss-of-coolant-accident and compares with licensee's prediction results.

  6. Analysis on Containment Response Following a LBLOCA of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kyu Hyun [KINS, Daejeon (Korea, Republic of)

    2016-05-15

    The predictions are in good agreements with the final safety analysis report, which implies the containment integrity is maintained during or after an accident like loss of coolant accident. In this study, the CONTEMPT-LT/028 was used to calculate the pressure and temperature, and in the follow-up study, CONTAIN 2.0 will be used for the pressure and temperature predictions in APR1400 reactors. Shin-Hanul Units 1 and 2 may possess different characteristics of peak pressure and temperature in containment following a large break loss-of-coolant-accident. To assess the important performance independently and to compare with prediction results presented in the final safety analysis report (FSAR) of Shin-Hanul Units 1 and 2 might be helpful to regulatory review for identifying validity of the FSAR. The end of blowdown (EOB) time during a LOCA could largely affect the peak pressure and temperature in the containment. This paper provides CONTEMPT-LT/028 prediction of the peak pressure and temperature of Shin-Hanul Units 1 and 2 following a large break loss-of-coolant-accident and compares with licensee's prediction results.

  7. Aircraft Impact Assessment of APR1400 Reactor Containment Building

    International Nuclear Information System (INIS)

    Moon, Il Hwan; Kim, Do Yeon; Kim, Jae Hee; Kim, Sang Yun

    2011-01-01

    The implementation of a protection to withstand aircraft impact on safety-related structures and systems is basically based on a probabilistic evaluation for each site, if the licensing body doesn't require a deterministic approach. Existing nuclear power plants in Korea were designed based on the probabilistic approach, and the aircraft impact hazard remained less than a probability of 10 -7 . However, a man-made aircraft impact have been considered as a possible external accident for the nuclear power plant. New plant designs that are to be constructed in the U.S. after July 2009 must consider the effect of impact from a large commercial aircraft according to the requirements of 10 CFR 50.150. Especially, Reactor Containment Building (RCB) housing the safety-related equipment and fuels should be protected safely against aircraft crash without perforation and scabbing failure of external wall. APR1400 RCB is constructed as a prestressed concrete containment vessel (PCCV) which is surrounded by the auxiliary building housing additional safety-related equipment and other systems. In this study, the aircraft impact analyses for the RCB are carried out using Riera forcing function and aircraft model. Considered external wall thickness is 4 ft 6 in. for the cylindrical wall and 4 ft for the dome. Actual strengths of concrete and steel are considered as the material properties. For these analyses, the dynamic increment factor and concrete aging effect are considered in accordance with NEI 07-13(2011)

  8. Fuel assembly design for APR1400 with low CBC

    Energy Technology Data Exchange (ETDEWEB)

    Hah, Chang Joo, E-mail: changhah@kings.ac.kr [Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-04-29

    APR 1400 is a PWR (Pressurized Water Reactor) with rated power of 3983 MWth and 241 assemblies. Recently, demand for extremely longer cycle up to 24 months is increasing with challenge of higher critical boron concentration (CBC). In this paper, assembly design method of selecting Gd-rods is introduced to reduce CBC. The purpose of the method is to lower the critical boron concentration of the preliminary core loading pattern (PLP), and consequently to achieve more negative or less positive moderator temperature coefficient (MTC). In this method, both the ratio of the number of low-Gd rod to the number of high-Gd rod (r) and assembly average Gd wt% (w) are the decision variables. The target function is the amount of soluble boron concentration reduction, which can be converted to Δk{sub TARGET}. A set of new designed fuel assembly satisfies an objective function, min [f=∑{sub i}(Δk{sub FA}−Δk{sub i})], and enables a final loading pattern to reach a target CBC. The constraints required to determine a set of Δk are physically realizable pair, (r,w), and the sum of Δk of new designed assemblies as close to Δk{sub TARGET} as possible. New Gd-bearing assemblies selected based on valid pairs of (r,w) are replaced with existing assemblies in a PLP. This design methodology is applied to Shin-Kori Unit 3 Cycle 1 used as a reference model. CASMO-3/MASTER code is used for depletion calculation. CASMO-3/MASTER calculations with new designed assemblies produce lower CBC than the expected CBC, proving that the proposed method works successful.

  9. Study on Maintenance Personnel Development Plan For The Exported APR1400 Commissioning

    International Nuclear Information System (INIS)

    Cho, Sungbae; Kim, Jongdae; Jun, Hokwang; Hwang, Inok; Kang, Jaeyuel

    2012-01-01

    This paper indicates ways to develop maintenance personnel for the exported APR1400 commissioning. The exported APR1400 has not been experienced ay maintenance yet, and requirements for maintenance personnel have not been clarified yet. Based on sound maintenance experience, KEPCO Plant Service and Engineering Company (KEPCO KPS) has studied on maintenance training and career requirement to establish a development plan of the maintenance personnel for the exported nuclear power plant. By defining manpower and training requirement, and mobilization plan, we expect to secure reliability of the exported APR1400

  10. Response Time Analysis and Test of Protection System Instrument Channels for APR1400 and OPR1000

    International Nuclear Information System (INIS)

    Lee, Chang Jae; Han, Seung; Yun, Jae Hee; Baek, Seung Min; Lee, Sang Jeong

    2015-01-01

    Safety limits are required to maintain the integrity of physical barriers designed to prevent the uncontrolled release of radioactive materials in nuclear power plants. The safety analysis establishes two critical constraints that include an analytical limit in terms of a measured or calculated variable, and a specific time after the analytical limit is reached to begin protective action. Keeping with the nuclear regulations and industry standards, satisfying these two requirements will ensure that the safety limit will not be exceeded during the design basis event, either an anticipated operational occurrence or a postulated accident. Various studies on the setpoint determination methodology for the safety-related instrumentation have been actively performed to ensure that the requirement of the analytical limit is satisfied. In particular, the protection setpoint methodology for the advanced power reactor 1400 (APP1400) and the optimized power reactor 1000 (OPR1000) has been recently developed to cover both the design basis event and the beyond design basis event. The developed setpoint methodology has also been quantitatively validated using specific computer programs and setpoint calculations. However, the safety of nuclear power plants cannot be fully guaranteed by satisfying the requirement of the analytical limit. In spite of the response time verification requirements of nuclear regulations and industry standards, it is hard to find the studies on the systematically integrated methodology regarding the response time evaluation. In cases of APR1400 and OPR1000, the response time analysis for the plant protection system is partially included in the setpoint calculation and the response time test is separately performed via the specific plant procedure. The test technique has a drawback which is the difficulty to demonstrate completeness of timing test. The analysis technique has also a demerit of resulting in extreme times that not actually possible. Thus

  11. Response Time Analysis and Test of Protection System Instrument Channels for APR1400 and OPR1000

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Jae; Han, Seung; Yun, Jae Hee; Baek, Seung Min [Department of Instrumentation and Control System Engineering, KEPCO Engineering and Construction, Daejeon (Korea, Republic of); Lee, Sang Jeong [Department of Electronics Engineering, Chungnam National University, Daejeon (Korea, Republic of)

    2015-07-01

    Safety limits are required to maintain the integrity of physical barriers designed to prevent the uncontrolled release of radioactive materials in nuclear power plants. The safety analysis establishes two critical constraints that include an analytical limit in terms of a measured or calculated variable, and a specific time after the analytical limit is reached to begin protective action. Keeping with the nuclear regulations and industry standards, satisfying these two requirements will ensure that the safety limit will not be exceeded during the design basis event, either an anticipated operational occurrence or a postulated accident. Various studies on the setpoint determination methodology for the safety-related instrumentation have been actively performed to ensure that the requirement of the analytical limit is satisfied. In particular, the protection setpoint methodology for the advanced power reactor 1400 (APP1400) and the optimized power reactor 1000 (OPR1000) has been recently developed to cover both the design basis event and the beyond design basis event. The developed setpoint methodology has also been quantitatively validated using specific computer programs and setpoint calculations. However, the safety of nuclear power plants cannot be fully guaranteed by satisfying the requirement of the analytical limit. In spite of the response time verification requirements of nuclear regulations and industry standards, it is hard to find the studies on the systematically integrated methodology regarding the response time evaluation. In cases of APR1400 and OPR1000, the response time analysis for the plant protection system is partially included in the setpoint calculation and the response time test is separately performed via the specific plant procedure. The test technique has a drawback which is the difficulty to demonstrate completeness of timing test. The analysis technique has also a demerit of resulting in extreme times that not actually possible. Thus

  12. A Probability Analysis of the Generating Cost for EU-APR1400 Single Unit

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Gak Hyeon; Kim, Sung Hwan [KHNP CRI, Seoul (Korea, Republic of)

    2014-10-15

    The nuclear power plant market is expected to grow rapidly in order to address issues of global warming, reducing CO{sub 2} emissions and securing stable electricity supplies. Under these circumstances, the main primary goal of the EU-APR100 development is to ensure export competitiveness in the European countries. To this end, EU-APR1400 have been developed based one te APR1400 (Advanced Power Reactor, GEN Type) The EU-APR1400 adds many advanced design features to its predecessor, as outlined below in Table 1. In this simulation, the results of the generating cost of the EU-APR1400 single unit were determined using the probability cost analysis technique, the generating cost range was shown to be 56.16 ∼ 70.92 won/kWh.

  13. A Probability Analysis of the Generating Cost for EU-APR1400 Single Unit

    International Nuclear Information System (INIS)

    Ha, Gak Hyeon; Kim, Sung Hwan

    2014-01-01

    The nuclear power plant market is expected to grow rapidly in order to address issues of global warming, reducing CO 2 emissions and securing stable electricity supplies. Under these circumstances, the main primary goal of the EU-APR100 development is to ensure export competitiveness in the European countries. To this end, EU-APR1400 have been developed based one te APR1400 (Advanced Power Reactor, GEN Type) The EU-APR1400 adds many advanced design features to its predecessor, as outlined below in Table 1. In this simulation, the results of the generating cost of the EU-APR1400 single unit were determined using the probability cost analysis technique, the generating cost range was shown to be 56.16 ∼ 70.92 won/kWh.

  14. Current status of integrated HFE V and V system of APR1400

    International Nuclear Information System (INIS)

    Lee, M. S.; Hong, J. H.; Lee, S. H.; Lee, Y. K.

    2006-01-01

    The first Advanced Light Water Reactor called Advanced Power Reactor (APR1400) has many specific features such as passive safety features, digital I and C, and digitalized main control room design. This digital-based neo-concept main control room design needs comprehensive verification and validation process to get the license for construction. An integrated system for APR1400 MMIS design validation is under development by KEPRI with the participating of KHNP. The facility which is based on the NUREG/CR-6393 and ANS3.5 can simulate all of the dynamic functions and responses of APR1400, and measure the human factors by using conventional subject methods and measuring the operator's biological signals. This system will be used in human factors V and V process of the PRM (NUREG0711) of APR1400 MMIS design. (authors)

  15. Design characteristics of EU-APR1400 on-site power system

    International Nuclear Information System (INIS)

    Kim, D.H.; Kim, Y.S.; Kim, Y.S.

    2014-01-01

    In the global nuclear market, US and European design requirements have been largely used to develop the design of nuclear power plants(NPPs). The APR1400 design was developed on the basis of US regulatory guide and EPRI utility requirements document(URD). In order to enlarge the export market of APR1400, KHNP (Korea Hydro & Nuclear Power Co., Ltd) has developed the EU-APR1400 design which complies with the European nuclear design requirements. In this paper, the design characteristics of EU-APR1400 on-site power system developed according to the European design requirements of electrical power system are described. The European main design requirements of electrical power system involve 50 Hz rated frequency, 400/110 kV grid voltage, the application of the diversity and the redundancy, and so on. The EU-APR1400 on-site power system has been developed on the basis of these requirements. The representative designs include the redundancy, diversity, independence design, the emergency power supply design, the design for providing electrical power to the dedicated severe accident systems, and the design for European grid requirements. (author)

  16. Conceptual Designs for the Performance Improvement of APR1400 SIT and Preliminary Performance Evaluation

    International Nuclear Information System (INIS)

    Chu, In-Cheol; Kwon, Tae-Soon; Song, Chul-Hwa

    2008-01-01

    Some evolutionary type PWRs such as APR1400 and APWR adopt advanced safety injection tank (SIT). The SIT of APR1400 has a fluidic device (FD) which passively controls ECC water injection flow rate into reactor coolant system during refill and reflood phases of LB-LOCA (i.e., a high injection flow rate during the refill phase and a low injection flow rate during the reflood phase). The benefit of the FD is the elimination of the function of low pressure safety injection pump from the safety injection system. The flow controlling performance of the APR1400 FD was evaluated using a prototypical full-scale test facility, called VAPER (Valve Performance Evaluation Rig). Even though the performance of the APR1400 FD satisfied major design and licensing requirements, further improvement of the performance is expected such as the extension of total injection period, the delay of nitrogen gas discharge. Several conceptual designs have been being drawn out in order to improve the performance of the APR1400 SIT. The performance of some designs was evaluated using a small scale SIT test rig. The present paper introduces some of the conceptual designs and shows the performance evaluation experimental results

  17. Measurement techniques of local parameters in the downcomer boiling experiment of APR1400

    International Nuclear Information System (INIS)

    Lee, Eu Hwak

    2004-02-01

    In order to investigate boiling phenomena experimentally in the downcomer during LBLOCA with Direct Vessel Injection (DVI), which is a new Safety Injection System (SIS) of Advanced Power Reactor 1400 MW (APR1400), several parameters should be measured through the verification of their applicability. In this study, measurement techniques of the parameters are developed for the downcomer boiling experiment; local phase velocities, local void fraction and heat flux from the heated wall. The experiment has been performed with the heated wall, which has a thickness of 8.2 cm and a height of 32.5 cm and made of the same material as the prototype (APR1400) with chrome coating against rusting. The newly developed pitot tube is applied to the measurement of local liquid velocity and its calibration curve is obtained experimentally with the consideration of the effect according to water temperature and hole size changes. The developed pitot tube measures the local liquid velocity with 0.69 % deviation and it is confirmed that the water temperature and geometrical change does not affect the calibration curve. The high-speed camera and commercial software are used to measure the local vapor velocity with the accuracy of 0.06 m/sec per pixel and the procedure is confirmed in the present study. It turns out that the vapor velocity is insensitive to void size. High-speed camera and image processing are used to measure the local void fraction with the determined intensity criterion for distinguishing each phase and the results are compared with the bulk void fraction by differential pressure transmitters. In the actual experiment, the developed method is applied successfully and the results show that the criterion of intensity has little effect on local void fraction. And, it is observed that the tendency between the measured local and bulk void faction is maintained with time. In order to measure heat flux from the heated wall, two heat flux measurement techniques are developed

  18. Application of the risk-informed methodology for APR1400 P-T limits curve

    Energy Technology Data Exchange (ETDEWEB)

    Kim, K.; Namgung, I. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-07-01

    A reactor pressure vessel (RPV) in a nuclear power plant has operational limits of pressure and temperature to prevent a potential drastic propagation of cracks due to brittle fracture. We call it a pressure-temperature limits curve (P-T limits curve). Appendix G of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, provides deterministic procedures to develop the P-T limits curve for the reactor pressure vessel. Recently, an alternative risk-informed methodology has been added in the ASME Code. Risk-informed means that we can consider insights from a probabilistic risk assessment by using this methodology. This alternative methodology provides a simple procedure to develop risk-informed P-T limits for heat up, cool down, and hydrostatic test events. The risk-informed P-T limits curve is known to provide more operational flexibility, particularly for reactor pressure vessels with relatively high irradiation levels and radiation sensitive materials. In this paper, we developed both the deterministic and a risk-informed P-T limits curve for an APR1400 reactor using Appendix G of the ASME Code, Section XI and compare the results in terms of additional operational margin. (author)

  19. GOTHIC Simulation of APR1400 Auxiliary Charging Pump room heat up

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Hui-Un; Heo, Sun [KHNP, Daejeon (Korea, Republic of)

    2014-10-15

    As a part of the Advanced Power Reactor 1400 (APR1400) U. S. Nuclear Regulatory Commission Design Certification (NRC DC) project, we have been investigating Auxiliary Charging Pump (ACP) room heat up. With reference to the design specification of the ACP room, we determined input information and developed a GOTHIC model of the APR1400 ACP room. This calculation model is described herein, and representative results from the calculation are presented as well. The results of the present paper are used to determine the integrity of ACP operating in the accident. APR 1400 GOTHIC model was developed for ACP room heat up calculation. Calculation results confirm that door opening is cooling the room properly. It is found that the difference due to the surface option of heat conductors is insignificant. Based on this result, further studies should be performed to confirm integrity of ACP.

  20. Seismic analysis of APR1400 RCS for site envelope using big mass method

    International Nuclear Information System (INIS)

    Kim, J. Y.; Jeon, J. H.; Lee, D. H.; Park, S. H.

    2002-01-01

    One of design concepts of APR1400 is the site envelope considering various soil sites as well as rock site. The KSNP's are constructed on the rock site where only the translational excitations are directly transferred to the plant. On the other hand, the rotational motions affect the responses of the structures in the soil cases. In this study, a Big Mass Method is used to consider rotational motions as excitations at the foundation in addition to translational ones to obtain seismic responses of the APR1400 RCS main components. The seismic analyses for the APR1400 excited simultaneously by translation and rotational motions were performed. The results show that the effect of soil sites is not significant for the design of main components and supports of the RCS, but it may be considerable for the design of reactor vessel internals, piping, and nozzles which have lower natural frequencies

  1. Computerized procedures system

    Science.gov (United States)

    Lipner, Melvin H.; Mundy, Roger A.; Franusich, Michael D.

    2010-10-12

    An online data driven computerized procedures system that guides an operator through a complex process facility's operating procedures. The system monitors plant data, processes the data and then, based upon this processing, presents the status of the current procedure step and/or substep to the operator. The system supports multiple users and a single procedure definition supports several interface formats that can be tailored to the individual user. Layered security controls access privileges and revisions are version controlled. The procedures run on a server that is platform independent of the user workstations that the server interfaces with and the user interface supports diverse procedural views.

  2. Effectiveness of External Reactor Vessel Cooling (ERVC) strategy for APR1400 and issues of phenomenological uncertainties

    International Nuclear Information System (INIS)

    Oh, S.J.; Kim, H.T.

    2007-01-01

    The APR1400(Advanced Power Reactor 1400) is an evolutionary advanced light water reactor with rated thermal power of 4000 MWt. For APR1400, External Reactor Vessel Cooling (ERVC) is adopted as a primary severe accident management strategy for in-vessel retention (IVR) of corium. The ERVC is a method of IVR by submerging the reactor vessel exterior. At the early stage of the APR1400 design, only ex-vessel cooling, cooling of the core melt outside the vessel after vessel is breached, is considered based on the EPRI Utility Requirement Document for Evolutionary LWR. However, based on the progress in implementation of Severe Accident Management Guidance (SAMG) for operating plants, as well as the research findings related to ERVC, ERVC strategy is adopted as a part of key severe accident management strategies. To improve its success, the strategy is reviewed and we implemented necessary design arrangement to increase its usefulness in managing the severe accident. In this paper, we examine the evolution of ERVC concept and its implementation in APR1400. Then, we review possible approach, including Risk-Oriented Accident Analysis Methodology (ROAAM), to evaluate the effectiveness of the strategy. (authors)

  3. An investigation of major influences on the seismic response of APR1400 reactor vessel internals - 15145

    International Nuclear Information System (INIS)

    Byun, Y.J.; Kim, J.G.; Sung, K.K.; Lee, D.H.

    2015-01-01

    This paper deals with 3 topics concerning the APR1400 reactor vessel internals (RVI) seismic analysis: nonlinear problems, approaches to account for uncertainties of seismic model, and dynamic responses to various seismic excitations. First, the noticeable nonlinear characteristics of the RVI seismic model are discussed, and the modeling methods for properly simulating the nonlinear behaviors of RVI under seismic loads are presented. By applying these methods to the seismic model, the seismic analysis can correctly predict the dynamic response of RVI. Next, two approaches to account for the uncertainties of seismic model are evaluated: the time history broadening method, and the sensitivity analysis based on NUREG-0800, Section 4.2, Appendix A. From the evaluation results, it is confirmed that the time history broadening method employed in the seismic analysis of APR1400 RVI sufficiently accounts for the uncertainty of seismic model. Finally, the response characteristics of APR1400 RVI to various seismic excitations are investigated. The seismic excitations corresponding to various soil profiles, including the effects of cracked and un-cracked concrete stiffness on the reactor containment building structure, are used as forcing functions. From this study, the effects of various site conditions on the dynamic response of APR1400 RVI are identified. As a result, the enveloped seismic responses obtained from this study will contribute to the development of RVI seismic design that covers a wide range of potential site conditions. (authors)

  4. System Response Analysis of Rod Ejection Accident for APR1400 Using KNAP Hot Spot Model

    International Nuclear Information System (INIS)

    Kim, Yo-Han; Ha, Sang-Jun; Jun, Hwang-Yong

    2006-01-01

    Korea Electric Power Research Institute (KEPRI) has been developed the non-loss-of-coolant accident (non- LOCA) analysis methodology, called as the Korea Non- LOCA Analysis Package (KNAP), for the typical Optimized Power Reactor 1000 (OPR1000) plants. Considering current licensing methodology conducted by ABB-CE, however, the KNAP could be applied to Advanced Power Reactor 1400 (APR1400) also. In spite of some difference in design concepts of two plant types, there is a close resemblance between their nuclear steam supply systems (NSSS). So, in this study, the rod ejection accident (REA) event was analyzed using KNAP hot spot model (HSM) for APR1400 to estimate the feasibility of the application and the results were compared with those given in APR1400 Standard Safety Analysis Report (SSAR), which were calculated using the CESEC-III and STRIKIN-II code of ABB-CE. Through the study, it was concluded that the KNAP could be applicable to APR1400 on the view point of REA

  5. Preliminary Design of Optimized Reactor Insulator for Severe Accident Mitigation of APR1400

    International Nuclear Information System (INIS)

    Heo, Sun; Lee, Jae-Gon; Kang, Yong-Chul

    2007-01-01

    APR1400, a Korean evolutionary advance light water reactor, has many advanced safety feature to prevent and mitigate of design basis accident (DBA) and severe accident. When reactor cooling system (RCS) fails to cooling its core, the core melted down and the molten core gathers together on bottom of reactor vessel. The molten core hurts reactor vessel and is released to containment, which raises the release of radioactive isotopes and the heating of the containment atmosphere. Finally, the corium is accumulated in the bottom of reactor cavity and it also raises the Molten Core and Concrete Interaction (MCCI) and the heating of containment atmosphere. There are two strategies to cooling molten core. Those are in-vessel retention and ex-vessel cooling. At the early stage of APR1400 design, only ex-vessel cooling which is cooling of the molten core outside the vessel after vessel failure is considered based on EPRI Utility Requirement Document (URD) for Evolutionary LWR. However, a need has been arisen to reflect current research findings on severe accident phenomena and mitigation technologies to Korean URD and IVRERVC (In-Vessel corium Retention using Ex-Reactor Vessel Cooling) was adopted APR1400. The ERVC is not considered as a licensing design basis but based on the defense-in-depth principle and safety margin basis, which is the top-tier requirement of the severe accident mitigation design as stated in the KURD. The Severe Accident Management strategy for APR1400 is intended to aid the plant operating staff to secure reactor vessel integrity in the early stage of the severe accident. As a part of a design implementation of IVR-ERVC for APR1400, we developed the preliminary design requirement, design specification and conceptual design

  6. Features of Computerized Procedure System of Shin-Kori unit 5 and 6

    International Nuclear Information System (INIS)

    Seong, Nokyu; Jung, Yeonsub; Sung, Chanho

    2016-01-01

    The Computerized Procedure System (CPS) is one of the Man Machine Interface (MMI) resources of Main Control Room (MCR) of the Advanced Power Reactor 1400 (APR1400). The CPS has been continuously improved since it was installed in Shin-Kori unit 3 and 4. The Korea Hydro Nuclear Power Central Research Institute (KHNP CRI) has found the points of improvement of CPS through CPS centered Human Factors Engineering Verification and Validation (HFE V and V) and Operating Experience Review (OER) of reference power plant. This paper shows the main features of CPS of Shin-Kori 5 and 6 unit. This paper shows the main features of CPS of Shin-Kori 5 and 6. These are some of improvements of CPS. This prototype of CPS currently is implementing in CRI. The respective function can be more detailed after testing the prototype. These features will be applied to Shin-Kori 5 and 6 CPS after HFE V and V

  7. Features of Computerized Procedure System of Shin-Kori unit 5 and 6

    Energy Technology Data Exchange (ETDEWEB)

    Seong, Nokyu; Jung, Yeonsub; Sung, Chanho [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The Computerized Procedure System (CPS) is one of the Man Machine Interface (MMI) resources of Main Control Room (MCR) of the Advanced Power Reactor 1400 (APR1400). The CPS has been continuously improved since it was installed in Shin-Kori unit 3 and 4. The Korea Hydro Nuclear Power Central Research Institute (KHNP CRI) has found the points of improvement of CPS through CPS centered Human Factors Engineering Verification and Validation (HFE V and V) and Operating Experience Review (OER) of reference power plant. This paper shows the main features of CPS of Shin-Kori 5 and 6 unit. This paper shows the main features of CPS of Shin-Kori 5 and 6. These are some of improvements of CPS. This prototype of CPS currently is implementing in CRI. The respective function can be more detailed after testing the prototype. These features will be applied to Shin-Kori 5 and 6 CPS after HFE V and V.

  8. The comparison between layout and design of APR1400 MCR and EPRI requirement

    International Nuclear Information System (INIS)

    Suharyo Widagdo; Darlis; Sigit Santoso; T J Suryono

    2013-01-01

    A good man-machine interface system is needed by a nuclear power reactor because of its complexity and high safety factor. The man-machine interface system is centralized in the main control room (MCR). All of monitoring and controlling activity to keep the installation operation safety can be done from this place. In order to increase its ability in monitoring and controlling a hard effort to raise the interface system to the highest possible level is done not only by using the latest computer technology and instrumentation system but also using Human Engineering, as well. The paper aims to compare the lay out and design the APR1400 MCR and the requirement from EPRI about main control room lay out and design as response of TMI-2 accident. We can see from the discussion that the design of the MCR of APR1400 have been applied the request of EPRI. (author)

  9. Calculation of fuel and moderator temperature coefficients in APR1400 nuclear reactor by MVP code

    International Nuclear Information System (INIS)

    Pham Tuan Nam; Le Thi Thu; Nguyen Huu Tiep; Tran Viet Phu

    2014-01-01

    In this project, these fuel and moderator temperature coefficients were calculated in APR1400 nuclear reactor by MVP code. APR1400 is an advanced water pressurized reactor, that was researched and developed by Korea Experts, its electric power is 1400 MW. The neutronics calculations of full core is very important to analysis and assess a reactor. Results of these calculation is input data for thermal-hydraulics calculations, such as fuel and moderator temperature coefficients. These factors describe the self-safety characteristics of nuclear reactor. After obtaining these reactivity parameters, they were used to re-run the thermal hydraulics calculations in LOCA and RIA accidents. These thermal-hydraulics results were used to analysis effects of reactor physics parameters to thermal hydraulics situation in nuclear reactors. (author)

  10. The effect of nodalization and temperature of reactor upper region: Sensitivity analysis for APR-1400 LBLOCA

    International Nuclear Information System (INIS)

    Kang, Dong Gu

    2017-01-01

    Highlights: • The nodalization of APR-1400 was modified to reflect the characteristic of upper region temperature. • The effect of nodalization and temperature of reactor upper region on LBLOCA consequence was evaluated. • The modification of nodalization is an essential prerequisite in APR-1400 LBLOCA analysis. - Abstract: In best estimate (BE) calculation, the definition of system nodalization is important step influencing the prediction accuracy for specific thermal-hydraulic phenomena. The upper region of reactor is defined as the region of the upper guide structure (UGS) and upper dome. It has been assumed that the temperature of upper region is close to average temperature in most large break loss of coolant accident (LBLOCA) analysis cases. However, it was recently found that the temperature of upper region of APR-1400 reactor might be little lower than or similar to hot leg temperature through the review of detailed design data. In this study, the nodalization of APR-1400 was modified to reflect the characteristic of upper region temperature, and the effect of nodalization and temperature of reactor upper region on LBLOCA consequence was evaluated by sensitivity analysis including best estimate plus uncertainty (BEPU) calculation. In basecase calculation, in case of modified version, the peak cladding temperature (PCT) in blowdown phase became higher and the blowdown quenching (or cooling) was significantly deteriorated as compared to original case, and as a result, the cladding temperature in reflood phase became higher and the final quenching was also delayed. In addition, thermal-hydraulic parameters were compared and analyzed to investigate the effect of change of upper region on cladding temperature. In BEPU analysis, the 95 percentile PCT used in current regulatory practice was increased due to the modification of upper region nodalization, and it occurred in the reflood phase unlike original case.

  11. Critical heat flux for APR1400 lower head vessel during a severe accident

    International Nuclear Information System (INIS)

    Noh, Sang W.; Suh, Kune Y.

    2013-01-01

    Highlights: ► Studied boiling on downward-facing hemispherical vessel with asymmetric thermal insulator. ► Scaled the APR1400 lower head linearly down by 1/10 including ICI tubes and shear keys. ► Performed thermal analysis using ANSYS V11.0 to determine the internal temperature and heat flux. ► Performed tests to obtain the CHF with saturated demineralized water at atmospheric pressure. ► Measured CHF accounting for 3D random flow effect expected in the APR1400 application. -- Abstract: Corium Ablation Stopper Apparatus (CASA) has a downward-facing hemispherical vessel and geometrically asymmetric thermal insulator of the Advanced Power Reactor 1400 MWe (APR1400) scaled linearly down by 1/10, as well as sixty-one in-core instrumentation (ICI) tubes and four shear keys. The heated vessel plays a pivotal role in CASA depending on the configuration of the oxide pool and metal layer to bring about the focusing effect expected of a molten pool in the lower head during a severe accident. The heated vessel was designed through a trial-and-error method and thermal analysis. Thermal analysis was performed using ANSYS V11.0 to investigate the effect of the internal temperature and heat flux on the integral hemispherical copper vessel. The CASA tests were carried out to obtain the critical heat flux (CHF) with saturated and demineralized water at the atmospheric pressure (0.1 MPa). The CHF in the metal layer through the hemispherical channel was found to be lower than that in the ULPU-2400 configuration V data through the streamlined thermal insulator. The experimental CHF was measured and obtained through the CASA hemispherical heated surface accounting for the three-dimensional random flow effect expected in the APR1400 application

  12. The Gravity Makeup on the LORHR Event during Mid-loop Operation for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Cheol Woo; Lee, Yong Hee; Lee, Gyu Cheon; Kim, Shin Whan [KEPCO, Daejeon (Korea, Republic of)

    2015-05-15

    This paper is to investigate means of the available gravity makeup after the event to prevent or sustain the core uncovery and fuel failure for the typical advanced power reactor nuclear power plants (APR1400). Unlike the OPR1000 (optimized power reactor 1000 nuclear power plants), the refueling water storage tank of APR1400 cannot be used for gravity makeup since it is located on the bottom of the containment with a lower elevation than the reactor vessel. So, the other means of gravity makeup and their effect on the core uncovery are accounted. The use of the water used for the cask loading pit (CLP) during refueling or the safety injection line filling tank (SIFT), which are not designed for gravity makeup during the event, and safety injection tanks (SITs) are considered as the alternative source of makeup feed. The results show that gravity makeup of a SIT provides a sufficient operator action time for the LORHR with the station black out (SBO) during the mid-loop operation for the APR1400. From the LORHR event analysis, the effective means of gravity makeup for APR1400 to cope with this event concurrent loss of all AC power is determined as the gravity feed using SITs. Other means for gravity makeup using CLP or SIFT, which are not designed to mitigate the LORHR event, are evaluated as not effective to the event due to the large flow resistances and the low elevation head to overcome the system pressure increase during the LORHR. The use of one SIT and two SITs for the LORHR provides the core uncovery times as 3 hr 8 min and 4 hr 32 min extending 1 hr 15 min and 2 hr 38 min from the base case, respectively.

  13. An Experimental Investigation on APR1400 Penetration Weld Failure by Metallic Melt

    International Nuclear Information System (INIS)

    An, Sang Mo; Ha, Kwang Soon; Kim, Hwan Yeol

    2014-01-01

    The penetrations are considered as the most vulnerable parts with respect to the reactor vessel failure when a core melt severe accident occurs and the corium reaches the lower head. Penetration tube failure modes can be divided into two categories; tube ejection out of the vessel lower head and rupture of the penetration tube outside the vessel. Tube ejection begins with degrading the penetration tube weld strength to zero as the weld is exposed to temperatures as high as the weld melting temperature, which is called weld failure, and then overcoming any binding force in the hole in the vessel wall that results from differential thermal expansion of the tube and vessel wall. Tube rupture assumes that the debris bed has melted the instrument tube inside the reactor and melt migrates down into the tube to a location outside the vessel wall where a pressure rupture can occur, thus breaching the pressure boundary. In the present paper, we have a focus on the tube ejection failure mode, specifically on the APR1400 weld failure by direct contact with a metallic melt. The objective is to investigate experimentally the ablation kinetics of an APR1400 penetration weld during the interactions with a metallic melt and to suggest the modification of the existing weld failure model. This paper involves the interaction experiments of two different metallic melts (metallic corium and stainless steel melts) with a weld specimen, and rough estimation of weld failure time. The interaction experiments between the metallic melts and an APR1400 penetration weld were performed to investigate the ablation kinetics of the penetration weld. Metallic corium and stainless steel melts were generated using an induction heating technique and interacted with a penetration weld specimen. The ablation rate of the weld specimen showed a range from 0.109 to 0..244 mm/s and thus the APR1400 penetration weld was estimated to be failed at hundreds of times after the interaction with the melt

  14. Seismic analysis of the APR1400 nuclear reactor system using a verified beam element model

    International Nuclear Information System (INIS)

    Park, Jong-beom; Park, No-Cheol; Lee, Sang-Jeong; Park, Young-Pil; Choi, Youngin

    2017-01-01

    Highlights: • A simplified beam element model is constructed based on the real dynamic characteristics of the APR1400. • Time history analysis is performed to calculate the seismic responses of the structures. • Large deformations can be observed at the in-phase mode of reactor vessel and core support barrel. - Abstract: Structural integrity is the first priority in the design of nuclear reactor internal structures. In particular, nuclear reactor internals should be designed to endure external forces, such as those due to earthquakes. Many researchers have performed finite element analyses to meet these design requirements. Generally, a seismic analysis model should reflect the dynamic characteristics of the target system. However, seismic analysis based on the finite element method requires long computation times as well as huge storage space. In this research, a beam element model was developed and confirmed based on the real dynamic characteristics of an advanced pressurized water nuclear reactor 1400 (APR1400) system. That verification process enhances the accuracy of the finite element analysis using the beam elements, remarkably. Also, the beam element model reduces seismic analysis costs. Therefore, the beam element model was used to perform the seismic analysis. Then, the safety of the APR1400 was assessed based on a seismic analysis of the time history responses of its structures. Thus, efficient, accurate seismic analysis was demonstrated using the proposed beam element model.

  15. Seismic analysis of the APR1400 nuclear reactor system using a verified beam element model

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong-beom [Department of Mechanical Engineering, Yonsei University, 50 Yonsei-ro, Seodaemun-gu, Seoul 03722 (Korea, Republic of); Park, No-Cheol, E-mail: pnch@yonsei.ac.kr [Department of Mechanical Engineering, Yonsei University, 50 Yonsei-ro, Seodaemun-gu, Seoul 03722 (Korea, Republic of); Lee, Sang-Jeong; Park, Young-Pil [Department of Mechanical Engineering, Yonsei University, 50 Yonsei-ro, Seodaemun-gu, Seoul 03722 (Korea, Republic of); Choi, Youngin [Korea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon 34142 (Korea, Republic of)

    2017-03-15

    Highlights: • A simplified beam element model is constructed based on the real dynamic characteristics of the APR1400. • Time history analysis is performed to calculate the seismic responses of the structures. • Large deformations can be observed at the in-phase mode of reactor vessel and core support barrel. - Abstract: Structural integrity is the first priority in the design of nuclear reactor internal structures. In particular, nuclear reactor internals should be designed to endure external forces, such as those due to earthquakes. Many researchers have performed finite element analyses to meet these design requirements. Generally, a seismic analysis model should reflect the dynamic characteristics of the target system. However, seismic analysis based on the finite element method requires long computation times as well as huge storage space. In this research, a beam element model was developed and confirmed based on the real dynamic characteristics of an advanced pressurized water nuclear reactor 1400 (APR1400) system. That verification process enhances the accuracy of the finite element analysis using the beam elements, remarkably. Also, the beam element model reduces seismic analysis costs. Therefore, the beam element model was used to perform the seismic analysis. Then, the safety of the APR1400 was assessed based on a seismic analysis of the time history responses of its structures. Thus, efficient, accurate seismic analysis was demonstrated using the proposed beam element model.

  16. Containment Performance Analysis with Large Break LOCA for EU-APR1400

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Keun Sung; Kim, Yong Soo

    2013-01-01

    In this paper for containment performance analysis, the containment pressurization analysis is performed and thermo-hydraulic response analysis of containment structure is carried out to provide basic understanding of containment transient states under a severe accident sequence. Especially, in EU-APR1400 design, to reduce containment pressure and temperature, Severe Accident Containment Spray System (SACSS) is designed to be actuated automatically when Core Exit Temperature (CET) reaches 922 K (649 .deg. C). The containment performance analysis was carried on LBLOCA sequence for EU-APR1400 with SACSS through MAAP code. If SACSS is actuated when CET reaches 922 K (649 .deg. C) , the containment pressure and temperature decrease to a sufficient low level. The predicted atmospheric pressure of containment will not exceed the ultimate pressure capacity (UPC) and have a sufficient margin to it even though the UPC of the reference plant (Shin-Kori Units 3 and 4) is used instead because the UPC calculation for EU-APR1400 has not been completed. The largest load on the containment by LBLOCA is estimated at 306.1 kPa. Thus the margin to UPC is estimated to be 330 % in comparison with 1.329 MPa as UPC for the reference plant.

  17. Main steam line break accident simulation of APR1400 using the model of ATLAS facility

    Science.gov (United States)

    Ekariansyah, A. S.; Deswandri; Sunaryo, Geni R.

    2018-02-01

    A main steam line break simulation for APR1400 as an advanced design of PWR has been performed using the RELAP5 code. The simulation was conducted in a model of thermal-hydraulic test facility called as ATLAS, which represents a scaled down facility of the APR1400 design. The main steam line break event is described in a open-access safety report document, in which initial conditions and assumptionsfor the analysis were utilized in performing the simulation and analysis of the selected parameter. The objective of this work was to conduct a benchmark activities by comparing the simulation results of the CESEC-III code as a conservative approach code with the results of RELAP5 as a best-estimate code. Based on the simulation results, a general similarity in the behavior of selected parameters was observed between the two codes. However the degree of accuracy still needs further research an analysis by comparing with the other best-estimate code. Uncertainties arising from the ATLAS model should be minimized by taking into account much more specific data in developing the APR1400 model.

  18. Analytical Assessment of Environmental Impact for APR1400DC UHS Cooling Tower

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jaiho [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Hot process water is pumped from the plant process to the cooling towers. Heat is rejected through evaporation of the process water, interacting with ambient air blown upward by fans.. Plumes generated from exit ports of the cooling tower may have adverse effects on the environment, such as deposition of cooling tower drift release, fogging, icing, shadowing, and ground-level temperature and humidity increase. These kinds of environmental impact of the cooling tower are linked closely with the dispersion of the cooling tower plumes. In this respect, predicting the behavior of the plumes has become one of the most important issues in the environmental assessments of the cooling towers. The SACTI (seasonal/annual cooling tower impact) model is an analytical tool to predict the environmental effect of cooling tower, which was developed by Argonne National Laboratory and University of Illinois with support from EPRI (electric power research institute). The initial version of SACTI has been widely used to assess the environmental effect of cooling towers in many industrial fields such as steam power plants and NPPs. Guo et. al. investigated impact of heat rejection and cooling tower height on plume dispersion using the SACTI model, for the purpose of the future construction of inland NPPs. They found that increasing cooling tower height decreases the plume length and height frequencies. Their simulation results showed that the increase in heat rejection increases the plum radius frequency. The APR1400DC is an advanced light water reactor developed for the purpose of NRC-DC (design certification). The cooling towers for APR1400DC UHS consist of two linear mechanical draft cooling towers (LMDCTs). The LMDCT for APR1400DC UHS is conceptually designed because the plant site has not been decided yet. In the present study, the dependency of plume dispersion on the number of cooling towers is investigated using SACTI-2-beta, for predicting annual environmental effect of APR

  19. A Source Term Calculation for the APR1400 NSSS Auxiliary System Components Using the Modified SHIELD Code

    International Nuclear Information System (INIS)

    Park, Hong Sik; Kim, Min; Park, Seong Chan; Seo, Jong Tae; Kim, Eun Kee

    2005-01-01

    The SHIELD code has been used to calculate the source terms of NSSS Auxiliary System (comprising CVCS, SIS, and SCS) components of the OPR1000. Because the code had been developed based upon the SYSTEM80 design and the APR1400 NSSS Auxiliary System design is considerably changed from that of SYSTEM80 or OPR1000, the SHIELD code cannot be used directly for APR1400 radiation design. Thus the hand-calculation is needed for the portion of design changes using the results of the SHIELD code calculation. In this study, the SHIELD code is modified to incorporate the APR1400 design changes and the source term calculation is performed for the APR1400 NSSS Auxiliary System components

  20. How to Maintain Computerized Procedure System in the same Version

    International Nuclear Information System (INIS)

    Jung, Yeon Sub

    2016-01-01

    CPS(Computerized Procedure System) has been introduced in advanced nuclear power plant worldwide. Korean CPS complies with this trend. It has been applied to Shinkori3,4 and all their successors including BNPP1,2,3,4. CPS is designed by KHNP CRI, and developed by Westinghouse or Doosan. Initial design has been improved by reflecting operator experience, human factor V and V, and advanced engineering method. Design improvement makes CPS differ from plant to plant. For example CPS in Shinhanul cannot interpret CP(Computerized Procedure) of ShinKori3, 4. Different CPS makes it difficult to utilize CP and train operators. Therefore it is important to keep CPS in single version. Note that typical text editors in the office are kept in single version. On the other hand, plant monitoring systems in main control room are actually different. Because CPS is positioned between text editor and monitoring system, goal to maintain CPS in single version is not an easy task. From Shinkori3,4, lots of improvements are achieved in CPS. This improvement surely makes operation easy and will not introduce human errors. Side effect of improvement is that PXS and CPS ES may not be compatible among nuclear power plants. So the side effect should be avoided by minimizing change of XML. Initial XML had been developed for Shinkori3,4. The XML has been modified slightly for Shinhanul1,2. PXS and CPS ES are being developed for the same version for all nuclear power plants of APR1400

  1. APR1400 Electrical Power System Conformance to SECY-91-078

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Che-Wung; Kim, Yun-Ho [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, the APR1400 electric power system for NRC-DC was described. In addition, the conformance to SECY 91-078 was evaluated. Enclosure 1 of the SECY provides an overview of the issue and states that the staff concludes that feeding the safety buses from the offsite power sources through non-safety buses or from a common transformer winding with non-safety loads is not the most reliable configuration. Such an arrangement increases the difficulty in properly regulating voltage at the safety buses, subjects the safety loads to transients caused by the non-safety loads, and adds additional failure points between the offsite power sources and safety loads. Therefore, it is the staff’s position that at least one offsite circuit to each redundant safety division should be supplied directly from one of the offsite power sources with no intervening non-safety buses, in such a manner that the offsite source can power the safety buses upon a failure of any non-safety bus. The APR1400 does not have an intervening nonsafety bus in the current offsite to onsite electrical configuration; however, the design does include nonsafety and safety buses coming from the same secondary side 4.16 kV transformer winding. Nevertheless, the APR1400 has designed the electrical interface system between offsite and onsite power with enhanced reliability measures to ensure that the nonsafety system will not impact the safety loads. The design complies with GDC 17 and also conforms to SECY-91-078.

  2. Structural assessments of plate type support system for APR1400 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, Anh Tung; Namgung, Ihn, E-mail: inamgung@kings.ac.kr

    2017-04-01

    Highlights: • This paper investigates plate-type support structure for the reactor vessel of the APR 1400. • The tall column supports of APR1400 reactor challenges in seismic and severe accident events. • A plate-type support of reactor vessel was proposed and evaluated based on ASME code. • The plate-type support was assessed to show its higher rigidity than column-type. - Abstract: This paper investigates an alternative form of support structure for the reactor vessel of the APR 1400. The current reactor vessel adopts a four-column support arrangement locating on the cold legs of the vessel. Although having been successfully designed, the tall column structure challenges in seismic events. In addition, for the mitigation of severe accident consequences, the columns inhibit ex-vessel coolant flow, hence the elimination of the support columns proposes extra safety advantages. A plate-type support was proposed and evaluated for the adequacy of meeting the structural stiffness by Finite Element Analysis (FEA) approach. ASME Boiler and Pressure Vessel Code was used to verify the design. The results, which cover thermal and static structural analysis, show stresses are within allowable limits in accordance with the design code. Even the heat conduction area is increased for the plate-type of support system, the results showed that the thermal stresses are within allowable limits. A comparison of natural frequencies and mode shapes for column support and plate-type support were presented as well which showed higher fundamental frequencies for the plate-type support system resulting in greater rigidity of the support system. From the outcome of this research, the plate-type support is proven to be an alternative to current APR column type support design.

  3. Development of phenomena identification and ranking table for APR1400 main steam line break

    International Nuclear Information System (INIS)

    Song, J. H.; Chung, B. D.; Jeong, J. J.

    2003-01-01

    A Phenomena Identification and Ranking Table (PIRT) was developed for the Main Steam Line Break (MSLB) event of an APR-1400 (Advanced Power Reactor-1400). A team of experts from research institutes, industries, and regulatory bodies participated in the development. The selected event was a double-ended steam line break at full power with the reactor coolant pump running. The panel selected the fuel performance as the primary safety criterion for ranking. The plant design data, the results of APR-1400 safety analysis, and the results of additional best estimate analysis by MARS2.1 were utilized. Three phases of pre-trip, rapid cool-down, and safety injection phase were identified. Then, the ranking of a system, components, phenomenon/process based on the relative importance to the primary evaluation criterion were followed for each time phase. Finally, the knowledge-level for each important process in the component was ranked in terms of the existing knowledge. The highly ranked phenomena identified for APR-1400 MSLB are tube wall heat transfer at the steam generator shell, void distribution at the steam generator shell, liquid entrainment in the separators, mixture level in the separators, boron mixing in the upper down comer, boron transport and thermal mixing in the lower plenum, stored energy release in the upper head, and flow to and/from the upper head. The PIRT will be used as a guide in planning cost effective experimental programs and code development efforts, especially for the quantification of the process and/or phenomena, which have a high importance but low knowledge level

  4. Single-tube condensation experiment in Passive Auxiliary Feedwater System of APR1400+

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Chang Wook; No, Hee Cheon; Yun, Bong Yo; Jeon, Byong Guk [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2012-05-15

    Conventional Korean nuclear power plants, Advanced Power Reactors (APR), are characterized by an active cooling system. However, Active cooling system may not prevent significant damage without any AC power source available for its operation as vividly illustrated through the recent Fukushima incident. In the APR1400+ to be designed, an independent passive cooling system was added in order to overcome the aforementioned shortcomings. In the Passive Auxiliary Feedwater System (PAFS), gravity force and density difference between steam and water are used. The system comprises of 240 condensation tubes to efficiently remove decay heat. Before applying the PAFS to APR1400+, the system's safety and heat removal performance must be verified. The present study experimentally evaluates the heat removal performance of a single tube in the PAFS. The objectives of SCOP (Single-tube Condensation experiment facility of PAFS) are the evaluation of the heat removal performance in the tube of the PAFS and database construction under various tube designs and test conditions. Reaching these objectives, we developed advanced measurement techniques for the amount of moisture, heat flux, and water film thickness.

  5. PLUS 7TM advanced fuel assembly development program for KSNPs and APR1400

    International Nuclear Information System (INIS)

    Kim, Kyutae; Stucker, David L.

    2002-01-01

    KNFC and Westinghouse have recently completed the development of the PLUS 7 TM advanced 16 X 16 fuel assembly for the Korean Standard Nuclear Plants (KSNPs) and the Advanced Power Reactor 1400 (APR 1400). This fuel design utilized the proven advanced design features including mixing vane spacer grids to increase critical heat flux performance, ZIRLO TM advanced materials to enable high-duty, high burnup fuel management and an optimized fuel rod diameter which improves fuel cycle cost while resulting in significant standardization of Korean fuel manufacture. PLUS 7 TM , also includes a patented spacer grid design with conformal fuel rod support designed to provide superior fuel rod wear/fretting resistance while minimizing pressure drop. This paper will present an overview of the PLUS 7 TM fuel assembly development process including a summary of the three-year design and testing program from a mechanical, neutronic, and thermal/hydraulic perspective. The PLUS 7 TM fuel for the KSNPs and the APR1400 reactors results in multi-million dollar per cycle savings in imported enriched uranium product for the Korean nuclear power program with technology specifically developed for Korea by experienced Korean engineers

  6. Post-test analysis for the APR1400 LBLOCA DVI performance test using MARS

    International Nuclear Information System (INIS)

    Bae, Kyoo Hwan; Lee, Y. J.; Kim, H. C.; Bae, Y. Y.; Park, J. K.; Lee, W.

    2002-03-01

    Post-test analyses using a multi-dimensional best-estimate analysis code, MARS, are performed for the APR1400 LBLOCA DVI (Direct Vessel Injection) performance tests. This report describes the code evaluation results for the test data of various void height tests and direct bypass tests that have been performed at MIDAS test facility. MIDAS is a scaled test facility of APR1400 with the objective of identifying multi-dimensional thermal-hydraulic phenomena in the downcomer during the reflood conditions of a large break LOCA. A modified linear scale ratio was applied in its construction and test conditions. The major thermal-hydraulic parameters such as ECC bypass fraction, steam condensation fraction, and temperature distributions in downcomer are compared and evaluated. The evaluation results of MARS code for the various test cases show that: (a) MARS code has an advanced modeling capability of well predicting major multi-dimensional thermal-hydraulic phenomena occurring in the downcomer, (b) MARS code under-predicts the steam condensation rates, which in turn causes to over-predict the ECC bypass rates. However, the trend of decrease in steam condensation rate and increase in ECC bypass rate in accordance with the increase in steam flow rate, and the calculation results of the ECC bypass rates under the EM analysis conditions generally agree with the test data

  7. Analysis of Total Loss of Feedwater for APR1400 using SPACE

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Seong Min; Park, Seok Jeong; Park, Chan Eok; Choi, Jong Ho; Lee, Gyu Cheon [KEPCO Engineering and Construction, Deajeon (Korea, Republic of)

    2016-10-15

    The Total Loss of FeedWater (TLOFW) event is an accident that main feedwater and auxiliary feedwater of secondary side are not supplied to steam generators. APR1400 uses the Safety Depressurization and Vent System (SDVS) for the F and B operation and SDVS is designed to perform the rapid depressurization function of Reactor Coolant System (RCS) through the remote manual operation when TLOFW is occurred. If RCS pressure falls below a Safety Injection Pump (SIP) working pressure, it can be possible to start the F and B operation which injects SIP flow to RCS and releases the RCS vapor and two-phase flow through Pilot Operated Safety Relief Valves (POSRVs) by opening the POSRVs, and then it can be possible to remove the decay heat. The design requirement of SDVS is that the core water level should be maintained at higher than 2 feet from the top of active core during the F and B operation. The TLOFW analysis was carried out to evaluate the capability of decay heat removal for APR1400 using newly developed SPACE code. The analysis results show that the F and B operation with 2 POSRVs and 2 SIPs and the F and B operation with 4 POSRVs and 4 SIPs meet the SDVS design requirement for the fuel cladding temperature. The comparison with RELAP5 shows good agreement and it validates the applicability of SPACE code for this type of accident analysis.

  8. Probability of Neutralization Estimation for APR1400 Physical Protection System Design Effectiveness Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myungsu; Lim, Heoksoon; Na, Janghwan; Chi, Moongoo [Korea Hydro and Nuclear Power Co. Ltd. Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    It is focusing on development of a new designing process which can be compatible to international standards such as IAEA1 and NRC2 suggest. Evaluation for the design effectiveness was found as one of the areas to improve. If a design doesn't meet a certain level of effectiveness, it should be re-designed accordingly. The effectiveness can be calculated with combination of probability of Interruption and probability of neutralization. System Analysis of Vulnerability to Intrusion (SAVI) has been developed by Sandia National Laboratories for that purpose. With SNL's timely detection methodology, SAVI has been used by U.S. nuclear utilities to meet the NRC requirements for PPS design effectiveness evaluation. For the SAVI calculation, probability of neutralization is a vital input element that must be supplied. This paper describes the elements to consider for neutralization, probability estimation methodology, and the estimation for APR1400 PPS design effectiveness evaluation process. Markov chain and Monte Carlo simulation are often used for simple numerical calculation to estimate P{sub N}. The results from both methods are not always identical even for the same situation. P{sub N} values for APR1400 evaluation were calculated based on Markov chain method and modified to be applicable for guards/adversaries ratio based analysis.

  9. The Analysis of Uncontrolled CEA Bank withdrawal from low power Accident for APR1400 Using KNAP

    International Nuclear Information System (INIS)

    Yang, Chang-Keun; Kim, Yo-Han; Ha, Sang-Jun

    2006-01-01

    In Korea, the nuclear industries such as fuel manufacturer, the architect engineer and the utility, have been using the methodologies and codes of vendors, such as Westinghouse(WH), Combustion Engineering(CE), for the safety analyses of nuclear power plants. Consequently the industries have kept up the many organizations to operate the methodologies and to maintain the codes for each vendor. It may cause difficulty to improve the safety analyses efficiency and technology related. So, the necessity another of methodologies and code systems applicable to Non- LOCA, beyond design basis accident and performance analyses for all types of pressurized water reactor (PWR) has been raised. As the first requirement, the best-estimate codes were required for applicable wider application area and realistic behavior prediction of power plants with various and sophisticated functions. After the review on several candidates, RETRAN-3D has been chosen as a system analysis code. The draft version of the methodology was developed based on the references for the general purpose, and modified to apply it to specific plants in Korea. As a part of the feasibility estimation for the methodology and code system, uncontrolled CEA bank withdrawal from low power accident for the Advanced Power Reactor 1400(APR1400) was selected to verify the feasibility using the RETRAN-3D. And the results were compared with the Standard Safety Analysis Reports (SSAR) of APR1400

  10. Domestic activity for technical development of the APR1400's RCP performance test

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seok; Kim, Seok; Bae, Byung-Uhn; Cho, Yun-Jae; Kim, Yeon-Sik; Jeon, Woo-Jin; Yun, Young-Jung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The thermal hydraulic and electric capability of the RCP test facility (RCPTF) covers up to 18.5 MPa, 343 .deg. C, 11.7 m{sup 3}/s, and 14.0 MW in the design pressure, temperature, flow rate, and the maximum electric power, respectively. In 2013, commissioning test had been performed to verify its designed capability, followed by several modifications in the RCPTF including signal processing and control logic to enhance verification and evaluation capability of the RCP performance. After finishing the commissioning and modification of the RCPTF, type test for the new-type RCP had been performed successfully. In this paper, several technical issues developed in the 2013 and the type test's method and results will be described. In the present paper, the technical activities for the development of the verification test of APR1400's RCP are described. KAERI has completed the full set of technology development, prerequisite for the RCP verification test, and now on the way to perform a test for the sealing capacity of the seal assembly during the Station Block Out (SBO) condition of APR1400.

  11. Reliability analysis of protection system of advanced pressurized water reactor - APR 1400

    International Nuclear Information System (INIS)

    Varde, P. V.; Choi, J. G.; Lee, D. Y.; Han, J. B.

    2003-04-01

    Reliability analysis was carried out for the protection system of the Korean Advanced Pressurized Water Reactor - APR 1400. The main focus of this study was the reliability analysis of digital protection system, however, towards giving an integrated statement of complete protection reliability an attempt has been made to include the shutdown devices and other related aspects based on the information available to date. The sensitivity analysis has been carried out for the critical components / functions in the system. Other aspects like importance analysis and human error reliability for the critical human actions form part of this work. The framework provided by this study and the results obtained shows that this analysis has potential to be utilized as part of risk informed approach for future design / regulatory applications

  12. A MARS and MIDAS Linked Accident Simulation for Large LOCA in APR1400

    International Nuclear Information System (INIS)

    Choi, Young; Kim, K. R.; Kim, D. H.; Chung, B. D.

    2006-01-01

    A linked calculation utilizing the design-basis code MARS and the severe accident code MIDAS has been accomplished for a station blackout simulation in APR1400. The MARS code was developed by using the RELAP3/MOD3 and COBRA-TF codes, while the MIDAS code is currently under a development process using the MELCOR code. The objectives of this paper are to explain how to identify the MAR-MIDAS linked calculation outlines and the technical problems, including the MARS data transfer method, the MIDAS input generation works and so on. For the performance verification of the MARS-MIDAS linked calculation, the MARS, MIDAS and their linkage system are run independently for the same initiating event, so that their data can be compared with each other after the selection of proper variables

  13. Minimum containment pressure and its effect on ECCS performance of APR-1400

    International Nuclear Information System (INIS)

    Kim, In Goo; Bang, Young S.; Kim, Hho Jung

    2004-01-01

    The containment pressure has a strong effect on the late reheat behavior for a large break LOCA, associated with the DVI issue. The downcomer boiling, which occurs during the post-reflood phase, has a negative effect on core cooling for a LBLOCA. Because the downcomer boiling is enhanced as the containment pressure decreases, how to determine containment pressure is important to the evaluation of ECCS performance. In spite of its importance of containment pressure, there are few studies on the containment pressure and the interaction between RCS and containment thermal hydraulics. To have a better knowledge of the effect of containment pressure on APR-1400 ECCS performance, a parametric study for containment pressure has been carried out. Also, the interaction between RCS and containment behavior has been also investigated

  14. Analysis Of Feedwater Line Break Of APR1400 By MARS Code

    International Nuclear Information System (INIS)

    Nguyen Thi Thanh Thuy; Le Dai Dien, Hoang Minh Giang

    2011-01-01

    This paper will deal with analysis of Feed water Line Break problem (FWLB) of the APR 1400 NPP with initial conditions: operation at 100% of power, double-ended break area of 0.058 m 2 and the break location of the feedwater line between the check valve and the steam generator. The analysis was simulated by MARS code through two step: calculation for steady state and calculation for transient state with initial condition mentioned. Some output result were presented with explanation: sequence of events corresponding to the time of the accident, the system behavior as temperature, pressure, steam generator water levels as well as DNBR, etc. before and after the accident. (author)

  15. Analysis Of Control Rod Ejection Of APR1400 By RELAP5

    International Nuclear Information System (INIS)

    Le Thi Thu; Hoang Minh Giang; Vo Thi Huong; Le Dai Dien

    2011-01-01

    This paper presents the analysis of Reactivity Induced Accident caused by ejection of a Control Element Assembly (CEA) from APR 1400 reactor vessel within 0.05 second. The initial condition were assumed as following: power level at 102%, delayed neutron fraction β = 412 pcm and CEA worth = 110 pcm. The analysis was simulated by RELAP5 code through two step: calculation of steady state and calculation of transient with initial condition mentioned as above. Some output results were presented with explanation: sequence of events corresponding to the time of the accident, the system behavior as power, reactivity feedback from fuel temperature changes (Doppler) as well as temperature, pressure, DNBR within 6 second of the accident. (author)

  16. Preliminary Analysis of Ex-Vessel Steam Explosion using TEXAS-V code for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Song, Sung Chu; Lee, Jung Jae; Cho, Yong Jin; Hwang, Taesuk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    The purpose of this study is to explore input development and the audit calculation using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS computational models are one of the simplified tools for simulations of fuel-coolant interaction during mixing, triggering and explosion phase. The models of TEXAS code were validated by performing the fundamental experimental investigation in the KROTOS facility at JRC, Ispra. The experiments such as KROTOS and FARO experiment are aimed at providing benchmark data to examine the effect of fuel-coolant initial conditions and mixing on explosion energetics with alumina and prototypical core material. TEXAS-V code used in this study was to analyze and predict the ex-vessel steam explosion for a reactor scale. The input deck to simulate the flooded reactor cavity of APR1400 is developed and base case calculation is performed. This study will provide a base for further study. The code will be of use for the evaluation and sensitivity study of ex-vessel steam explosion for ERVC strategy in the future studies. Analysis result of this study is similar to the result of other study. Through this study, it is found that TEXAS-V could be the used as a tool for predicting the steam explosion load on a reactor scale, as fast running computer code. In addition, TEXAS-V code could be to evaluate the impact of various uncertainties, which are not clearly understood yet, to provide a conservative envelope for the steam explosion.

  17. Preliminary Analysis of Ex-Vessel Steam Explosion using TEXAS-V code for APR1400

    International Nuclear Information System (INIS)

    Song, Sung Chu; Lee, Jung Jae; Cho, Yong Jin; Hwang, Taesuk

    2013-01-01

    The purpose of this study is to explore input development and the audit calculation using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS computational models are one of the simplified tools for simulations of fuel-coolant interaction during mixing, triggering and explosion phase. The models of TEXAS code were validated by performing the fundamental experimental investigation in the KROTOS facility at JRC, Ispra. The experiments such as KROTOS and FARO experiment are aimed at providing benchmark data to examine the effect of fuel-coolant initial conditions and mixing on explosion energetics with alumina and prototypical core material. TEXAS-V code used in this study was to analyze and predict the ex-vessel steam explosion for a reactor scale. The input deck to simulate the flooded reactor cavity of APR1400 is developed and base case calculation is performed. This study will provide a base for further study. The code will be of use for the evaluation and sensitivity study of ex-vessel steam explosion for ERVC strategy in the future studies. Analysis result of this study is similar to the result of other study. Through this study, it is found that TEXAS-V could be the used as a tool for predicting the steam explosion load on a reactor scale, as fast running computer code. In addition, TEXAS-V code could be to evaluate the impact of various uncertainties, which are not clearly understood yet, to provide a conservative envelope for the steam explosion

  18. Use case driven approach to develop simulation model for PCS of APR1400 simulator

    International Nuclear Information System (INIS)

    Dong Wook, Kim; Hong Soo, Kim; Hyeon Tae, Kang; Byung Hwan, Bae

    2006-01-01

    The full-scope simulator is being developed to evaluate specific design feature and to support the iterative design and validation in the Man-Machine Interface System (MMIS) design of Advanced Power Reactor (APR) 1400. The simulator consists of process model, control logic model, and MMI for the APR1400 as well as the Power Control System (PCS). In this paper, a use case driven approach is proposed to develop a simulation model for PCS. In this approach, a system is considered from the point of view of its users. User's view of the system is based on interactions with the system and the resultant responses. In use case driven approach, we initially consider the system as a black box and look at its interactions with the users. From these interactions, use cases of the system are identified. Then the system is modeled using these use cases as functions. Lower levels expand the functionalities of each of these use cases. Hence, starting from the topmost level view of the system, we proceeded down to the lowest level (the internal view of the system). The model of the system thus developed is use case driven. This paper will introduce the functionality of the PCS simulation model, including a requirement analysis based on use case and the validation result of development of PCS model. The PCS simulation model using use case will be first used during the full-scope simulator development for nuclear power plant and will be supplied to Shin-Kori 3 and 4 plant. The use case based simulation model development can be useful for the design and implementation of simulation models. (authors)

  19. Analysis for the Effects of Grid Voltage Degradation on APR1400 Operation, Case Study for Egypt

    International Nuclear Information System (INIS)

    Hassan, Mostafa Ahmed Fouad; Koo, Chang Choong

    2015-01-01

    Egypt is one of the countries planning to introduce a NPP into its electrical power system. Although the Egyptian power system has sufficient capacity to integrate any commercially available nuclear unit as the total installed capacity of the power system is more than 32GWe, which is more than 10 times capacity of any nuclear unit in the range of 1000 to 1700MWe, the system is vulnerable to extreme voltage variations, especially voltage degradation during peak load conditions. These conditions can lead to voltage collapse if a counter measure, usually load shedding, is not taken in a proper time. Hence, it is necessary to analyze the effect of such conditions on the safe and economic operation of the NPP. In this paper we analyzed the effects of grid voltage degradation on the safe and economic operation of the Advanced Power Reactor (APR1400) to determine any adverse effects on the plant auxiliary loads while operating in the Egyptian power system. In this paper the effects of grid voltage degradation on the safe and economic operation of APR1400 were investigated taking into account, generator operating limits, plant safety requirements, operation modes and loading categories in order to determine any adverse effect on the plant auxiliary loads while operating in the Egyptian power system. The results of the load flow and motor starting analysis demonstrated that during normal operation the automatic voltage regulator and transformers OLTCs can mitigate the effect of grid voltage degradation without any detrimental effect on the plant auxiliary loads. During the highly unlikely LOCA condition if the grid voltage degraded below 95%, the degraded voltage relays at Class 1E 4.16 kV buses will trip the supply and load breakers and reconnect the required safety loads to the EDG after 4 minutes time delay. During this period the safety loads required for LOCA can be started and accelerated to their rated speed safely even in the worst case of expected degraded voltage

  20. A Development Method of Mobile Computerized Procedure System for the Cooperation among Field Workers and Main Control Room Operators in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Sun Jin; Seong, No Kyu; Jung, Yeon Sub

    2014-01-01

    Human errors can occur during the test and maintenance of steam generator, safety injection system and other various systems and devices in nuclear power plants (NPPs). Most of human errors can be improved by the human error prevention techniques such as self-check, peer-check, concurrent verification and etc. Another important technique is to share work information among main control room (MCR) operators and field workers. Various field service automation tools have been developed with recent information technology in many countries. APR1400 computerized procedure system (CPS) has been developed for the MCR operators of Shin-Kori 3 and 4 units. Especially, the concurrent verification support design is applied in the construction project of Shin-Hanul 1 and 2 CPS. It is expected that the proposed mobile CPS can enhance the reduction of human errors by supporting human error prevention techniques and information sharing. This paper describes the technical issues of the mobile CPS (mobile CPS) in the initial development stage. Based on the design of APR1400, CRI CPS has been developed and operated for SKN 3 and 4 HFE V and V and license test for the MCR operating staff. Therefore the mobile CPS will be developed by upgrading the CRI CPS with improved features

  1. A Development Method of Mobile Computerized Procedure System for the Cooperation among Field Workers and Main Control Room Operators in Korean Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sun Jin; Seong, No Kyu; Jung, Yeon Sub [KHNP ,Daejeon (Korea, Republic of)

    2014-08-15

    Human errors can occur during the test and maintenance of steam generator, safety injection system and other various systems and devices in nuclear power plants (NPPs). Most of human errors can be improved by the human error prevention techniques such as self-check, peer-check, concurrent verification and etc. Another important technique is to share work information among main control room (MCR) operators and field workers. Various field service automation tools have been developed with recent information technology in many countries. APR1400 computerized procedure system (CPS) has been developed for the MCR operators of Shin-Kori 3 and 4 units. Especially, the concurrent verification support design is applied in the construction project of Shin-Hanul 1 and 2 CPS. It is expected that the proposed mobile CPS can enhance the reduction of human errors by supporting human error prevention techniques and information sharing. This paper describes the technical issues of the mobile CPS (mobile CPS) in the initial development stage. Based on the design of APR1400, CRI CPS has been developed and operated for SKN 3 and 4 HFE V and V and license test for the MCR operating staff. Therefore the mobile CPS will be developed by upgrading the CRI CPS with improved features.

  2. Analysis of steam condensation in APR1400 IRWST for loss of coolant accident

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Young Suk

    2006-02-15

    The In-Containment Refueling Water Storage Tank (IRWST) of APR1400 is installed at the bottom of containment building to promote the plant safety functions during an accident. This design feature brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised when an accident occurs. The hot steam which is released from RCS break enters the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, in which water is colder than incoming steam. The purpose of this study is to investigate the influence of IRWST and pressure relief damper on back pressure and temperature in APR1400 containment codes such as CONTEMPT-LT and GOTHIC. The comparison of codes showed that GOTHIC code be more appropriate for the prediction of containment pressure and temperature under the condition of steam condensation occurring in confined water pool. Especially, the GOTHIC has superior capability to treat multi-compartmentalized geometry This study developed one-compartment (single) model, two-compartment (separated) model, and three-dimension (3-D) model, respectively. Two compartment model separates the IRWST from the other containment compartments. In 3-D model, only the IRWST is nodalized with Cartesian modeling. The single model is developed for comparison with two-compartment model which can analyze PRD's influence. The separated model for predicting PRD's influence divides the space between containment and IRWST. 3-D model for IRWST was generated because it is not symmetric considering location of sparger, pump, and suction sump. Therefore, IRWST is simulated with not only detailed three-dimensional behavior but also independent flow paths for four PRDs. Many experimental studies for the direct-contact heat transfer in stratified steam water flows, cocurrent or countercurrent, have been performed (Segev et al., 1981; Lim et al., 1981

  3. Analysis of Hydrogen Concentration Distribution during an SBO Accident for Shin-Ulchin APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jongtae; Hong, Seong Wan [Korea Atomic energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    To prohibit the accumulation of hydrogen, the containment volume is considered to reduce the hydrogen concentration, or hydrogen mitigation devices such as PARs or igniters are installed in the containment. In the case of the Fukushima NPPs, the applied strategy for the hydrogen safety is the use of a containment venting system (CVS). In this way, the hydrogen accumulated in the containment vessel is vented into the environment. One of the causes of the hydrogen explosions occurring in the containment buildings of the Fukushima NPPs is expected to be the failure of the venting system. The hydrogen was therefore easily accumulated in the containment building. It is uncertain what the ignition source for the hydrogen combustion was during the accident. However, it is not too conservative to assume that an ignition source exists at any time and any place in a containment during a core-melt accident. Shin-Ulchin 1 and 2, which are construction plants of an APR 1400, are two of the newest NPPs in Korea. They have many features to enhance the safety margin during a design-based and beyond-design-based accident. One of them is the in-containment refueling water storage tank (IRWST) located inside the containment. It is used as a sink/source for feed-bleed operation. When the core is damaged along an accident progression, the hydrogen generated in the RPV can be released into the IRWST of the APR1400 with steam and water. From a previous study, it was found that a highly concentrated hydrogen/air mixture can be developed if the hydrogen is released into the IRWST. In the case of Shin-Ulchin 1 and 2, the hydrogen mitigation strategy during a high-pressure accident such as a station blackout (SBO) is changed by installing a 3-way valve. When a severe accident management (SAM) for the plant is initiated, the flow path from a pressurizer to the IRWST is changed into a steam-generator (S/G) compartment by turning the 3-wat valve actively (pilot operated). By doing so, it is

  4. Comparison of serpent and triton generated FEW group constants for APR1400 nuclear reactor core

    International Nuclear Information System (INIS)

    Elsawi, Mohamed A.; Alnoamani, Zainab

    2015-01-01

    The accuracy of full-core reactor power calculations using diffusion codes is strongly dependent on the quality of the homogenized cross sections and other few-group constants generated by lattice codes. For many years, deterministic lattice codes have been used to generate these constants using different techniques: the discrete ordinates, collision probability or the method of characteristics, just to name a few. These codes, however, show some limitations, for example, on complex geometries or near heavy absorbers as in modern pressurized water reactor (PWR) designs like the Korean Advanced Power Reactor 1400 (APR1400) core. The use of continuous-energy Monte Carlo (MC) codes to produce nuclear constants can be seen as an attractive option when dealing with fuel or reactor types that lie beyond the capabilities of conventional deterministic lattice transport codes. In this paper, the few-group constants generated by two of the state-of-the-art reactor physics codes, SERPENT and SCALE/TRITON, will be critically studied and their reliability for being used in subsequent diffusion calculations will be evaluated. SERPENT is a 3D, continuous-energy, Monte Carlo reactor physics code which has a built-in burn-up calculation capability. It has been developed at the Technical Research Center of Finland (VTT) since 2004. SCALE/TRITON, on the other hand, is a control module developed within the framework of SCALE package that enables performing deterministic 2-D transport calculations on nuclear reactor core lattices. The approach followed in this paper is as follows. First, the few-group nuclear constants for the APR1400 reactor core were generated using SERPENT (version 2.1.22) and NEWT (in SCALE version 6.1.2) codes. For both codes, the critical spectrum, calculated using the B1 method, was used as a weighting function. Second, 2-D diffusion calculations were performed using the US NRC core simulator PARCS employing the two few-group constant sets generated in the first

  5. Analysis of steam condensation in APR1400 IRWST for loss of coolant accident

    International Nuclear Information System (INIS)

    Oh, Young Suk

    2006-02-01

    The In-Containment Refueling Water Storage Tank (IRWST) of APR1400 is installed at the bottom of containment building to promote the plant safety functions during an accident. This design feature brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised when an accident occurs. The hot steam which is released from RCS break enters the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, in which water is colder than incoming steam. The purpose of this study is to investigate the influence of IRWST and pressure relief damper on back pressure and temperature in APR1400 containment codes such as CONTEMPT-LT and GOTHIC. The comparison of codes showed that GOTHIC code be more appropriate for the prediction of containment pressure and temperature under the condition of steam condensation occurring in confined water pool. Especially, the GOTHIC has superior capability to treat multi-compartmentalized geometry This study developed one-compartment (single) model, two-compartment (separated) model, and three-dimension (3-D) model, respectively. Two compartment model separates the IRWST from the other containment compartments. In 3-D model, only the IRWST is nodalized with Cartesian modeling. The single model is developed for comparison with two-compartment model which can analyze PRD's influence. The separated model for predicting PRD's influence divides the space between containment and IRWST. 3-D model for IRWST was generated because it is not symmetric considering location of sparger, pump, and suction sump. Therefore, IRWST is simulated with not only detailed three-dimensional behavior but also independent flow paths for four PRDs. Many experimental studies for the direct-contact heat transfer in stratified steam water flows, cocurrent or countercurrent, have been performed (Segev et al., 1981; Lim et al., 1981; Kim and

  6. Best-estimated multi-dimensional calculation during LB LOCA for APR1400

    International Nuclear Information System (INIS)

    Oh, D. Y.; Bang, Y. S.; Cheong, A. J.; Woong, S.; Korea, W.

    2010-01-01

    Best-estimated (BE) calculation with uncertainty quantification for the emergency core cooling system (ECCS) performance analysis during Loss of Coolant Accident (LOCA) is more broadly used in nuclear industries and regulations. In Korea, demand on regulatory audit calculation is continuously increasing to support the safety review for life extension, power up-rating and advanced nuclear reactor design. The thermal-hydraulic system code, MARS (Multi-dimensional Analysis of Reactor Safety), with multi-dimensional capability is used for audit calculation. It achieves to describe the complicated phenomena in reactor coolant system by very effectively consolidating the one dimensional RELAP5/MOD3 with the multidimensional COBRA-TF codes. The advanced power reactors (APR1400) to be evaluated has four separated hydraulic trains of the high pressure injection system (HPSI) with direct vessel injection (DVI) which is different from the existing commercial PWRs. Also, the therma-hydraulic behavior of DVI plant would be considerably different from that of a cold-leg safety injection since the low pressure safety injection system are eliminated and the high pressure safety flow are injected into the specific elevation of reactor vessel downcomer. The ECCS bypass induced by the downcomer boiling due to hot wall heating of reactor vessel during reflooding phase is one of the important phenomena which should be considered in DVI plants. Therefore, in this study, BE calculation with one-dimensional (1-D) and multi-dimensional (multi-D) MARS models during LBLOCA are performed for APR1400 plant. In the multi-D evaluation, the reactor vessel is modeled by multi-D components and the specific treatment of flow path inside reactor vessel, e.g., upper guide structure, is essential. The concept of hot zone is adopted to simulate the limiting thermal-hydraulic conditions surrounding hot rod, which is similar to hot channel in 1-D. Also, alternative treatment of the hot rods in multi-D is

  7. Numerical Analysis of Molten Corium Dispersion during Hypothetical High-Pressure Accidents in APR1400 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kim, Jong Tae; Ha, Kwang Soon; Kim, Sang Baik; Kim, Hee Dong; Jeong, Jae Sik

    2010-01-01

    During a hypothetical high-pressure accident in a nuclear power plant (NPP), molten corium can be ejected through a breach of a reactor pressure vessel (RPV) and dispersed by the following jet of a high pressure steam in the RPV. The dispersed corium is fragmented into smaller droplets in a reactor cavity of the NPP by the steam jet with very high velocity and is released into the upper compartment of the NPP by an overpressure in the cavity. The heat-carrying fragments of the corium transfer the thermal energy to the ambient air in the containment and react chemically with steam and generate hydrogen which may be burnt in the containment. The thermal loads from the ejected molten corium on the containment which is called direct containment heating (DCH) can threaten the integrity of the containment. New generation NPPs such as APR1400 and EPR have been designed in consideration of reducing the possibility of the containment failure from the DCH. In order for that, APR1400 has a convolute-type corium chamber connected to the reactor cavity. In the case of EPR, severe-accident dedicated depressurization valves are installed to preclude a high pressure melt ejection (HPME). DCH in a NPP containment is related to many physical phenomena such as multi-phase hydrodynamics, thermodynamics and chemical reaction. In the evaluation of the DCH load, the melt dispersion rates depending on the RPV pressure are the most important parameter. Mostly, DCH was evaluated by using lumped-analysis codes with some correlations obtained from experiments for the dispersion rates. The corium dispersion rates for many types of the NPP containments had been obtained by experiments in 90s. And some correlations from the experimental data were developed. As mentioned above, APR1400 has a corium chamber to reduce the corium dispersion rate. But there is no experimental data for the dispersion rate specific to the APR1400 cavity geometry. So its performance for capturing of the dispersed corium

  8. Modeling of melt retention in EU-APR1400 ex-vessel core catcher

    Energy Technology Data Exchange (ETDEWEB)

    Granovsky, V. S.; Sulatsky, A. A.; Khabensky, V. B.; Sulatskaya, M. B. [Alexandrov Research Inst. of Technology NITI, Sosnovy Bor (Russian Federation); Gusarov, V. V.; Almyashev, V. I.; Komlev, A. A. [Saint Petersburg State Technological Univ. SPbSTU, St.Petersburg (Russian Federation); Bechta, S. [KTH, Stockholm (Sweden); Kim, Y. S. [KHNP, 1312 Gil 70, Yuseongdaero, Yuseong-gu, Daejeon (Korea, Republic of); Park, R. J.; Kim, H. Y.; Song, J. H. [KAERI, 989 Gil 111, Daedeokdaero, Yuseong-gu, Daejeon (Korea, Republic of)

    2012-07-01

    A core catcher is adopted in the EU-APR1400 reactor design for management and mitigation of severe accidents with reactor core melting. The core catcher concept incorporates a number of engineering solutions used in the catcher designs of European EPR and Russian WER-1000 reactors, such as thin-layer corium spreading for better cooling, retention of the melt in a water-cooled steel vessel, and use of sacrificial material (SM) to control the melt properties. SM is one of the key elements of the catcher design and its performance is critical for melt retention efficiency. This SM consists of oxide components, but the core catcher also includes sacrificial steel which reacts with the metal melt of the molten corium to reduce its temperature. The paper describes the required properties of SM. The melt retention capability of the core catcher can be confirmed by modeling the heat fluxes to the catcher vessel to show that it will not fail. The fulfillment of this requirement is demonstrated on the example of LBLOCA severe accident. Thermal and physicochemical interactions between the oxide and metal melts, interactions of the melts with SM, sacrificial steel and vessel, core catcher external cooling by water and release of non-condensable gases are modeled. (authors)

  9. Development of a Desktop Simulator for APR1400 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lee, J. B.

    2016-01-01

    It is essential for utilities to possess a full-scope simulator for operator training and operation test for operators. But it is very expensive and sometimes lack of fidelity if processes of developing the simulator and designing the plant are in parallel. It is due to the situation that simulator development stage sometimes precedes the plant design stage and modifications may occur to the design of the plant in construction stage. In an attempt to build a low cost and efficient simulator, a desktop simulator has been developed. This model is described herein. Using desktop simulators for training operators is an efficient method for familiarizing operators with their plant’s operation. A low cost and efficient desktop simulator for APR1400 has been developed, and brief features are introduced here. It is configured to mimic a full-scale simulator, and can be used for operators to be familiarized to their plant’s operation. Since the size of the simulator is small enough to be fit in a desk, it can be used in a classroom or in an office at any time. It can also be used to evaluate design changes or modifications of the plant before implementing them to the plant

  10. Consolidation and Decomposition of APR1400 NRC Design Certification Processes for Collaborative and Accelerated Processing

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Young Chul [FNC Technology Co., Yongin (Korea, Republic of); Kang, Deog Ji [KNHP, Daejeon (Korea, Republic of)

    2016-05-15

    KEPCO and KHNP are conducting APR1400 Design Certification from NRC. For the proper management of processes and information, a system called RIS (Regulatory Information management System) has been implemented by FNC from 2014, and it is on the final stage. In retaining the certification from NRC, RIS will be a very essential role by providing platform for collaborative and accelerated processing of responses to RAI (Request of Additional Information). Preparation of responses to RAI with this kind of systematic approach may be the first in the world. Westinghouse is doing manually and using MS Excel to collect the processing status. Where as, RIS will enable each member can do his own job and collect the status automatically. In this paper, how collaborative and accelerated processing of responses to RAI can be enabled will be described, and further enhancements will also be discussed. It handles MS Word directory with the help of VSTO. And with the help of Aspose.Total for .NET, the prepared response to RAI meets NRC's requirements. Through some further work and direct integration with requirement management solution, RIS can be expanded to cover a prior impact notice in case of DCD being altered.

  11. Evaluation on thermal-hydraulic characteristics for passive safety device of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Seong Yeon; Lee, S. H.; Son, M. K. [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Jee, M. S.; Chung, M. H. [Chungnam National Univ., Taejon (Korea, Republic of)

    2001-07-15

    To establish evaluation and verification guideline for the APR1400, thermal-hydraulic characteristics for fuel rod bundle, reactor vessel and fluidic device is analyzed using FLUENT. Scope and major results of research are as follows : Thermal-hydraulic characteristics for nuclear fuel rod bundle: design data for nuclear fuel rod bundle and structure are surveyed, and 3 x 3 sub-channel model is adopted to investigate the fluid flow and heat transfer characteristics in fuel rod bundle. Computational results are compared with the heat transfer data measured by naphthalene sublimation method, and numerical analysis and evaluation are performed at various design conditions and flow conditions. Thermal-hydraulic characteristics for reactor vessel: reactor vessel design data are surveyed to develop numerical model. Porous media model is applied for fuel rod bundle, and full-scale, three dimensional simulation is performed at actual operating conditions. Distributions of velocity, pressure and temperature are discussed. Flow characteristics for fluidic device: three dimensional numerical model for fluidic device is developed, and numerical results are compared with experimental data obtained at KAERI in order to verify numerical simulation. In addition, variation of flow rate is investigated at various elapsed times after valve operating, and flow characteristics is analyzed at low and high flow rate conditions, respectively.

  12. Improved Design of PECS to reduce Flow Instability for EU-APR1400

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Keunsung

    2014-01-01

    For EU-APR1400, PECS (Passive Ex-vessel corium retaining and Cooling System), so-called core catcher, was adopted to keep the integrity of basemat in containment by preventing MCCI (Molten Core Concrete Interaction) through retaining core debris and cooling corium outside the reactor vessel. In this paper, the improved design of PECS is presented to increase coolability by reducing flow instability in the region of cooling channel. In this paper, flow instability analysis was carried out using CFD code to find out the most improved design of PECS, which is to increase coolability by reducing bubble entrainment in the region of cooling channel. The reduction of bubble entrainment in the downcomer facilitates higher mass flow rates in the downcomer. Among presented four designed for the downcomer of PECS, the superstep design shows the highest mass flow rate and the lowest gas holdup in the downcomer as well as in the cooling channel. Compared with the existing design, the elimination of the horizontal part and the addition of an extra space above the vertical entrance to the downcomer seem to help the separation of the vapor

  13. Development of Alarm System link Drawing for Operation Support for APR1400 Digital Main Control Room

    International Nuclear Information System (INIS)

    Kim, Ki-Hwan

    2016-01-01

    Digitalized MMI(Man-Machine Interface) including Digital Main Control Room(MCR) and digital I and C system was being applied for SKN 3 and 4 Nuclear Power Plant(NPP) and subsequent APR1400 NPP type. But, operators can not easily find instrument for alarm immediately. Therefore, Alarm system is required to easily find instrument for Alarm. For this implementation, we will plan system design considering design feature without affecting network load and CPU load. We have developed Alarm system link drawing for digital MCR. Operators of the digitalized MCR navigates from their consoles to the drawings related to the plant alarms and their instruments or the operation status. Such method gives cognitive load to the operators having to travel to different locations in finding the related information. Screen Sharing System, which is the fundamental technique for Drawing Interconnection Alarm System is close to completion, and it should be functionally tested and verified by the human factor engineering. For the actual application to the operating plants, the drawings to be interconnected to the alarms and the opinions from the operators/maintenance departments for designating alarm number should be surveyed, Also, another function that allows the access to the alarm related drawings not only from the MCR but also from the other offices

  14. Development of Alarm System link Drawing for Operation Support for APR1400 Digital Main Control Room

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ki-Hwan [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Digitalized MMI(Man-Machine Interface) including Digital Main Control Room(MCR) and digital I and C system was being applied for SKN 3 and 4 Nuclear Power Plant(NPP) and subsequent APR1400 NPP type. But, operators can not easily find instrument for alarm immediately. Therefore, Alarm system is required to easily find instrument for Alarm. For this implementation, we will plan system design considering design feature without affecting network load and CPU load. We have developed Alarm system link drawing for digital MCR. Operators of the digitalized MCR navigates from their consoles to the drawings related to the plant alarms and their instruments or the operation status. Such method gives cognitive load to the operators having to travel to different locations in finding the related information. Screen Sharing System, which is the fundamental technique for Drawing Interconnection Alarm System is close to completion, and it should be functionally tested and verified by the human factor engineering. For the actual application to the operating plants, the drawings to be interconnected to the alarms and the opinions from the operators/maintenance departments for designating alarm number should be surveyed, Also, another function that allows the access to the alarm related drawings not only from the MCR but also from the other offices.

  15. The Development and Evaluation of Inherent RPCS for the APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jae D.; Ryu, Seok H.; Jung, Dong C.; Kim, Joon S.; Baek, Byung C.; Sung, Song K.; You, Guk J. [KNF, Daejeon (Korea, Republic of); Kim, Han G. [KHNP, Daejeon (Korea, Republic of); Chi, Sung G. [KOPEC, Daejeon (Korea, Republic of)

    2008-10-15

    The APR1400 RPCS (Reactor Power Cutback System) is designed to rapidly reduce the core power to eliminate the need for a reactor trip following a large load rejection or a loss of two main feedwater pumps at high power. GDC (General Design Criteria) 25 says 'Protection system requirements for reactivity control malfunctions. The protection system shall be designed to assure that SAFDL (Specified Acceptable Fuel Design Limits) are not exceeded for any single malfunction of the reactivity control systems, such as accidental withdrawal (not ejection or dropout) of control rods.' In order to comply GDC 25, CPCS (Core Protection Calculator System) will apply a big power penalty({approx} 1.3) to determine the minimum DNBR (Departure from Nucleate Boiling Ratio), the maximum LPD(Local Power Density) and reactor may immediately trip by CPCS low DNBR and high LPD during high power operation for 12-finger CEA drop. The purpose of this study is to develop the inherent RPCS to avoid unwanted reactor trips due to a 12-finger CEA drop. In order to accomplish this purpose, the CPCS should be modified to send RPCS actuation signal and not to apply power penalty due to 12-finger CEA drop for a shot period. During this period which is determined by assessment of safety, the SAFDL will not be violated without any CPCS trip function. The system and CPCS performance is evaluated to verify that CPCS trip does not occurred during 12-finger CEA drop event.

  16. Development of a Desktop Simulator for APR1400 Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. B. [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    It is essential for utilities to possess a full-scope simulator for operator training and operation test for operators. But it is very expensive and sometimes lack of fidelity if processes of developing the simulator and designing the plant are in parallel. It is due to the situation that simulator development stage sometimes precedes the plant design stage and modifications may occur to the design of the plant in construction stage. In an attempt to build a low cost and efficient simulator, a desktop simulator has been developed. This model is described herein. Using desktop simulators for training operators is an efficient method for familiarizing operators with their plant’s operation. A low cost and efficient desktop simulator for APR1400 has been developed, and brief features are introduced here. It is configured to mimic a full-scale simulator, and can be used for operators to be familiarized to their plant’s operation. Since the size of the simulator is small enough to be fit in a desk, it can be used in a classroom or in an office at any time. It can also be used to evaluate design changes or modifications of the plant before implementing them to the plant.

  17. Preliminary COM3D Analysis for H{sub 2} Combustion in the APR1400 Containment

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Hyung Seok; Kim, Jongtae; Kim, Sang-Baik; Hong, Seong-Wan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    In order to assure the containment integrity of APR1400, it is necessary to evaluate an overpressure buildup resulting from a propagation of hydrogen flame along the structure and wall in the containment during a severe accident using the COM3D. Korea Atomic Energy Research Institute (KAERI) established a numerical analysis system for evaluating an overpressure buildup owing to a hydrogen combustion in the containment of a nuclear power plant by importing COM3D from KIT in Germany. The COM3D has been currently used in the simulations of the combustions and explosions, together with the system of industrial risk mitigation of hydrogen and burnable gases in nuclear containment and auxiliary buildings. KAERI performed the hydrogen combustion analysis using the COM3D code with the initial hydrogen distribution calculated by the GASFLOW under assumption of 85% metal-water reaction in the reactor vessel. From the COM3D results, we can know that the pressure buildup was about 100 kPa because the flame speed was not increased above 1000 m/s and the pressure wave passed through the open spaces in the large containment.

  18. Evaluation Methodology for Void Swelling Susceptibility of APR1400 Reactor Vessel Internals for U.S. NRC Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kweon, Hyeong Do; Lee, Do Hwan [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The APR1400 RVI (Reactor Vessel Internals) operates in harsh conditions, such as long term exposure to neutron irradiation, high temperatures, reactor coolant environment, and other operating loads. Therefore, even though the RVI components are mainly made of austenitic stainless steel which is well known to have good mechanical and corrosion-resistive properties, these operating conditions. The aging is characterized by a chromium depletion along grain boundaries of austenitic stainless steel, a decrease in ductility and fracture toughness of the steel, an increase in yield and ultimate strength of the steel, and a potential volume change due to void formation in the steel. For these reasons, under certain conditions of stress, temperature, and level of irradiation, the void swelling which is one of the challenging degradation mechanisms affecting the integrity of the RVI may appear at specific locations of the RVI, especially due to high neutron fluence and high temperature under localized gamma heating and low velocity of coolant flow. To assess the effects of operating neutron fluences, temperatures and stresses on the material properties changes and the susceptibility to the void swelling, the evaluation methodology of the APR1400 RVI components for U.S. NRC Design Certification was suggested in this paper. The approach to the evaluation is summarized as follows: 1. RVI component list of the APR1400 is collected. 2. Initial screening to determine the evaluation scope is completed using the design values of fluences. 3. Functionality assessments (radiation transport analysis, CFD analysis, structural analysis) are sequentially performed. 4. Susceptibility to the void swelling is identified through ANSYS/USERMAT module. KHNP believes that the proposed methodology which is based on the EPRI works for operating reactors is the best way to evaluate the void swelling for new reactors such as the APR1400.

  19. Drop size measurements and entrainment in APR1400 during LBLOCA reflood phase

    International Nuclear Information System (INIS)

    Lee, Eo Hwak

    2010-02-01

    A study has been performed to investigate droplet size in the nuclear reactor of APR1400 during LBLOCA reflood phase and to develop droplet entrainment and deposition models for SPACE (Safety and Performance CodE) which is a safety analysis tool for PWR being developed in Korea. A freezing technique for measuring the size of droplets was developed to obtain the droplet size distribution in horizontal annular flow in a pipe with a 37.1 mm diameter. Droplets are frozen by using an extremely low temperature nitrogen gas with liquid film extraction. They are then photographed with a microscope and a CCD camera and measured by means of an image process. The results are compared with various experimental data. The droplet sizes measured by the freezing technique are comparable with those measured by other methods at a high superficial air velocity (of 50 m/s). However, because of the film extraction problem, the droplet sizes measured at a low superficial air velocity of less than 40 m/s are higher than those measured by other methods. A present method suggested for predicting the Sauter mean diameter is based on the maximum droplet size correlation for the experimental data, with and without liquid film extraction. The average droplet size is remarkably smaller downstream of the liquid film extractor because large droplets from the liquid film are excluded. In order to understand and to predict a heat transfer between superheated steam and droplets properly during reflood phase of LBLOCA, it is very important to measure broken droplet sizes by spacer grids. A study, therefore, has been performed to investigate droplet size in rod bundles with spacer grids and to develop a spacer grid droplet breakup model for safety analysis codes. Experiments were conducted with liquid droplets (SMD of 300∼700 μm) and various spacer grids at superficial air velocity of 10 m/s and 20 m/s based on FLECHT SEASET. The test channel and the grids were heated to 150 .deg. C to prevent

  20. Drop size measurements and entrainment in APR1400 during LBLOCA reflood phase

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eo Hwak

    2010-02-15

    A study has been performed to investigate droplet size in the nuclear reactor of APR1400 during LBLOCA reflood phase and to develop droplet entrainment and deposition models for SPACE (Safety and Performance CodE) which is a safety analysis tool for PWR being developed in Korea. A freezing technique for measuring the size of droplets was developed to obtain the droplet size distribution in horizontal annular flow in a pipe with a 37.1 mm diameter. Droplets are frozen by using an extremely low temperature nitrogen gas with liquid film extraction. They are then photographed with a microscope and a CCD camera and measured by means of an image process. The results are compared with various experimental data. The droplet sizes measured by the freezing technique are comparable with those measured by other methods at a high superficial air velocity (of 50 m/s). However, because of the film extraction problem, the droplet sizes measured at a low superficial air velocity of less than 40 m/s are higher than those measured by other methods. A present method suggested for predicting the Sauter mean diameter is based on the maximum droplet size correlation for the experimental data, with and without liquid film extraction. The average droplet size is remarkably smaller downstream of the liquid film extractor because large droplets from the liquid film are excluded. In order to understand and to predict a heat transfer between superheated steam and droplets properly during reflood phase of LBLOCA, it is very important to measure broken droplet sizes by spacer grids. A study, therefore, has been performed to investigate droplet size in rod bundles with spacer grids and to develop a spacer grid droplet breakup model for safety analysis codes. Experiments were conducted with liquid droplets (SMD of 300∼700 μm) and various spacer grids at superficial air velocity of 10 m/s and 20 m/s based on FLECHT SEASET. The test channel and the grids were heated to 150 .deg. C to prevent

  1. Review on the NEI Methodology of Debris Transport Analysis in Sump Blockage Issue for APR1400

    International Nuclear Information System (INIS)

    Kim, Jong Uk; Lee, Jeong Ik; Hong, Soon Joon; Lee, Byung Chul; Bang, Young Seok

    2007-01-01

    Since USNRC (United State Nuclear Regulatory Committee) initially addressed post-accident sump performance under Unresolved Safety Issue USI A-43, sump blockage issue has gone through GSI-191, Regulation Guide 1.82, Rev. 3 (RG. 1.82 Rev.3), and generic Letter 2004-02 for PWRs (Pressurized Water Reactors). As a response of these USNRC's activities, NEI 04-07 was issued in order to evaluate the post-accident performance of a plant's recirculation sump. The baseline methodology of NEI 04-07 is composed of break selection, debris generation, latent debris, debris transport, and head loss. In analytical refinement of NEI 04-07, computational fluid dynamic (CFD) is suggested for the evaluation of debris transport in emergency core cooling (ECC) recirculation mode as guided by RG. 1.82 Rev.3. In Korea nuclear industry also keeps step with international activities of this safety issue, with Kori 1 plant as a pioneering edge. Korean nuclear industry has been also pursuing development of an advanced PWR of APR1400, which incorporates several improved safety features. One of the key features, considering sump blockage issue, is the adoption of IRWST (In-containment Refueling Water Storage Tank). This device, as the acronym implies, changes the emergency core cooling water injection pattern. This fact makes us to review the applicability of NEI 04-07's methodology. In this paper we discuss the applicability of NEI 04- 07's methodology, and more over, new methodology is proposed. And finally the preliminary debris transport is analyzed

  2. Feasibility Study of Core Design with a Monte Carlo Code for APR1400 Initial core

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jinsun; Chang, Do Ik; Seong, Kibong [KEPCO NF, Daejeon (Korea, Republic of)

    2014-10-15

    The Monte Carlo calculation becomes more popular and useful nowadays due to the rapid progress in computing power and parallel calculation techniques. There have been many attempts to analyze a commercial core by Monte Carlo transport code using the enhanced computer capability, recently. In this paper, Monte Carlo calculation of APR1400 initial core has been performed and the results are compared with the calculation results of conventional deterministic code to find out the feasibility of core design using Monte Carlo code. SERPENT, a 3D continuous-energy Monte Carlo reactor physics burnup calculation code is used for this purpose and the KARMA-ASTRA code system, which is used for a deterministic code of comparison. The preliminary investigation for the feasibility of commercial core design with Monte Carlo code was performed in this study. Simplified core geometry modeling was performed for the reactor core surroundings and reactor coolant model is based on two region model. The reactivity difference at HZP ARO condition between Monte Carlo code and the deterministic code is consistent with each other and the reactivity difference during the depletion could be reduced by adopting the realistic moderator temperature. The reactivity difference calculated at HFP, BOC, ARO equilibrium condition was 180 ±9 pcm, with axial moderator temperature of a deterministic code. The computing time will be a significant burden at this time for the application of Monte Carlo code to the commercial core design even with the application of parallel computing because numerous core simulations are required for actual loading pattern search. One of the remedy will be a combination of Monte Carlo code and the deterministic code to generate the physics data. The comparison of physics parameters with sophisticated moderator temperature modeling and depletion will be performed for a further study.

  3. Onset of liquid droplet entrainment on a direct vessel injection system for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Han-sol; Lee, Jae-Young [Handong Global University, Pohang (Korea, Republic of); Kim, Jong-Rok; Euh, Dong-Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this research, a series of visualization works was conducted to understand droplet entrainment of the flow pattern generated in direct vessel injection system(DVI) of Korea nuclear power plant, APR 1400. In the emergency situation of a nuclear power plant, reliability of DVI cooling can be an important issue. It is known that, the amount and the rate of entrainment during the DVI cooling process can significantly affect the total heat removal. To visualize the film Reynolds number closely related with onset of droplet entrainment induced by falling film flow and lateral air flow in a small gap, confocal chromatic sensing method for measuring accurately film thickness and depth averaging particle image velocimetry for film velocity were used. The results have been post processed 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. To visualize the droplet entrainment induced by falling film flow and lateral air flow in a small gap, shadowgraph method with CCD camera (2200fps, 1280 pixel X 800 pixel, ) on coated plate with super water-repellent agent was used. The results have been post processed using 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. By adopting both super hydrophobic coating method and shadowgraph method, entrainment in a narrow gap was successfully visualized that has rarely performed before and meaningful results for DVI system research fields have been made.

  4. Onset of liquid droplet entrainment on a direct vessel injection system for APR1400

    International Nuclear Information System (INIS)

    Kim, Han-sol; Lee, Jae-Young; Kim, Jong-Rok; Euh, Dong-Jin

    2016-01-01

    In this research, a series of visualization works was conducted to understand droplet entrainment of the flow pattern generated in direct vessel injection system(DVI) of Korea nuclear power plant, APR 1400. In the emergency situation of a nuclear power plant, reliability of DVI cooling can be an important issue. It is known that, the amount and the rate of entrainment during the DVI cooling process can significantly affect the total heat removal. To visualize the film Reynolds number closely related with onset of droplet entrainment induced by falling film flow and lateral air flow in a small gap, confocal chromatic sensing method for measuring accurately film thickness and depth averaging particle image velocimetry for film velocity were used. The results have been post processed 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. To visualize the droplet entrainment induced by falling film flow and lateral air flow in a small gap, shadowgraph method with CCD camera (2200fps, 1280 pixel X 800 pixel, ) on coated plate with super water-repellent agent was used. The results have been post processed using 4G Insight software. By measuring two dimensional film Reynolds number, we can predict the onset of droplet entrainment and obtain visible breakup region intuitively. By adopting both super hydrophobic coating method and shadowgraph method, entrainment in a narrow gap was successfully visualized that has rarely performed before and meaningful results for DVI system research fields have been made

  5. Analysis of a molten pool natural convection in the APR1400 RPV at a severe accident

    International Nuclear Information System (INIS)

    Kim, Jong Tae; Park, Rae Joon; Kim, Sang Baik

    2005-01-01

    During a hypothetical severe accident, reactor fuel rods and structures supporting them are melted and relocated in the lower head of the reactor vessel. These relocated molten materials could be separated by their density difference and construct metal/oxide stratified pools in the lower head. A decay heat generated from the fuel material is transferred to the vessel wall and upper structures remaining in the reactor vessel by natural convection. As shown in Fig. 1 two-layered stratified molten pool is developed in the reactor lower vessel. The oxidic pool usually constructed by the mixture of uranium oxide and zirconium oxide. The melting temperature of the oxidic material is very high compared to the steel vessel and metallic layer. And highly turbulent natural convection generated by the decay heat enhances heat transfer to the boundary of the oxidic pool. By this thermal mechanism, oxide curst is developed around the oxidic layer as shown in Fig. 1. The oxidic pool is bounded thermally and fluid-dynamically by the developed crust. By this boundedness, the heat transfer structure in the stratified oxidic/metallic pool can be solved separately. The thermal boundary condition of the oxidic pool is isothermal with constant melting temperature of the oxidic material. The decay heat is transfer to side wall and upper interface between oxidic and metallic layer. Turbulent natural convection is dominant heat transfer mechanism in the oxidic pool. The heat transferred from the bottom oxidic layer is imposed to the upper metallic layer. This transferred heat in the metallic pool is removed through side and upper surface, which is augmented also by natural convection developed in the pool. In this study, a molten pool natural convection in the APR1400 RPV during a severe accident is simulated using the Lilac code and the calculated heat flux distribution on the reactor vessel wall is compared with a lumped-parameter (LP) prediction

  6. A Study on the Embedment Effect in the Soil-Structure Interaction Analysis of the APR1400

    International Nuclear Information System (INIS)

    Young-Sun Jang; Kwang-Ho Joo; Chong-Hak Kim

    2002-01-01

    The SSI (Soil-Structure Interaction) analyses are being performed for the APR1400 (Advanced Power Reactor 1400 MWe, Old name - KNGR; Korean Next Generation Reactor) design, because the APR1400 is developed as a Standard Nuclear Power Plant concept enveloping suitable soil conditions. For the SSI analyses, SASSI program which adopts the Flexible Volume Method is used. In the SSI analyses, there can be uncertainties by Bond and De-bond problem between the structure and lateral soil elements. According to ASCE Standard 4, one method to address this concern is to assume no connectivity between structure and lateral soil over the upper half of the embedment of 20 ft (6 m), whichever is less. This study is performed as a part of the parametric analyses for the APR1400 seismic analyses to address the concern of the potential embedment effect on the in-structure response spectra due to connectivity between structure and lateral soil. In this study, 4 model cases are analyzed to check the potential embedment effect - Full connection, 20 ft no connectivity which is defined as a minimum De-bond depth of the soil in ASCE Standard 4 and 26.5 ft no connectivity between structure and lateral soil over the upper half of the embedment. Last one is full no connection for only reference. The in-structure response spectra are compared with the response spectra without considering the embedment effect. (authors)

  7. Investigation of the Condensation Effect at IRWST Pool Surface on Containment Back Pressure in APR1400 Containment

    International Nuclear Information System (INIS)

    Lee, Eui Jong; Lee, Jin Yong; Lee, Byung Chul

    2006-01-01

    The APR1400 has several new design concepts in order to improve the plant safety functions during a postulated accident. The In-Containment Refueling Water Storage Tank (IRWST) is one of the new design concepts of APR1400 and installed at the bottom of containment building to promote the plant safety functions by simplifying emergency core cooling water source and preventing release of the fission product during an accidents. This design feature, however, brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised under accident conditions. The hot steam which is released from RCS break enters into the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, colder than incoming steam. The purpose of this study is to examine closely the influence of the condensation effect at IRWST on containment back pressure in APR1400 containment building using the GOTHIC code which can predict the steam condensation on IRWST pool surface

  8. Cold-Leg Small Break LOCA Analysis of APR1400 Plant Using a SPACE/sEM Code

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Sang Gyu; Lee, Suk Ho; Yu, Keuk Jong; Kim, Han Gon; Lee, Jae Yong [Central Research Institute, KHNP, Ltd., Daejeon (Korea, Republic of)

    2013-10-15

    The Small Break Loss-of-Coolant Accident (SBLOCA) evaluation methodology (EM) for APR1400, called sEM, is now being developed using SPACE code. SPACE/sEM is to set up a conservative evaluation methodology in accordance with appendix K of 10 CFR 50. Major required and acceptable features of the evaluation models are described as below. - Fission product decay : 1.2 times of ANS97 decay curve - Critical flow model : Henry-Fauske Moody two phase critical flow model - Metal-Water reaction model : Baker-Just equation - Critical Heat Flux (CHF) : B and W, Barnett and Modified Barnett correlation - Post-CHF : Groeneveld 5.7 film boiling correlation A series of test matrix is established to validate SPACE/sEM code in terms of major SBLOCA phenomena, e.g. core level swelling and boiling, core heat transfer, critical flow, loop seal clearance and their integrated effects. The separated effect tests (SETs) and integrated effect tests (IETs) are successfully performed and these results shows that SPACE/sEM code has a conservatism comparing with experimental data. Finally, plant calculations of SBLOCA for APR1400 are conducted as described below. - Break location sensitivity : DVI line, hot-leg, cold-leg, pump suction leg. - Break size spectrum : 0.4ft{sup 2}∼0.02ft{sup 2}(DVI) 0.5ft{sup 2}∼0.02ft{sup 2}(hot-leg, cold-leg, pump suction leg) This paper deals with break size spectrum analysis of cold-leg break accidents. Based on the calculation results, emergency core cooling system (ECCS) performances of APR1400 and typical SBLOCA phenomena can be evaluated. Cold-leg SBLOCA analysis for APR1400 is performed using SPACE/sEM code under harsh environment condition. SPACE/sEM code shows the typical SBLOCA behaviors and it is reasonably predicted. Although SPACE/sEM code has conservative models and correlations based on appendix K of 10 CFR 50, PCT does not exceed the requirement (1477 K). It is concluded that ECCS in APR1400 has a sufficient performance in cold-leg SBLOCA.

  9. Cold-Leg Small Break LOCA Analysis of APR1400 Plant Using a SPACE/sEM Code

    International Nuclear Information System (INIS)

    Lim, Sang Gyu; Lee, Suk Ho; Yu, Keuk Jong; Kim, Han Gon; Lee, Jae Yong

    2013-01-01

    The Small Break Loss-of-Coolant Accident (SBLOCA) evaluation methodology (EM) for APR1400, called sEM, is now being developed using SPACE code. SPACE/sEM is to set up a conservative evaluation methodology in accordance with appendix K of 10 CFR 50. Major required and acceptable features of the evaluation models are described as below. - Fission product decay : 1.2 times of ANS97 decay curve - Critical flow model : Henry-Fauske Moody two phase critical flow model - Metal-Water reaction model : Baker-Just equation - Critical Heat Flux (CHF) : B and W, Barnett and Modified Barnett correlation - Post-CHF : Groeneveld 5.7 film boiling correlation A series of test matrix is established to validate SPACE/sEM code in terms of major SBLOCA phenomena, e.g. core level swelling and boiling, core heat transfer, critical flow, loop seal clearance and their integrated effects. The separated effect tests (SETs) and integrated effect tests (IETs) are successfully performed and these results shows that SPACE/sEM code has a conservatism comparing with experimental data. Finally, plant calculations of SBLOCA for APR1400 are conducted as described below. - Break location sensitivity : DVI line, hot-leg, cold-leg, pump suction leg. - Break size spectrum : 0.4ft 2 ∼0.02ft 2 (DVI) 0.5ft 2 ∼0.02ft 2 (hot-leg, cold-leg, pump suction leg) This paper deals with break size spectrum analysis of cold-leg break accidents. Based on the calculation results, emergency core cooling system (ECCS) performances of APR1400 and typical SBLOCA phenomena can be evaluated. Cold-leg SBLOCA analysis for APR1400 is performed using SPACE/sEM code under harsh environment condition. SPACE/sEM code shows the typical SBLOCA behaviors and it is reasonably predicted. Although SPACE/sEM code has conservative models and correlations based on appendix K of 10 CFR 50, PCT does not exceed the requirement (1477 K). It is concluded that ECCS in APR1400 has a sufficient performance in cold-leg SBLOCA

  10. Development of an amphibious robot for visual inspection of APR1400 Npp IRWST strainer

    International Nuclear Information System (INIS)

    Jang, You Hyun; Kim, Jong Seog

    2014-01-01

    An amphibious inspection robot system (hereafter AIROS) is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST) strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of installing sole

  11. Development of an amphibious robot for visual inspection of APR1400 Npp IRWST strainer

    Energy Technology Data Exchange (ETDEWEB)

    Jang, You Hyun; Kim, Jong Seog [Korea Hydro Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)

    2014-06-15

    An amphibious inspection robot system (hereafter AIROS) is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST) strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of installing sole

  12. DEVELOPMENT OF AN AMPHIBIOUS ROBOT FOR VISUAL INSPECTION OF APR1400 NPP IRWST STRAINER ASSEMBLY

    Directory of Open Access Journals (Sweden)

    YOU HYUN JANG

    2014-06-01

    Full Text Available An amphibious inspection robot system (hereafter AIROS is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of

  13. Analysis of MSGTR events for APR1400 by means of best estimate thermal-hydraulic system code

    International Nuclear Information System (INIS)

    Jeong, Ji Hwan; Kim, Sang Jae; Chang, Keun Sun; Lee, Jae Hun

    2001-01-01

    A multiple steam generator tube rupture (MSGTR) event has never occurred in the history of commercial nuclear reactor operation while single steam generator tube rupture (SGTR) event is reported to occur every two years. As there is no history of MSGTR event, the understandings of transients and consequences of this event are not so much. In this study, a postulated MSGTR event in advanced power reactor 1400 (APR1400) is analyzed using thermal-hydraulic system code. The APR 1400 is a two-loop, 1000 MWe, PWR supposed to be built in 2009. MARS1.4 is used in this study. The present study aims to understand the effects of rupture location in heat transfer tubes and selection of affected steam generator following a MSGTR event. The effects of five tube rupture locations are compared with each other. The comparison shows that the response of APR1400 is to allow shortest time for operator action following a tubes rupture in the vicinity of hot-leg side tube sheet and to allow longest time following a tube ruptures at the tube top. The MSSV lift time for rupture at tube-top is evaluated as 24.5% larger than that for rupture at hot-leg side tube sheet. Also, the MSSV lift time for four cases are compared in order to examine how long operator response time is allowed depending on which steam generator is affected. The comparison shows that the cases for both of two steam generators are affected allow longer time for operator action compared with the cases that a single steam generator is affected. Further more, the tube ruptures in the steam generator where a pressurizer is linked leads to the shortest operator response time

  14. CFD Analysis of Random Turbulent Flow Load in Steam Generator of APR1400 Under Normal Operation Condition

    International Nuclear Information System (INIS)

    Lim, Sang Gyu; You, Sung Chang; Kim, Han Gon

    2011-01-01

    Regulatory guide 1.20 revision 3 of the Nuclear Regulatory Committee (NRC) modifies guidance for vibration assessments of reactor internals and steam generator internals. The new guidance requires applicants to provide a preliminary analysis and evaluation of the design and performance of a facility, including the safety margins of during normal operation and transient conditions anticipated during the life of the facility. Especially, revision 3 require rigorous assessments of adverse flow effects in the steam dryer cased by flow-excited acoustic and structural resonances such as the abnormality from power-uprated BWR cases. For two nearly identical nuclear power plants, the steam system of one BWR plant experienced failure of steam dryers and the main steam system components when steam flow was increased by 16 percent for extended power uprate (EPU). The mechanisms of those failures have revealed that a small adverse flow changing from the prototype condition induced severe flow-excited acoustic and structural resonances, leading to structural failures. In accordance with the historical background, therefore, potential adverse flow effects should be evaluated rigorously for steam generator internals in both BWR and Pressurized Water Reactor (PWR). The Advanced Power Reactor 1400 (APR1400), an evolutionary light water reactor, increased the power by 7.7 percent from the design of the 'Valid Prototype', System80+. Thus, reliable evaluations of potential adverse flow effects on the steam generator of APR1400 are necessary according to the regulatory guide. This paper is part of the computational fluid dynamics (CFD) analysis results for evaluation of the adverse flow effect for the steam generator internals of APR1400, including a series of sensitivity analyses to enhance the reliability of CFD analysis and an estimation the effect of flow loads on the internals of the steam generator under normal operation conditions

  15. Development of a Human Performance Evaluation Support System for Human Factors Validation of MCR MMI Design in APR-1400

    International Nuclear Information System (INIS)

    Ha, Jun Su; Seong, Poong Hyun

    2005-01-01

    As CRT-based display and advanced information technology were applied to advanced reactors such as APR-1400 (Advanced Power Reactor-1400), human operators' tasks became more cognitive works. As a results, Human Factors Engineering (HFE) became more important in designing the MCR (Main Control Room) MMI (Man-Machine Interface) of an advanced reactor. According to the Human Factors Engineering Program Review Model, human factors validation of MCR MMI design should be performed through performance-based tests to determine whether it acceptably supports safe operation of the plant. In order to support the evaluation of the performance, a HUman Performance Evaluation Support System (HUPESS) is in development

  16. Preliminary design of S-CO{sub 2} Brayton cycle for APR-1400 with power generation and desalination process

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Seong Jun; Lee, Won Woong; Jeong, Yong Hoon; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of); Yoon, Ho Joon [KUSTAR, Abu Dhabi (United Arab Emirates)

    2015-10-15

    This study was conducted to explore the capabilities of the S-CO{sub 2} Brayton cycle for a cogeneration system for APR-1400 application. Three concepts of the S-CO{sub 2} simple recuperated co-generation cycle were designed. A supercritical CO{sub 2} (S-CO{sub 2}) Brayton cycle is recently receiving significant attention as a promising power conversion system in wide range of energy applications due to its high efficiency and compact footprint. The main reason why the S-CO{sub 2} Brayton cycle has these advantages is that the compressor operates near the critical point of CO{sub 2} (30.98 .deg. C, 7.38MPa) to reduce the compression work significantly compared to the other Brayton cycles. In this study, the concept of replacing the entire steam cycle of APR-1400 with the S-CO{sub 2} Brayton cycle is evaluated. The power generation purpose S-CO{sub 2} Brayton cycles are redesigned to generate power and provide heat to the desalination system at the same time. The performance of these newly suggested cycles are evaluated in this paper. The target was to deliver 147MW heat to the desalination process. The thermal efficiencies of the three concepts are not significantly different, but the 3{sup rd} concept is relatively simpler than other cycles because only an additional heat exchanger is required. Although the 2{sup nd} concept is relatively complicated in comparison to other concepts, the temperatures at the inlet and outlet of the DHX are higher than that of the others. As shown in the results, the S-CO{sub 2} Brayton cycles are not easy to outperform the steam cycle with very simple layout and general design points under APR-1400 operating condition. However, this study shows that the S-CO{sub 2} Brayton cycles can be designed as a co-generation cycle while producing the target desalination heat with a simple configuration. In addition, it was also found that the S-CO{sub 2} Brayton cycle can achieve higher cycle thermal efficiency than the steam power cycle under

  17. Improvements on computerized procedure system of advanced power reactor 1400 MWe

    International Nuclear Information System (INIS)

    Seong, Nokyu; Jung, Yeonsub; Sung, Chanho; Kang, Sungkon

    2017-01-01

    Plant procedures are instructions to help operator in monitoring, decision making, and controlling Nuclear Power Plants (NPPs). While plant procedures conventionally have been paper-based, computerized-based procedures are being implemented to reduce the drawbacks of paper-based procedures in many nuclear power plants. The Computerized Procedure System (CPS) designed by Korea Hydro and Nuclear Power Central Research Institute (KHNP CRI) is one of the human-system interfaces (HSIs) in digitalized Main Control Room (MCR) of APR1400 (Advanced Power Reactor 1400 MWe). Currently, CPS is being applied to constructing nuclear power plants of Korea and Barakah NPP 1, 2, 3 and 4 units of United Arab Emirates. The CPS has many advantages to perform the procedure in fully digitalized MCR. First, CPS provides the procedure flow with logic diagram to operators. The operator easily can be aware of the procedure flow from a previous instruction to the next instruction and also can find out the relation between parent instruction and child instructions such as AND, OR and SEQUENCE logics. Second, CPS has three logic-based functions such as procedure entry condition monitoring logic, continuously applied step (CAS) re-execution monitoring logic and auto evaluation logic on instructions. E.g. CPS provides the standard post trip actions procedure open popup message when the reactor trips by calculating the entry condition logic that procedure writer had made in the writing process. Third, CPS can directly display the task information related to instructions such as valves, pumps, process parameters, etc. and also the operator can call the system display related to procedure execution. If an operator clicks the system display link, the related system display popups on the right side monitor of CPS display. Lastly, CPS supports the synchronization of procedure among the operators. This synchronization function helps operators to succeed the goal of procedure and improve the situation

  18. MDEP Design-Specific Common Position CP-APR1400WG-01. Common position addressing Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2016-05-01

    The MDEP APR1400 Working Group (APR1400WG) members consist of members from Republic of Korea, United Arab Emirates, and the United States. A main objectives of MDEP is to encourage convergence of code, standard and safety goals with exploring the opportunities for harmonization of regulatory practice and cooperation on safety review of APR-1400 specific designs. This common position addressing is aimed at sharing knowledge, information and experience on safety improvement related to lessons learned from the Fukushima Daiichi NPP Accident or Fukushima Daiichi NPP Accident-related issues amongst APR-1400 WG member states to achieve the MEDP goal. Because not all of these Regulators have completed the regulatory review of their APR1400 applications yet, this paper identifies common preliminary approaches to address potential safety improvements for APR1400 plants, as well as common general expectations for new nuclear power plants, as related to lessons learned from the Fukushima Daiichi NPP Accident or Fukushima Daiichi NPP Accident-related issues. While some asymmetry exists among those of three Regulators in terms of design, regulatory practice and licensing milestone sharing information and common understanding on post-Fukushima Daiichi NPP Accident enhancement would be promote resilient design for countering beyond design extreme external event like Fukushima Daiichi NPP nuclear disaster. This common position paper aims at identifying characteristics of post-Fukushima Daiichi NPP Accident enhancements putting in place by each country and setting common position to achieve balanced and harmonized APR-1400 design. After the safety reviews of the APR1400 design applications that are currently in review are completed, the regulators will update this paper to reflect their safety conclusions regarding the APR1400 design and how the design could be enhanced to address Fukushima Daiichi NPP Accident-related issues. The common preliminary approaches are organised into

  19. Human Reliability Analysis For Computerized Procedures

    International Nuclear Information System (INIS)

    Boring, Ronald L.; Gertman, David I.; Le Blanc, Katya

    2011-01-01

    This paper provides a characterization of human reliability analysis (HRA) issues for computerized procedures in nuclear power plant control rooms. It is beyond the scope of this paper to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper provides a review of HRA as applied to traditional paper-based procedures, followed by a discussion of what specific factors should additionally be considered in HRAs for computerized procedures. Performance shaping factors and failure modes unique to computerized procedures are highlighted. Since there is no definitive guide to HRA for paper-based procedures, this paper also serves to clarify the existing guidance on paper-based procedures before delving into the unique aspects of computerized procedures.

  20. Simplified study for the proposed APR1400 condenser performance based on EL-DABAA SITE, EGYPT, with respect to BNPP and SHIN KORI NPP

    Energy Technology Data Exchange (ETDEWEB)

    Abdoelatef, M. Gomaa; Rezk, Osama; Lee, YonKwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    • Perception of nuclear power as a convenient, economically competitive and viable source of energy which, if introduced in the country, would not only complement the traditional energy sources, but would also promote technological development and serve as an incentive for social and economic progress. In this paper we will introduce APR-1400 as the most likely selected reactor type for 1st Egyptian Nuclear Power Plant. Then we will study the optimized APR-1400 condenser performance based on El-Dabaa site conditions. As the climate conditions, especially the seawater temperatures (intake for the cooling system) having a direct effects on the condenser performance and the overall NPP Efficiency, we studied the seawater temperature change based on EL-Dabaa site conditions and it's feedback on the proposed APR-1400 condenser performance and the NPP efficiency. All of the calculations and analysis had been executed by using KINGS NPA by applying EL-Dabaa seawater temperature variations for the 2 types of APR-1400 Condensers (Shinkori, south Korea and Barakah, UAE), and the main findings were as follow: For the APR-1400 condensers (Shinkori and Barakah) performance • The average difference all over the year for saturation temperature, cooling water outlet temperature, and condenser pressure are 0.135 .deg. C, .05785 .deg. C, and 0.3948 mHgA respectively. This shows that the Barakah condenser performance is not significantly better than the shinkori condenser performance based on EL-Dabaa Conditions, especially if we considered the cost difference between the two condensers designs. For APR-1400 NPPs (Shinkori and Barakah) net efficiency • The average difference all over the year for the power productions and net efficiency are 1.4791 MWe and .00037 %, respectively.

  1. Mobile Computerized Procedure System for the Improved Situation Awareness among Field Workers and Main Control Room Operators

    International Nuclear Information System (INIS)

    Lee, Sungjin; Seong, Nokyu; Jung, Yeonsub

    2013-01-01

    This paper explains the technical issues of the mobile CPS (m-CPS) in the conceptual development stage. The proposed m-CPS can be developed with many recent technologies in the various industry fields based on CRI CPS. Performance and stability of CRI CPS have been tested several times until now. It is expected that more human errors can be reduced by the m-CPS through improved situation awareness and human performance tools for local workers and MCR operators. Some considerations as well as mentioned ones will be reflected in the m-CPS development. Human errors can occur during the test and maintenance of the generator, safety injection system and reactor coolant inventory in nuclear power plants (NPPs). Most of human errors have been occurred by the omission of the prevention techniques such as the self-check, the peer-check, the concurrent verification and etc. Another important reason is the insufficient information sharing among main control room (MCR) operators and field workers. Various field service automation tools have been developed with recent information technology in many countries. APR1400 computerized procedure system (CPS) has been developed for the MCR operators of Shin-Kori 3 and 4 units. Especially, the concurrent verification support design is applied in the construction project of Shin-Hanul 1 and 2 CPS. KHNP central research institute (CRI) expects that the extended application of CPS including the field activity, that is a kind of mobile CPS, can enhance the reduction of human errors

  2. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    Energy Technology Data Exchange (ETDEWEB)

    Ualikhan Zhiyenbayev [KAIST, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether.

  3. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    International Nuclear Information System (INIS)

    Ualikhan Zhiyenbayev; Chung, Dae Wook

    2015-01-01

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether

  4. Formal Verification of Computerized Procedure with Colored Petri Nets

    International Nuclear Information System (INIS)

    Kim, Yun Goo; Shin, Yeong Cheol

    2008-01-01

    Computerized Procedure System (CPS) supports nuclear power plant operators in performing operating procedures which are instructions to guide in monitoring, decision making and controlling nuclear power plants. Computerized Procedure (CP) should be loaded to CPS. Due to its execution characteristic, computerized procedure acts like a software in CPS. For example, procedure flows are determined by operator evaluation and computerized procedure logic which are pre-defined. So the verification of Computerized Procedure logic and execution flow is needed before computerized procedures are installed in the system. Formal verification methods are proposed and the modeling of operating procedures with Coloured Petri Nets(CP-nets) is presented

  5. Development of the APR1400 model for countercurrent natural circulation in hot leg and steam generator under station blackout

    International Nuclear Information System (INIS)

    Park, Sang Gil; Kim, Han Chul

    2012-01-01

    In order to analyze severe accident phenomena, Korea Institute of Nuclear Safety (KINS) made a MELCOR model for APR1400 to examine natural circulation and creep rupture failure in the Reactor Coolant System (RCS) under station blackout (SBO). In this study, we are trying to advance the former model to describe natural circulation more accurately. After Fukushima accident, the concerns of severe accident management, assuring the heat removal capability, has risen for the case when the SBO is happened and there are no more electric powers to cool down decay heat. Under SBO there are three kinds of natural circulation which can delay the core heatup. One is in vessel natural circulation in the upper plenum of reactor vessel and the second is countercurrent natural circulation in hot leg through steam generator tubes and the last is full loop natural circulation when the reactor coolant pump loop seal is cleared and reactor coolant pump sealing is damaged by high temperature and high pressure. Among them this study focuses on the countercurrent natural circulation model using MELCOR1.8.6

  6. A study on the hydrogen behavior and its mitigation in the APR1400 containment during a severe accident

    International Nuclear Information System (INIS)

    Kim, Jong Tae; Hong, Seong Wan; Park, Rae Joon; Kim, Sang Baik

    2005-02-01

    During a hypothetical severe accident in a nuclear power plant (NPP), hydrogen is generated by the active reaction of fuel-cladding and steam in the reactor pressure vessel and released with steam into the containment. In this study, the analysis of the hydrogen and steam behavior during selected severe accidents in the APR1400 containment has been conducted by using the GASFLOW code. For the SBLOCA, hydrogen was accumulated in the containment dome region quickly when only PARSs were used. When the igniters were turned on, a standing flame was formed around a coolant pump and burnt most of the hydrogen blown-out. For the TLOFW accident, the flap-type pressure damper installed at the IRWST vents strongly affected the flow structure of the hydrogen. And by the steam-rich and oxygen starvation conditions in the IRWST, DDT is not likely to occur. For the SBO accident, dry hydrogen was release in the IRWST by the assumption of full condensation of the released steam in the IRWST water. In this case, the possibility of flame acceleration is high in the IRWST and annular compartment. In this study two design modifications were proposed in view of the hydrogen mitigation strategy and their effectiveness was evaluated by the GASFLOW analysis

  7. Consideration on hydrogen explosion scenario in APR 1400 containment building during small breakup loss of coolant accident

    Energy Technology Data Exchange (ETDEWEB)

    Park, Kweonha, E-mail: khpark@kmou.ac.kr [Division of Mechanical & Energy Systems Engineering, Korea Maritime University, Dongsam-dong, Yeongdo-gu, Busan 606-791 (Korea, Republic of); Khor, Chong Lee, E-mail: itachi_829@hotmail.com [Department of Mechanical Engineering, Korea Maritime University, Dongsam-dong, Yeongdo-gu, Busan 606-791 (Korea, Republic of)

    2015-11-15

    Highlights: • Hydrogen behavior in the containment building of APR1400 nuclear plant up to 15 h after the failure happened. • The risk of hydrogen explosion largely depends on the combination of air, hydrogen and steam in the containment. • Hydrogen explosion risk at different locations in the containment was analyzed. - Abstract: This paper describes the analytical result of the potential risk of hydrogen gas up to 15 h after the failure takes place. The major cause of the disaster occurred in Fukushima Daiichi nuclear reactor was the detonation of accumulated hydrogen in the containment by highly increased reactor core temperatures after the failure of the emergency cooling system. The hydrogen risk should be considered in severe accident strategies in current and future NPPs. A hydrogen explosion scenario is proposed. Hydrogen is accumulated on top of the dome during the hydrogen release period. At this point, there are no risk of explosion due to the steam that resides in upper part of the dome. As the hydrogen concentration increase, substantial amount of steams are released. Subsequently, hydrogen is forced into the lower part of the building with high air density—small explosion and dormant steam condensation phase are possible. The light hydrogen rises up slowly with air, gathering on top of the building with high air density. Massive hydrogen explosion is anticipated upon ignition at this stage.

  8. Air clearing pressure oscillation produced in a quenching tank by a prototype unit cell sparger of the APR1400

    International Nuclear Information System (INIS)

    Cho, Seok; Song, Chul-Hwa; Park, Choon-Kyong; Kim, Hwan-Yeol; Baek, Won-Pil

    2008-01-01

    KAERI has performed a series of experiments to investigate the performance of a prototype sparger for the APR1400 in view of a dynamic load oscillation with a variation of the test conditions such as a discharged air mass, a submergence of the sparger, the valve opening time, and the pool temperature during an air clearing phase. The air mass and pool temperature are in the range of 0.8-1.5 kg and 20-90 o C, respectively. The valve opening time can be adjusted within the range of 0.6-1.8 s. The maximum positive pressure amplitude, which is observed at the bottom of the quenching tank, is increased with the maximum header pressure of the sparger. The valve opening time has a considerable effect on the maximum amplitude. As the opening time decreases, the maximum amplitude at the tank wall is increased. Air mass and pool temperature, however, have a weak effect on the maximum amplitude. Oscillation frequency is decreased with an increase of the air mass in the range of 2.5-4.5 Hz

  9. Numerical Investigation of APR1400 Loop Seal Reformation and Clearing Phenomena during Post-LOCA Long-term Cooling Period using RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. I.; Jeon, J. H.; Park, J. H.; Sung, H. J.; Lee, J. I.; Choi, T. S. [KEPCO NF, Daejeon (Korea, Republic of)

    2016-10-15

    Hand calculations had been tried to show that the loop seal reformation does not degrade the LTC performance of the APR1400, but the result was unclear. Therefore, the code assessments of the phenomena for APR1400 are required to guarantee the performance of LTC. In the present study, RELAP5/MOD3.3 patch04 (3.3iy) is used for the assessments. The safety degradation, e.g., possible cladding temperature rise due to LSRC during LTC period would be stronger when the safety injection (SI) is larger, while the core uncovery is more probable when the SI is smaller. In other words, it is not easy to determine the limiting condition of safety injection as two or four safety injection pumps (SIPs) in APR1400. In the present study, both the minimum SI condition with two SIPs and the maximum SI condition with four SIPs are considered. The study focuses only on the top slot break condition due to its highest possibility of LSRC phenomena. The LSRC issues for APR1400 are discussed and investigated through numerical investigation using RELAP5MOD3.3 patch04 for top-slot cold leg (pump discharge line) breaks. The major items investigated are whether the simultaneous four loop seal reformation is possible and whether there is any possible violation of the long term coolability criteria in 10 CFR 50.46. Safety injection with two SIPs and four SIPs are investigated to find that the four loop seal reformation condition before the simultaneous injection may occur only with four SIPs.

  10. Analysis of Post-LOCA Core Inlet Blockage to Evaluate In-vessel Downstream Effect in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Young Seok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The method was developed to have a conservatism to cover the uncertainty of analysis and the acceptance is judged by the representative bounding estimation. However, the important safety parameters such as the available driving head need to be confirmed by the plant specific calculation. Also an interaction between the debris induced head loss and the core flow rate needs to be explained because the head loss induced by debris in actual condition may reduce the core inflow rate faster. To confirm the safety parameters, in this study, thermal-hydraulic response considering the core inlet blockage (CIB) by debris during LTCC process following a double-ended guillotine break of cold leg (CLB), one of hot leg (HLB) and one of intermediate leg (ILB) of the APR1400 were calculated, respectively. MARS-KS 1.3 code has been used. The CIB has been modeled by the closure of valves to the core in exponential manner with time to observe the behavior near the complete blockage. To understand the effect of core inlet blockage (CIB) during a long term core cooling (LTCC) phase following a loss-of-coolant accident (LOCA) in the light of in-vessel downstream effect (IDE) of Generic Safety Issue (GSI) 191, double-ended guillotine break of hot leg (HLB), one of cold leg (CLB) and one of intermediate leg (ILB) were calculated, respectively. And the important safety parameters such as the available driving head and the head loss due to debris were calculated using MARS-KS code and discussed in comparison with the WCAP method. As a result, a little delayed heatup behavior of the fuel cladding was found for all the cases, which due to the redistribution of flow within the core after blockage.

  11. Analysis of a Natural Circulation in the Reactor Coolant System Following a High Pressure Severe Accident at APR1400

    International Nuclear Information System (INIS)

    Kim, Han Chul; Cho, Yong Jin; Park, Jae Hong; Cho, Song Won

    2011-01-01

    Under a high temperature and pressure condition during a severe accident, hot leg pipes or steam generator tubes could fail due to creep rupture following natural circulation in the Reactor Coolant System (RCS) unless depressurization of the system is performed at a proper time. Natural circulation in the RCS can be a multi-dimensional circulation in the reactor vessel, a partial loop circulation of two-phase flow from the core up to steam generators (SGs), or circulation in the total loop. It can delay the reactor vessel failure time by removing heat from the reactor core. This natural phenomenon can be hardly simulated with a single flow path model for the hot spots of the RCS, since it cannot deal with the counter-current flow. Thus it may estimate accident progression faster than reality, which may cause troubles for optimized implementation of severe accident management strategies. An earlier damage in the RCS other than the reactor pressure vessel may make subsequent behaviors of hydrogen or fission products in the containment quite different from the single reactor vessel failure. Therefore, a RCS model which treats natural circulation is needed to evaluate the RCS response and the safety depressurization strategy in a best-estimate way. The aim of this study is to develop a detailed model which allows natural circulation between the reactor vessel and steam generators through hot legs, based on the existing APR1400 RCS model. The station blackout sequence was selected to be the representative high-pressure scenario. Sensitivity study on the effect of node configuration of the upper plenum and addition of cross flow paths from the upper plenum to the hot legs were carried out. This model is described herein and representative calculation results are presented

  12. Analysis of Post-LOCA Core Inlet Blockage to Evaluate In-vessel Downstream Effect in APR1400

    International Nuclear Information System (INIS)

    Bang, Young Seok

    2015-01-01

    The method was developed to have a conservatism to cover the uncertainty of analysis and the acceptance is judged by the representative bounding estimation. However, the important safety parameters such as the available driving head need to be confirmed by the plant specific calculation. Also an interaction between the debris induced head loss and the core flow rate needs to be explained because the head loss induced by debris in actual condition may reduce the core inflow rate faster. To confirm the safety parameters, in this study, thermal-hydraulic response considering the core inlet blockage (CIB) by debris during LTCC process following a double-ended guillotine break of cold leg (CLB), one of hot leg (HLB) and one of intermediate leg (ILB) of the APR1400 were calculated, respectively. MARS-KS 1.3 code has been used. The CIB has been modeled by the closure of valves to the core in exponential manner with time to observe the behavior near the complete blockage. To understand the effect of core inlet blockage (CIB) during a long term core cooling (LTCC) phase following a loss-of-coolant accident (LOCA) in the light of in-vessel downstream effect (IDE) of Generic Safety Issue (GSI) 191, double-ended guillotine break of hot leg (HLB), one of cold leg (CLB) and one of intermediate leg (ILB) were calculated, respectively. And the important safety parameters such as the available driving head and the head loss due to debris were calculated using MARS-KS code and discussed in comparison with the WCAP method. As a result, a little delayed heatup behavior of the fuel cladding was found for all the cases, which due to the redistribution of flow within the core after blockage

  13. Comparison of APR1400 safety between brake site and shin-Kori site Due to the difference in the climate conditions

    International Nuclear Information System (INIS)

    Yoon, Ho Joon; Lee, Jeong Ik; Lee, Jeong Ik

    2012-01-01

    Brake Nuclear Power Plant (BNPP) is now under the construction based on APR1400 designed by Korean Electric Power Corporation (KEPCO). APR1400 is a two loop pressurized water reactor, the nuclear steam supply system (NSSS) US designed for about put of 4,000 MWt, with a corresponding electrical output of approximately 1,390 MWe. The first APR1400 (SKN 3 and 4) constructed in Shin-Kori, Korea has been modified according to the surrounding environment of the United Arab Emirates. In this paper, authors would like to compare safety issues between B NPP and Skin due to the changes of surroundings, since the site characteristics are very different. For instance, the mean annual air temperature in the UAE is 28 .deg. C and the peak air temperature was recorded as 48.8 .deg. C. Sea temperatures are varying from 17. deg. C in January to 35. deg. C in August, while that of Korea is in 9-16. deg. C range. Hot climate of UAE and the malfunction of HVAC system can lead the increasing of the water temperature in safety injection system (SIS). The heated water in SIS may affect the safety margin of the peak cladding temperature (PCT). The change of PCT and response time according to design basis accident scenarios such as large break LOCA are analyzed in detail. To evaluate such effect, Mars code was utilized to evaluate assumed condition by KAIST and the analyses of the results were carried out by Khalifa Univ.

  14. A Computerized Procedure linked to Virtual Equipment

    International Nuclear Information System (INIS)

    Jung, Yeon Sub; Song, Tae Young

    2011-01-01

    Digital, information, and communication technologies have change human's behavior. This is because human has limitation to memorize and process information. Human has to access other information and real time information for important decisions. Those technologies are playing important roles. Nuclear power plants cannot be exception. Many accidents in nuclear power plants result from absent or incorrect information. The information for nuclear personnel is context sensitive. They don't have enough time to verify the context sensitive information. Therefore they skip the information, as resulting in incident. Nuclear personnel are usually carrying static paper procedures during local task performance. The procedure guides them steps to follow. There is, however, no dynamic and context sensitive information in the paper. The effect of the work is evaluated once while getting permission of the work. Afterward they are not informed. The static paper is generally simplified, so that it does not show detail of equipment being manipulated. Particularly novice workers feel difficult to understand the procedure due to lack of detail. Pictures of equipment inserted in the procedure are not enough for comprehension. A computerized procedure linked with virtual equipment is one of the best solutions to increase the detail of procedure. Virtual equipment, however, has still limitation not to provide real time information, because the virtual equipment is not synchronized with real plants

  15. A Study on the Coupled FEM-Analysis for Reactor Vessel Lower Head of APR1400 under the Severe Accident Scenario

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyonam; Namgung, Ihn [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    For the stabilization of the RPV the in-vessel retention strategy with external reactor vessel cooling (IVR-ERVC) is adopted in APR1400. Under this severe accident condition, a good understanding of the mechanical behavior of the reactor vessel lower head (RVLH) is necessary both for verification of structural integrity and for improving the design applying appropriate accident mitigation strategies. The purpose of this study is to develop the analysis method of the RVLH with thermo-mechanical analysis using FEM tool (ANSYS v.15) in case of core-melting severe accident condition, and then analyze the RVLH of APR1400 including creep behavior. The plastic strain can be the major cause of lower head failure on the reactor vessel, and the creep cannot be not negligible factor of the failure under the severe accident condition. In the study, we applied constant convection coefficient at assumed temperature on the outside wall of RPV and substitute creep data of SA-508. In addition, it was found that the steel ablation at the interface between corium and vessel steel is not only a thermal phenomenon in the METCOR experiments. Corrosion processes and the formation of eutectics lead to the erosion of the vessel steel at temperatures that are significantly lower than the melting temperature of steel. It called thermo-chemical attack of the corium (corrosion). Reduced wall thickness because of the thermo-chemical effect by corium increase the equivalent plastic strain, and decrease the minimum time to reach 20% creep strain.

  16. Failure Mode and Effect Analysis of the Application Software of the Safety-critical I and C System in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Koheun; Kim, Yong geul; Choi, Woong seok; Sohn, Se do [KEPCO Engineering and Construction, Daejeon (Korea, Republic of)

    2016-10-15

    In APR1400, the computer software hazard analysis is performed by hazard and operability analysis (HAZOP) method. Meanwhile, HAZOP has its limitation and cannot be considered better than fault tree analysis (FTA) or failure mode and effect (FMEA) analysis. HAZOP assumes that the system has been carefully studied, and all possible hazards, their effects or consequences and remedies are incorporated in the system. But incorporating every possible event in the design is impossible. In this light, this paper attempts to use FMEA method for evaluating the risk for safety-critical instrumentation and control (I and C) system software for NPP which is more practically than HAZOP. It is possible because the software failures are due to systematic faults that causing simultaneous failure in multiple division when the triggering event happens. This analysis is applied to safety-critical system of Shin-Hanul units 1 and 2 NPP, i.e., APR1400. Through SFMEA, the critical software failure modes and tasks that could result in CCF are identified and also evaluated to determine the associated risk level (e.g. high or intermediate or low) based on the failure effect. Biggest benefit from this analysis comparing with HAZOP is it can reveal the possible weak points and provide the guidance to the V and V team by helping to generate the test cases.

  17. Integrated System Validation Usability Questionnaire: Computerized Procedures

    International Nuclear Information System (INIS)

    Garcés, Ma. I.; Torralba, B.

    2015-01-01

    The Research and Development (R&D) project on “Theoretical and Methodological Approaches to Integrated System Validation of Control Rooms, 2014-2015”, in which the research activities described in this report are framed, has two main objectives: to develop the items for an usability methodology conceived as a part of the measurement framework for performance-based control room evaluation that the OECD Halden Reactor Project will test in the experiments planned for 2015; and the statistical analysis of the data generated in the experimental activities of the Halden Man-Machine Laboratory (HAMMLAB) facility, with previous usability questionnaires, in 2010 and 2011. In this report, the procedure designed to meet the first goal of the project is described, in particular, the process followed to identify the items related to operating procedures, both computer and paper-based, one of the elements to be included in the usability questionnaire. Three phases are performed, in the first one, the approaches developed by the United States Nuclear Regulatory Commission, NRC, are reviewed, the models used by the nuclear industry and their technical support organizations, mainly, the Electric Power Research Institute, EPRI, are analyzed, and scientist advances are also explored. In the remaining stages, general and specific guidelines for computerized and paper-based procedures are compared and criteria for the preliminary selection of the items that should be incorporated into the usability questionnaire are defined. This proposal will be reviewed and adapted by the Halden Reactor Project to the design of the specific experiments performed in HAMLAB.

  18. Some procedures for computerized ability testing

    NARCIS (Netherlands)

    van der Linden, Willem J.; Zwarts, Michel A.

    1989-01-01

    For computerized test systems to be operational, the use of item response theory is a prerequisite. As opposed to classical test theory, in item response models the abilities of the examinees and the properties of the items are parameterized separately. Hence, when measuring the abilities of

  19. Extension of Surveillance Test Interval of Safety Injection Pump for APR-1400 Reactors to Improve Reliability and Availability of the Pump

    Energy Technology Data Exchange (ETDEWEB)

    Osama, A. Rezk; Jung, J. C.; Lee, Yong-Kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    The safety features function to localize, control, mitigate, and terminate such incidents and to hold exposure levels below applicable limits. The safety injection system is comprised of four independent mechanical trains without any tie line among the injection paths and two electrical divisions. Each train has one active Safety Injection Pump (SIP) and one passive Safety Injection Tank (SIT) equipped with a Fluidic Device (FD), each train provides 50% of the minimum injection flow rate for breaks larger than the size of a direct vessel injection line. For breaks equal to or smaller than the size of a direct vessel injection line, each train has 100% of the required capacity. The low pressure injection pumps with common header installed in the conventional design are eliminated, and the functions for safety injection and shutdown cooling are separated. The arrangement of safety injection system for APR-1400 as shown in figure (1). The results obtained in this work show that STI extensions for the SIS feasible without any unacceptable increase in the plant total risk, STI extensions are acceptable for safety injection system to provide plant operational flexibility in the performance of both corrective and preventive maintenance for the safety injection system.

  20. Liquid entrainment and off-take at the top of the pressurizer in the case of the actuation of safety depressurization system of APR1400

    International Nuclear Information System (INIS)

    Kim, Chang Hyun; No, Hee Cheon

    2003-01-01

    In order to determine the bleed capacity of Safety Depressurization System (SDS) of Advanced Power Reactor 1400 (APR1400) in case of Total Loss of Feed Water (TLOFW), we performed an experimental study of liquid entrainment and liquid off-take from the swelled two-phase mixture surface in a vessel. A total of 208 experimental data on the entrainment and off-take are obtained using a test vessel with the height of 2.0m and the inner diameter of 0.3m having a top break with diameter of 0.05m. Two-phase mixture levels are measured by the ultrasonic sensor within ? .77% with respect to the visual level data. Droplet entrainments are measured and compared with the existing pool entrainment data. The empirical correlation for the onset of off-take is developed in terms of the Froude number (Fr g ) at the break and non-dimensional inception height (h b /d). This correlation shows agreement with the present experimental data within ? 5%. The present off-take quality data is in agreement with Schrock's off-take quality correlation with the r.m.s. error of 15.8%. In the present experiment, droplet entrainment E fg strongly depends upon jg * /h * and is proportional to the 7 th power of jg * /h * in the same way as the off-take data

  1. Development of a system for a linked analysis of RELAP5 and MAAP4 and its application for an analysis of LB-LOCA case of APR1400

    International Nuclear Information System (INIS)

    Park, Chang Hwan; Lee, Un Chul; Park, Goon Cherl; Suh, Kune Yull

    2004-01-01

    The RELAP5 (1995) and MAAP4 (1994) linked-analysis system was designed and illustrative calculation was performed. A large-break loss-of-coolant accident (LBLOCA) was taken as the reference case for the APR1400 (Advanced Power Reactor 1400MWe). For the early phase of this case, the calculational results of two codes have some deviations in water level depletion and hot assembly temperature. Ordinarily, it is considered that RELAP5 has enough accuracy in calculation of the thermal hydraulic behavior of typical PWR during design basis accidents. If the data set for the thermal hydraulic state of RELAP5 can be well-transferred to MAAP4 as an initial condition, the overall transients given by the linked analysis can get more reliability. In this study, the linked analysis system of RELAP5 and MAAP4 doesn't mean the mechanically integrated code structure. The objective of this study is to formulate the linked analysis system of RELAP5 and MAAP4, which should precede construction of mechanically integrated analyzer. Thus, the main scope of this work covers development of the methodology for data linkage and decision of the transfer timing

  2. Current Human Reliability Analysis Methods Applied to Computerized Procedures

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring

    2012-06-01

    Computerized procedures (CPs) are an emerging technology within nuclear power plant control rooms. While CPs have been implemented internationally in advanced control rooms, to date no US nuclear power plant has implemented CPs in its main control room (Fink et al., 2009). Yet, CPs are a reality of new plant builds and are an area of considerable interest to existing plants, which see advantages in terms of enhanced ease of use and easier records management by omitting the need for updating hardcopy procedures. The overall intent of this paper is to provide a characterization of human reliability analysis (HRA) issues for computerized procedures. It is beyond the scope of this document to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper serves as a review of current HRA as it may be used for the analysis and review of computerized procedures.

  3. Mental Workload and Situational Awareness Evaluation of APR1400 Engineered Safety Features- Component Control Activation Systems using Augmented Reality

    International Nuclear Information System (INIS)

    Murungi, Mwongeera; Jung, JaeCheon

    2016-01-01

    In the study, an Augmented Reality procedure guidance support system concept was designed and used as a tool for the measurement of mental workload and Situational awareness of an SRO (Senior Reactor Operator). The EOP was chosen as the scenario for testing because it is the one of the critical plant conditions that requires human intervention and it represents (one of the more) conservative approaches to the test scenarios that are possible. The system is expected to realize an improvement in the level of Situational Awareness and mental workload which have been demonstrated by previous studies to be directly linked with the system response to an emergency situation in the MCR. The planning and design of the project adhered to a Systems Engineering approach in order to provide an optimized framework for ensuring the successful implementation of the system design. Previous study and research into this topic has emphasized the importance of situational awareness in determining the human factor performance issues in the nuclear power plant Control Room operations. This paper broadly defined a technique that successfully used the operator’s mental workload (using NASATLX) and Situational Awareness (using SART) as quantifying measures to evaluate the performance of specific ESF-CCS functions based on human factors. These results show that an improvement of the SA/workload could lead to an improvement of the level of certainty that the emergency situation can be brought under control. It is expected that future development work in this area will yield an actualized Augmented Reality system that could incorporate MCR team control and possibly be implemented in the system validation of other I and C systems

  4. Mental Workload and Situational Awareness Evaluation of APR1400 Engineered Safety Features- Component Control Activation Systems using Augmented Reality

    Energy Technology Data Exchange (ETDEWEB)

    Murungi, Mwongeera; Jung, JaeCheon [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    In the study, an Augmented Reality procedure guidance support system concept was designed and used as a tool for the measurement of mental workload and Situational awareness of an SRO (Senior Reactor Operator). The EOP was chosen as the scenario for testing because it is the one of the critical plant conditions that requires human intervention and it represents (one of the more) conservative approaches to the test scenarios that are possible. The system is expected to realize an improvement in the level of Situational Awareness and mental workload which have been demonstrated by previous studies to be directly linked with the system response to an emergency situation in the MCR. The planning and design of the project adhered to a Systems Engineering approach in order to provide an optimized framework for ensuring the successful implementation of the system design. Previous study and research into this topic has emphasized the importance of situational awareness in determining the human factor performance issues in the nuclear power plant Control Room operations. This paper broadly defined a technique that successfully used the operator’s mental workload (using NASATLX) and Situational Awareness (using SART) as quantifying measures to evaluate the performance of specific ESF-CCS functions based on human factors. These results show that an improvement of the SA/workload could lead to an improvement of the level of certainty that the emergency situation can be brought under control. It is expected that future development work in this area will yield an actualized Augmented Reality system that could incorporate MCR team control and possibly be implemented in the system validation of other I and C systems.

  5. A Study on Large Display Panel Design for the Countermeasures against Team Errors within the Main Control Room of APR-1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sa Kil; Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The personal aspect of human errors has been mainly overcome by virtue of the education and training. However, in the system aspect, the education and training system needs to be reconsidered for more effective reduction of human errors affected from various systems hazards. Traditionally the education and training systems are mainly not focused on team skills such as communication, situational awareness, and coordination, etc. but individual knowledge, skill, and attitude. However, the team factor is one of the crucial issues to reduce the human errors in most industries. In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Team error is one of the typical organizational errors that may occur during performing operations in nuclear power plants. The large display panel is a representative feature of digitalized control room. As a group-view display, the large display panel provides plant overview to the operators. However, in terms of team performance and team errors, the large display panel is on a discussion board still because the large display panel was designed just a concept of passive display. In this study, we will propose revised large display panel which is integrated with several alternative interfaces against feasible team errors.

  6. A Study on Large Display Panel Design for the Countermeasures against Team Errors within the Main Control Room of APR-1400

    International Nuclear Information System (INIS)

    Kim, Sa Kil; Lee, Yong Hee

    2015-01-01

    The personal aspect of human errors has been mainly overcome by virtue of the education and training. However, in the system aspect, the education and training system needs to be reconsidered for more effective reduction of human errors affected from various systems hazards. Traditionally the education and training systems are mainly not focused on team skills such as communication, situational awareness, and coordination, etc. but individual knowledge, skill, and attitude. However, the team factor is one of the crucial issues to reduce the human errors in most industries. In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Team error is one of the typical organizational errors that may occur during performing operations in nuclear power plants. The large display panel is a representative feature of digitalized control room. As a group-view display, the large display panel provides plant overview to the operators. However, in terms of team performance and team errors, the large display panel is on a discussion board still because the large display panel was designed just a concept of passive display. In this study, we will propose revised large display panel which is integrated with several alternative interfaces against feasible team errors

  7. Procedures for Selecting Items for Computerized Adaptive Tests.

    Science.gov (United States)

    Kingsbury, G. Gage; Zara, Anthony R.

    1989-01-01

    Several classical approaches and alternative approaches to item selection for computerized adaptive testing (CAT) are reviewed and compared. The study also describes procedures for constrained CAT that may be added to classical item selection approaches to allow them to be used for applied testing. (TJH)

  8. Evaluation of the computerized procedures Manual II (COPMA II)

    International Nuclear Information System (INIS)

    Converse, S.A.

    1995-11-01

    The purpose of this study was to evaluate the effects of a computerized procedure system, the Computerized Procedure Manual II (COPMA-II), on the performance and mental workload of licensed reactor operators. To evaluate COPMA-II, eight teams of two operators were trained to operate a scaled pressurized water reactor facility (SPWRF) with traditional paper procedures and with COPMA-II. Following training, each team operated the SPWRF under normal operating conditions with both paper procedures and COPMA-II. The teams then performed one of two accident scenarios with paper procedures, but performed the remaining accident scenario with COPMA-II. Performance measures and subjective estimates of mental workload were recorded for each performance trial. The most important finding of the study was that the operators committed only half as many errors during the accident scenarios with COPMA-II as they committed with paper procedures. However, time to initiate a procedure was fastest for paper procedures for accident scenario trials. For performance under normal operating conditions, there was no difference in time to initiate or to complete a procedure, or in the number of errors committed with paper procedures and with COPMA-II. There were no consistent differences in the mental workload ratings operators recorded for trials with paper procedures and COPMA-II

  9. Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Park, Rae-Joon, E-mail: rjpark@kaeri.re.kr; Ha, Kwang-Soon; Rhee, Bo-Wook; Kim, Hwan Yeol

    2016-03-15

    Highlights: • Ex-vessel core catcher of PECS is installed in EU-APR1400. • CE-PECS has been conducted to test a cooling capability of the PECS. • Two phase flow in CE-PECS and PECS was analyzed using RELAP5/MOD3. • RELAP5 results are very similar to the CE-PECS data. • The super-step design is suitable for steam injection into the downcomer in PECS. - Abstract: The ex-vessel core catcher of the PECS (Passive Ex-vessel corium retaining and Cooling System) is installed to retain and cool down the corium in the reactor cavity of the EU (European Union)-APR (Advanced Power Reactor) 1400. A verification experiment on the cooling capability of the PECS has been conducted in the CE (Cooling Experiment)-PECS. Simulations of a two-phase natural circulation flow using the RELAP5/MOD3 computer code in the CE-PECS and PECS have been conducted to predict the two-phase flow characteristics, to determine the natural circulation mass flow rate in the cooling channel, and to evaluate the scaling in the experimental design of the CE-PECS. Particularly from a comparative study of the prototype PECS and the scaled test facility of the CE-PECS, the orifice loss coefficient in the CE-PECS was found to be 6 to maintain the coolant circulation mass flux, which is approximately 273.1 kg/m{sup 2} s. The RELAP5 results on the coolant circulation mass flow rate are very similar to the CE-PECS experimental results. An increase in the coolant injection temperature and the heat flux lead to an increase in the coolant circulation mass flow rate. In the base case simulation, a lot of vapor was injected into the downcomer, which leads to an instability of the two-phase natural circulation flow. A super-step design at a downcomer inlet is suitable to prevent vapor injection into the downcomer piping.

  10. Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

    International Nuclear Information System (INIS)

    Park, Rae-Joon; Ha, Kwang-Soon; Rhee, Bo-Wook; Kim, Hwan Yeol

    2016-01-01

    Highlights: • Ex-vessel core catcher of PECS is installed in EU-APR1400. • CE-PECS has been conducted to test a cooling capability of the PECS. • Two phase flow in CE-PECS and PECS was analyzed using RELAP5/MOD3. • RELAP5 results are very similar to the CE-PECS data. • The super-step design is suitable for steam injection into the downcomer in PECS. - Abstract: The ex-vessel core catcher of the PECS (Passive Ex-vessel corium retaining and Cooling System) is installed to retain and cool down the corium in the reactor cavity of the EU (European Union)-APR (Advanced Power Reactor) 1400. A verification experiment on the cooling capability of the PECS has been conducted in the CE (Cooling Experiment)-PECS. Simulations of a two-phase natural circulation flow using the RELAP5/MOD3 computer code in the CE-PECS and PECS have been conducted to predict the two-phase flow characteristics, to determine the natural circulation mass flow rate in the cooling channel, and to evaluate the scaling in the experimental design of the CE-PECS. Particularly from a comparative study of the prototype PECS and the scaled test facility of the CE-PECS, the orifice loss coefficient in the CE-PECS was found to be 6 to maintain the coolant circulation mass flux, which is approximately 273.1 kg/m"2 s. The RELAP5 results on the coolant circulation mass flow rate are very similar to the CE-PECS experimental results. An increase in the coolant injection temperature and the heat flux lead to an increase in the coolant circulation mass flow rate. In the base case simulation, a lot of vapor was injected into the downcomer, which leads to an instability of the two-phase natural circulation flow. A super-step design at a downcomer inlet is suitable to prevent vapor injection into the downcomer piping.

  11. Two-phase flow parameters of a downcomer boiling during a postulated reflood phase of APR1400; Parametres d'ecoulement diphasique dans un ebullition a la cuve en acier pendant un refroidissement d'un APRP de APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Byong-Jo, Yun; Dong-Jin, Euh; Chul-Hwa, Song [Korea Atomic Energy Research Inst. (Korea, Republic of)

    2009-07-01

    Downcomer boiling phenomena is one of the key issues for a postulated large-break LOCA (LBLOCA) in a conventional pressurized water reactor, because it can degrade the hydraulic head of the coolant in the downcomer and consequently affect the reflood flow rate for a core cooling. To investigate the thermal hydraulic behavior in the downcomer region of the APR1400, a test program for a downcomer boiling is being progressed for the reflood phase of a postulated LBLOCA. Test was performed in a one side heated rectangular test channel which was designed by adopting a full-pressure, full-height, and full-size downcomer-gap approach, but with the circumferential length was reduced 47.08-fold. The test consists of two steps: (I) for the global two-phase flow parameters and (II) for the local two-phase flow parameters. The step-I test has already been completed. In the present paper, the experimental results of the step-II test are introduced. (authors)

  12. Core on-line monitoring and computerized procedures systems

    International Nuclear Information System (INIS)

    Gangloff, W.C.

    1986-01-01

    The availability of operating nuclear power plants has been affected significantly by the difficulty people have in coping with the complexity of the plants and the operating procedures. Two ways to use modern computer technology to ease the burden of coping are discussed in this paper, an on-line core monitoring system with predictive capability and a computerized procedures system using live plant data. These systems reduce human errors by presenting information rather than simply data, using the computer to manipulate the data, but leaving the decisions to the plant operator

  13. Application of computerized procedure system for AP1000

    International Nuclear Information System (INIS)

    Wen Fang

    2012-01-01

    With the tendency of digitalisation in instrumentation and control system of nuclear power plants, AP1000, as well as other advanced PWRs, is provided with the technical basis for the application of CPS (computerized procedure system). This paper makes a brief introduction on CPS construction and function. CPS, as an advanced procedure system, does not only have the function of electronic indication for operation procedures, but also have the ability to monitor plant data, process the data and then present the status of the procedure steps to the reactor operator. In addition, advantages of CPS compared with paper-based procedures and comparison with digital operating system of one M310 plus advanced nuclear power plant are described. Moreover, based on current situation, this paper offers several suggestions on CPS localization for Sanmen AP1000 nuclear power project. Besides, the last part of this paper discusses problems we might meet during the process of CPS localization. (author)

  14. Study on computerized presentation of emergency procedures of a nuclear plant (step 2). The guidelines of the prototype of the computerized procedure presentation system

    International Nuclear Information System (INIS)

    Niwa, Yuji; Hollnagel, E.; Iwaki, Toshio.

    1995-01-01

    New methods of information presentation and interface design are changing the working conditions in the modern Nuclear Power Plant (NPP) control room. One area receiving considerable attention is that of Emergency Operating Procedures (EOPs), which plays an essential role in NPPs. Conventionally procedures are presented in a hard copy form. However developments in information technology have offered new opportunities for the computerization of such procedures. Consideration for the first stage of computerization should be focused upon the presentation of procedures. The specification of the computerized presentation of procedures is discussed with respect to the issues which were central to the project: navigation through procedures; formatting and presentation of procedures; and process monitoring. Issues that would be included in more advanced systems, such as help and explanation facilities features, and process linking, are also discussed. This paper deals with the specific design guidelines that were implemented for the computerization of procedure presentation. Issues of principal concern that were identified from this experience are highlighted, such as the relationship between procedure presentation and format; the registration of progress through a procedure; compensation for the limitations of computer displays versus printed documents; and the way in which the added capabilities of computerized presentation can be generally utilized in the operators' working environment. (author)

  15. A production system for computerized emergency procedures tracking

    International Nuclear Information System (INIS)

    Petrick, W.; Ng, K.; Stuart, C.; Cain, D.

    1988-01-01

    This paper describes a methodology used to implement a computerized Emergency Operating Procedures (EOP) tracking system based on artificial intelligence (AI) technologies. In AI parlance, the system is a production system in which the knowledge representation is a set of productions (IF-THEN rules) which are interpreted by an inference engine or rule interpreter. The inference engine looks for pattern matches in the rule premises which lead to a conclusion. This inferred conclusion is subsequently used in further pattern matches. By separating the knowledge representation from the inference engine, the system can readily accommodate changes to the written procedures. The system is written in the C language and is co-resident on the same computer as the Safety Parameter Display System (SPDS). The plant EOPs have been written in about 250 rules which are evaluated in less than one second using about 10-20% of the CPU. The conclusions are available to multiple users within seconds after a parameter value changes. The benefits achieved with this production rule system include compatibility with the written procedures used as the knowledge source, compatibility with control room instrumentation, compatibility with the SPDS, realtime performance, and efficient computer usage

  16. Aiming for a fully integrated computerized procedure system

    International Nuclear Information System (INIS)

    Marron, J. E.

    2006-01-01

    A fully integrated Computerized Procedure System must provide, at a minimum, a) Specification: access to design basis procedures, b) Monitoring: incorporation of real-time plant status, c) Advise: highlighting likely decision paths, and d) Reporting: logging conditions and actions taken. The CPS plays a critical role in overcoming the human factors that lead to accidents. At the same time it can be an essential tool in providing the information and automation to augment what humans do best, identify patterns and make associative leaps in the presence of ambiguous data. Timeliner and TaskGuide are examples of CPS that have evolved from projects in the aerospace industry. They illustrate certain common characteristics of a CPS, namely the knowledge base, user interface, and traceability features. The complexity and number of procedures for a current nuclear project has led to the development of two tools, the Power Generation Control System (PGCS) and the Online Procedure System (OLPS). Together, these systems address the knowledge-base and user interface aspects of a CPS and go a long way in addressing other areas. PGCS and OLPS contain full configuration management capabilities for procedures and the operating recipe. They include administrative functions for online and offline management of documents and data. Some lessons learned from this pair of programs developed by Invensys is the need for more integrated recording mechanisms. The future of CPS is likely to see higher integration of the document access, system status, decision support and logging capabilities. The CPS may evolve into the standard operational interface. Internet technologies that are common-place today have made the possibility of the Active Document a reality. The OPC Foundation is pursuing standards that may accelerate such developments. (authors)

  17. A computerized system for improved management and execution of plant procedures

    International Nuclear Information System (INIS)

    Lipner, M.H.; Orendi, R.G.; Impink, A.J.; Mundy, R.A.

    1987-01-01

    The authors have shown how the deficiencies reported in this paper can be resolved by using the Computerized Procedures System. The Westinghouse Computerized Procedures System solves many of the human performance problems associated with procedures. It has been designed to assist plant operators in executing procedures more efficiently and cost effectively. The system brings all of the necessary information to one location for easy and continuous assessment of plant conditions and permits the operator to concentrate on the big picture

  18. Experimental studies of computerized procedures and team size in nuclear power plant operations

    International Nuclear Information System (INIS)

    Huang, F.-H.; Hwang, S.-L.

    2009-01-01

    The operation of a nuclear power plant is so complex that it requires teamwork. To support team performance, a system need to provide all team members integrated information displays as well as decision aids (e.g., computerized procedures). Two experiments were conducted to investigate the effects of computerized procedures and team size on operating performance. Forty-five participants were involved in the experiments. Each participant executed decision and action tasks to deal with alarm signals, while detecting occasional system errors in the interface. Results showed that effects of computerized procedures were significant on various performance indicators, such as operation time, operation errors, and learning effect, and that two operators would be a satisfactory size in the teamwork system providing computerized procedures

  19. A toolkit for computerized operating procedure of complex industrial systems with IVI-COM technology

    International Nuclear Information System (INIS)

    Zhou Yangping; Dong Yujie; Huang Xiaojing; Ye Jingliang; Yoshikawa, Hidekazu

    2013-01-01

    A human interface toolkit is proposed to help the user develop computerized operating procedure of complex industrial system such as Nuclear Power Plants (NPPs). Coupled with a friendly graphical interface, this integrated tool includes a database, a procedure editor and a procedure executor. A three layer hierarchy is adopted to express the complexity of operating procedure, which includes mission, process and node. There are 10 kinds of node: entrance, exit, hint, manual input, detector, actuator, data treatment, branch, judgment and plug-in. The computerized operating procedure will sense and actuate the actual industrial systems with the interface based on IVI-COM (Interchangeable Virtual Instrumentation-Component Object Model) technology. A prototype system of this human interface toolkit has been applied to develop a simple computerized operating procedure for a simulated NPP. (author)

  20. APR1400 Containment Simulation with CONTAIN code

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Moon Kyu; Chung, Bub Dong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-05-15

    The more realistic containment pressure variation predicted by the CONTAIN code through the coupled analysis during a large break loss of coolant accident in the nuclear power plant is expected to provide more accurate prediction for the plant behavior than a standalone MARS-KS calculation. The input deck has been generated based on the already available ARP- 1400 input for CONTEMPT code. Similarly to the CONTEMPT input deck, a simple two-cell model was adopted to model the containment behavior, one cell for the containment inner volume and another cell for the environment condition. The developed input for the CONTAIN code is to be eventually applied for the coupled code calculation of MARS-KS/CONTAIN

  1. APR1400 Containment Simulation with CONTAIN code

    International Nuclear Information System (INIS)

    Hwang, Moon Kyu; Chung, Bub Dong

    2010-01-01

    The more realistic containment pressure variation predicted by the CONTAIN code through the coupled analysis during a large break loss of coolant accident in the nuclear power plant is expected to provide more accurate prediction for the plant behavior than a standalone MARS-KS calculation. The input deck has been generated based on the already available ARP- 1400 input for CONTEMPT code. Similarly to the CONTEMPT input deck, a simple two-cell model was adopted to model the containment behavior, one cell for the containment inner volume and another cell for the environment condition. The developed input for the CONTAIN code is to be eventually applied for the coupled code calculation of MARS-KS/CONTAIN

  2. CONSIDERATIONS FOR THE TREATMENT OF COMPUTERIZED PROCEDURES IN HUMAN RELIABILITY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; David I. Gertman

    2012-07-01

    Computerized procedures (CPs) are an emerging technology within nuclear power plant control rooms. While CPs have been implemented internationally in advanced control rooms, to date no US nuclear power plant has implemented CPs in its main control room. Yet, CPs are a reality of new plant builds and are an area of considerable interest to existing plants, which see advantages in terms of easier records management by omitting the need for updating hardcopy procedures. The overall intent of this paper is to provide a characterization of human reliability analysis (HRA) issues for computerized procedures. It is beyond the scope of this document to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper serves as a review of current HRA as it may be used for the analysis and review of computerized procedures.

  3. HUMAN RELIABILITY ANALYSIS FOR COMPUTERIZED PROCEDURES, PART TWO: APPLICABILITY OF CURRENT METHODS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; David I. Gertman

    2012-10-01

    Computerized procedures (CPs) are an emerging technology within nuclear power plant control rooms. While CPs have been implemented internationally in advanced control rooms, to date no U.S. nuclear power plant has implemented CPs in its main control room. Yet, CPs are a reality of new plant builds and are an area of considerable interest to existing plants, which see advantages in terms of easier records management by omitting the need for updating hardcopy procedures. The overall intent of this paper is to provide a characterization of human reliability analysis (HRA) issues for computerized procedures. It is beyond the scope of this document to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper serves as a review of current HRA as it may be used for the analysis and review of computerized procedures.

  4. An ergonomics study of computerized emergency operating procedures: Presentation style, task complexity, and training level

    International Nuclear Information System (INIS)

    Xu Song; Song Fei; Li Zhizhong; Zhao Qianyi; Luo Wei; He Xuhong; Salvendy, Gavriel

    2008-01-01

    Emergency operating procedures (EOPs) are widely used in nuclear power plants (NPPs). With the development of information technology, computerized EOPs are taking the place of paper-based ones. Unlike paper-based EOPs, the industrial practice of computerized EOPs is still quite limited. Ergonomics issues of computerized EOPs have not been studied adequately. This study focuses on the effects of EOP presentation style, task complexity, and training level on the performance of the operators in the execution of computerized EOPs. One simulated computerized EOP system was developed to present two EOPs, each with different task complexity levels, by two presentation styles (Style A: one- and two-dimensional flowcharts combination; Style B: two-dimensional flowchart and success logic tree combination). Forty subjects participated in the experiment of EOP execution using the simulated system. Statistical analysis of the experimental results indicates that: (1) complexity, presentation style, and training level all can significantly influence the error rate. High-complexity tasks and lack of sufficient training may lead to a higher error rate. Style B caused a significantly higher error rate than style A did in the skilled phase. So the designers of computerized procedures should take the presentation styles of EOPs into account. (2) Task complexity and training level can significantly influence operation time. No significant difference was found in operation time between the two presentation styles. (3) Training level can also significantly influence the subjective workload of EOPs operations. This implies that adequate training is very important for the performance of computerized EOPs even if emergency responses with computerized EOPs are much more simple and easy than that with paper-based EOPs

  5. An ergonomics study of computerized emergency operating procedures: Presentation style, task complexity, and training level

    Energy Technology Data Exchange (ETDEWEB)

    Xu Song; Song Fei [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China); Li Zhizhong [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China)], E-mail: zzli@tsinghua.edu.cn; Zhao Qianyi; Luo Wei [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China); He Xuhong [Scanpower Risk Management China Inc., Towercrest International Plaza, No. 3 Maizidian West Road, Chaoyang District, Beijing 100016 (China); Salvendy, Gavriel [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China)

    2008-10-15

    Emergency operating procedures (EOPs) are widely used in nuclear power plants (NPPs). With the development of information technology, computerized EOPs are taking the place of paper-based ones. Unlike paper-based EOPs, the industrial practice of computerized EOPs is still quite limited. Ergonomics issues of computerized EOPs have not been studied adequately. This study focuses on the effects of EOP presentation style, task complexity, and training level on the performance of the operators in the execution of computerized EOPs. One simulated computerized EOP system was developed to present two EOPs, each with different task complexity levels, by two presentation styles (Style A: one- and two-dimensional flowcharts combination; Style B: two-dimensional flowchart and success logic tree combination). Forty subjects participated in the experiment of EOP execution using the simulated system. Statistical analysis of the experimental results indicates that: (1) complexity, presentation style, and training level all can significantly influence the error rate. High-complexity tasks and lack of sufficient training may lead to a higher error rate. Style B caused a significantly higher error rate than style A did in the skilled phase. So the designers of computerized procedures should take the presentation styles of EOPs into account. (2) Task complexity and training level can significantly influence operation time. No significant difference was found in operation time between the two presentation styles. (3) Training level can also significantly influence the subjective workload of EOPs operations. This implies that adequate training is very important for the performance of computerized EOPs even if emergency responses with computerized EOPs are much more simple and easy than that with paper-based EOPs.

  6. State Token Petri Net modeling method for formal verification of computerized procedure including operator's interruptions of procedure execution flow

    International Nuclear Information System (INIS)

    Kim, Yun Goo; Seong, Poong Hyun

    2012-01-01

    The Computerized Procedure System (CPS) is one of the primary operating support systems in the digital Main Control Room. The CPS displays procedure on the computer screen in the form of a flow chart, and displays plant operating information along with procedure instructions. It also supports operator decision making by providing a system decision. A procedure flow should be correct and reliable, as an error would lead to operator misjudgement and inadequate control. In this paper we present a modeling for the CPS that enables formal verification based on Petri nets. The proposed State Token Petri Nets (STPN) also support modeling of a procedure flow that has various interruptions by the operator, according to the plant condition. STPN modeling is compared with Coloured Petri net when they are applied to Emergency Operating Computerized Procedure. A converting program for Computerized Procedure (CP) to STPN has been also developed. The formal verification and validation methods of CP with STPN increase the safety of a nuclear power plant and provide digital quality assurance means that are needed when the role and function of the CPS is increasing.

  7. A Procedure for the Computerized Analysis of Cleft Palate Speech Transcription

    Science.gov (United States)

    Fitzsimons, David A.; Jones, David L.; Barton, Belinda; North, Kathryn N.

    2012-01-01

    The phonetic symbols used by speech-language pathologists to transcribe speech contain underlying hexadecimal values used by computers to correctly display and process transcription data. This study aimed to develop a procedure to utilise these values as the basis for subsequent computerized analysis of cleft palate speech. A computer keyboard…

  8. A Comparison of Procedures for Content-Sensitive Item Selection in Computerized Adaptive Tests.

    Science.gov (United States)

    Kingsbury, G. Gage; Zara, Anthony R.

    1991-01-01

    This simulation investigated two procedures that reduce differences between paper-and-pencil testing and computerized adaptive testing (CAT) by making CAT content sensitive. Results indicate that the price in terms of additional test items of using constrained CAT for content balancing is much smaller than that of using testlets. (SLD)

  9. Tight integration of computerized procedures with plant information at the South Texas Project

    International Nuclear Information System (INIS)

    Brtis, J.S.; Green, T.

    1996-01-01

    This paper describes a unique undertaking that is underway at Houston Lighting and Power's South Texas Project (STP). The paper presents an information upgrade project that uses expert system technologies to computerize design change procedures and to tightly integrate the resulting on-line, interactive procedures with the on-line information that design change activities use and generate. This effort will show how procedure computerization can leverage the large investments in plant data. The expected benefits include reduced costs and improved quality of design change work, plus a significant reduction in the burden of configuration management that comes from design changes. Both process computerization and the integration of process with data are being implemented at STP. This work is part of a major migration of information from a mainframe to a LAN platform. This paper will be of greatest interest to those involved in: (1) configuration management, (2) coordinating information to support design change procedures, (3) plant information management, and (4) business process reengineering

  10. Influence of step complexity and presentation style on step performance of computerized emergency operating procedures

    Energy Technology Data Exchange (ETDEWEB)

    Xu Song [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China); Li Zhizhong [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China)], E-mail: zzli@tsinghua.edu.cn; Song Fei; Luo Wei; Zhao Qianyi; Salvendy, Gavriel [Department of Industrial Engineering, Tsinghua University, Beijing 100084 (China)

    2009-02-15

    With the development of information technology, computerized emergency operating procedures (EOPs) are taking the place of paper-based ones. However, ergonomics issues of computerized EOPs have not been studied adequately since the industrial practice is quite limited yet. This study examined the influence of step complexity and presentation style of EOPs on step performance. A simulated computerized EOP system was developed in two presentation styles: Style A: one- and two-dimensional flowcharts combination; Style B: two-dimensional flowchart and success logic tree combination. Step complexity was quantified by a complexity measure model based on an entropy concept. Forty subjects participated in the experiment of EOP execution using the simulated system. The results of data analysis on the experiment data indicate that step complexity and presentation style could significantly influence step performance (both step error rate and operation time). Regression models were also developed. The regression analysis results imply that operation time of a step could be well predicted by step complexity while step error rate could only partly predicted by it. The result of a questionnaire investigation implies that step error rate was influenced not only by the operation task itself but also by other human factors. These findings may be useful for the design and assessment of computerized EOPs.

  11. Feasibility study of computerized presentation of procedures of a nuclear plant

    International Nuclear Information System (INIS)

    Takagawa, Kenichi; Niwa, Yuji; Urakami, Masahiro

    2010-01-01

    Introduction of a digital instrumentation control system is in progress in recent nuclear power plants, and an application of Computer Based Procedures (CBP) is being considered. The Institute of Nuclear Safety System, Incorporated has developed a system for a Computerized Presentation of Procedures (CPP) which corresponds to CBP. By fiscal year 2002, all items in the emergency operation procedures of a model plant were made displayable on the CPP. In 2003, the CPP instead of the paper based procedures was used for trial by the operators of a nuclear power plant in an actual training simulator, and feasibility of its practical application was evaluated. Based on the result, we considered subjects which should be taken into account in the future. As a result, improvements of CPP and its navigation system, etc. to enable operations with multi-procedures in parallel were extracted as primary subjects for introduction of CBP in the future as well as practical application of CPP. (author)

  12. Development of a testing methodology for computerized procedure system based on JUnit framework and MFM

    International Nuclear Information System (INIS)

    Qin, Wei

    2004-02-01

    Paper Based Procedure (PBP) and Computerized Procedure System (CPS) are studied to demonstrate that it is necessary to develop CPS in Nuclear Power Plant (NPP) Instrumentation and Control (I and C) system. Computerized procedure system is actually a software system. All the desired and undesired properties of a software system can be described and evaluated as software qualities. Generally, software qualities can be categorized into product quality and process quality. In order to achieve product quality, the process quality of a software system should also be considered and achieved. Characteristics of CPS will be described to analyse the product and process of an example CPS: ImPRO. At the same time, several main product and process issues will be analysed from Verification and Validation (V and V) point of view. It is concluded and suggested that V and V activities can also be regarded as a software development process, this point of view then is applied to the V and V activities of ImPRO as a systematic approach of testing of ImPRO. To support and realize this approach, suitable testing technologies and testing strategies are suggested based on JUnit framework and Multi-level Flow Modeling (MFM)

  13. REVIEW Of COMPUTERIZED PROCEDURE GUIDELINES FOR NUCLEAR POWER PLANT CONTROL ROOMS

    Energy Technology Data Exchange (ETDEWEB)

    David I Gertman; Katya Le Blanc; Ronald L Boring

    2011-09-01

    Computerized procedures (CPs) are recognized as an emerging alternative to paper-based procedures for supporting control room operators in nuclear power plants undergoing life extension and in the concept of operations for advanced reactor designs. CPs potentially reduce operator workload, yield increases in efficiency, and provide for greater resilience. Yet, CPs may also adversely impact human and plant performance if not designed and implemented properly. Therefore, it is important to ensure that existing guidance is sufficient to provide for proper implementation and monitoring of CPs. In this paper, human performance issues were identified based on a review of the behavioral science literature, research on computerized procedures in nuclear and other industries, and a review of industry experience with CPs. The review of human performance issues led to the identification of a number of technical gaps in available guidance sources. To address some of the gaps, we developed 13 supplemental guidelines to support design and safety. This paper presents these guidelines and the case for further research.

  14. Analysis of risk in computerized tomography and other diagnostic radiology procedures

    International Nuclear Information System (INIS)

    Mossman, K.L.

    1982-01-01

    Medical practice entails continuous risks to the patient taken in good faith by the physician for the benefit of the patient. Risk of radiation induced cancer death approximates 10(-4) per cGy (rad). Assuming an average whole body dose of 0.1 cGy for many diagnostic X-ray procedures, the probability of radiation-induced cancer death is about 10(-5). The purpose of this paper is to compare the risks of common diagnostic X-ray procedures including computerized tomography (CT) with risks of smoking or automobile travel. Such comparisons should be constructive in putting radiation in perspective and facilitating explanation of risk/benefit to patients

  15. Development of a computerized procedure system on the basis of formalized action and check

    International Nuclear Information System (INIS)

    Jung, Y. S.; Shin, Y. C.; Jung, K. H.; Sung, C. H.

    1999-01-01

    A computerized procedure system was developed on the basis of formalized action and check. The actions and checks are rendered into two dimensional flowchart with foldable, dynamic, and interactive functions. The action and check are evaluated by computer automatically, and can be overridden by operator if necessary. Detail of each action and check is described in the logic tree with several boolean instruction set and n out m of mathematical operator. Computer supports operators to execute the boolean instruction providing relevant process parameters and control devices. In spite of all these computer support, its inner logic is simple and transparent to operators to keep them in the control loop. The boolean instruction can have 3 states. And n out m operator is defined on the 3 states. The definition minimizes not only number of context switching in procedure execution, but also enables evaluation of the action and check. The process parameters are presented in both text label and graphical symbol to improve readability. Moreover, new mechanism to access any part of a procedure is devised while keeping the main stream of procedure execution

  16. Assessing mental workload and situation awareness in the evaluation of computerized procedures in the main control room

    International Nuclear Information System (INIS)

    Yang, Chih-Wei; Yang, Li-Chen; Cheng, Tsung-Chieh; Jou, Yung-Tsan; Chiou, Shian-Wei

    2012-01-01

    Highlights: ► This study investigates procedure types’ effects on operators’ performance. ► The computer-based procedure is suggested to be implemented in the main control room. ► The computer-based procedure brings lowest mental workload. ► And it also generates fewer error of omission, and the highest situation awareness. ► The shift supervisor has the highest workload and the lowest situation awareness. - Abstract: Computerized procedure (CP) system has been developed in nuclear power plant (NPP) instrumentation and control (I and C) system. The system may include normal operating procedures (OPs), abnormal operating procedures (AOPs), alarm response procedures (ARPs), surveillance test procedures (STPs) and/or emergency operating procedures (EOPs). While there are many ways to evaluate computerized procedures design, the user's mental workload and situation awareness (SA) are particularly important considerations in the supervisory control of safety-critical systems. Users’ mental workload and situation awareness may be influenced by human factor issues relating to computerized procedures, e.g., level of automation, dealing with (partially) unavailable I and C, switching to back-up system (e.g., paper-based procedures). Some of the positive impacts of CPs on operator performance include the following: tasks can be performed more quickly; overall workload can be reduced; cognitive workload can be minimized; fewer errors may be made in transitioning through or between procedures. However, various challenges have also been identified with CP systems. These should be addressed in the design and implementation of CPs where they are applicable. For example, narrower “field of view” provided by CP systems than with paper-based procedures could reduce crew communications and crewmember awareness of the status and progress through the procedure. Based on a human factors experiment in which each participant monitored and controlled multiple simulated

  17. Assessing mental workload and situation awareness in the evaluation of computerized procedures in the main control room

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chih-Wei, E-mail: yangcw@iner.gov.tw [Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Yang, Li-Chen; Cheng, Tsung-Chieh [Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Jou, Yung-Tsan; Chiou, Shian-Wei [Department of Industrial Engineering, Chung-Yuan Christian University, 200, Chung Pei Rd., Chung-Li 32023, Taiwan (China)

    2012-09-15

    Highlights: Black-Right-Pointing-Pointer This study investigates procedure types' effects on operators' performance. Black-Right-Pointing-Pointer The computer-based procedure is suggested to be implemented in the main control room. Black-Right-Pointing-Pointer The computer-based procedure brings lowest mental workload. Black-Right-Pointing-Pointer And it also generates fewer error of omission, and the highest situation awareness. Black-Right-Pointing-Pointer The shift supervisor has the highest workload and the lowest situation awareness. - Abstract: Computerized procedure (CP) system has been developed in nuclear power plant (NPP) instrumentation and control (I and C) system. The system may include normal operating procedures (OPs), abnormal operating procedures (AOPs), alarm response procedures (ARPs), surveillance test procedures (STPs) and/or emergency operating procedures (EOPs). While there are many ways to evaluate computerized procedures design, the user's mental workload and situation awareness (SA) are particularly important considerations in the supervisory control of safety-critical systems. Users' mental workload and situation awareness may be influenced by human factor issues relating to computerized procedures, e.g., level of automation, dealing with (partially) unavailable I and C, switching to back-up system (e.g., paper-based procedures). Some of the positive impacts of CPs on operator performance include the following: tasks can be performed more quickly; overall workload can be reduced; cognitive workload can be minimized; fewer errors may be made in transitioning through or between procedures. However, various challenges have also been identified with CP systems. These should be addressed in the design and implementation of CPs where they are applicable. For example, narrower 'field of view' provided by CP systems than with paper-based procedures could reduce crew communications and crewmember awareness of the

  18. Comparison of the effect of paper and computerized procedures on operator error rate and speed of performance

    International Nuclear Information System (INIS)

    Converse, S.A.; Perez, P.B.; Meyer, S.; Crabtree, W.

    1994-01-01

    The Computerized Procedures Manual (COPMA-II) is an advanced procedure manual that can be used to select and execute procedures, to monitor the state of plant parameters, and to help operators track their progress through plant procedures. COPMA-II was evaluated in a study that compared the speed and accuracy of operators' performance when they performed with COPMA-II and traditional paper procedures. Sixteen licensed reactor operators worked in teams of two to operate the Scales Pressurized Water Reactor Facility at North Carolina State University. Each team performed one change of power with each type of procedure to simulate performance under normal operating conditions. Teams then performed one accident scenario with COPMA-II and one with paper procedures. Error rates, performance times, and subjective estimates of workload were collected, and were evaluated for each combination of procedure type and scenario type. For the change of power task, accuracy and response time were not different for COPMA-II and paper procedures. Operators did initiate responses to both accident scenarios fastest with paper procedures. However, procedure type did not moderate response completion time for either accident scenario. For accuracy, performance with paper procedures resulted in twice as many errors as did performance with COPMA-II. Subjective measures of mental workload for the accident scenarios were not affected by procedure type

  19. Interface of RETRAN/MASTER Code System for APR1400

    International Nuclear Information System (INIS)

    Ku, Keuk Jong; Kang, Sang Hee; Kim, Han Gon

    2008-01-01

    MASTER(Multi-purpose Analyzer for Static and Transient Effects of Reactors), which was developed by KAERI, is a nuclear analysis and design code which can simulate the pressurized water reactor core or boiling water reactor core in 3-dimensional geometry. RETRAN is a best-estimate code for transient analysis of Non-LOCA. RETRAN code generates neutron number density in core using point kinetics model which includes feedback reactivities and converts the neutron number density into reactor power. It is conventional that RETRAN code for power generation is roughly to extrapolate feedback reactivities which are provided by MASTER code only one time before transient analysis. The purpose of this paper is to interface RETRAN code with MASTER code by real-time processing and to supply adequate feedback reactivities to RETRAN code. So, we develop interface code called MATRAN for real-time feedback reactivity processing. And for the application of MATRAN code, we compare the results of real-time MATRAN code with those of conventional RETRAN/MASTER code

  20. Structural Analysis of Advanced Refueling Machine of APR1400

    International Nuclear Information System (INIS)

    Cho, J. R.; Kim, Y. H.; Park, B. T.; Park, J. B.; Jung, J. H.

    2007-01-01

    The Refueling Machine (RM) consists of two structural parts of bridge and trolley. The bridge structure is approximately 8.5 m long and 5 m wide and is primarily composed of two deep wide flange sections spanning the rector area at the operating level. The trolley is mounted on wheels that roll on the rails of the bridge. Vertical movements of trolley and bridge are restricted by guide rollers. In this paper, dynamic and structural analyses based on the earthquake spectrum are carried out to verify the structural integrity of advanced refueling machine. It is done by 3-dimensional finite element analysis using ANSYS software

  1. A study on a systematic approach of verification and validation of a computerized procedure system: ImPRO

    International Nuclear Information System (INIS)

    Qin, Wei; Seong, Poong Hyun

    2003-01-01

    Paper Based Procedure (PBP) and Computerized Procedure System (CPS) are studied to demonstrate that it is necessary to develop CPS in NPP I and C system. Computerized procedure system is actually a software system. All the desired and undesired properties of a software system can be described and evaluated as software qualities. Generally, software qualities can be categorized into product quality and process quality. In order to achieve product quality, the process quality of a software system should also be considered and achieved. Characteristics of CPS will be described to analyse the product and process of an example CPS: ImPRO. At the same time, several main product and process issues will be analysed from Verification and Validation (V and V) point of view. It is concluded and suggested that V and V activities can also be regarded as software development process, this point of view then is applied to the V and V activities of ImPRO as a systematic approach of V and V of ImPRO. To support and realize this approach, suitable testing technologies and testing strategies are suggested

  2. Computerized operating procedures for shearing and dissolution of segments from LWBR [Light Water Breeder Reactor] fuel rods

    International Nuclear Information System (INIS)

    Osudar, J.; Deeken, P.G.; Graczyk, D.G.; Fagan, J.E.; Martino, F.J.; Parks, J.E.; Levitz, N.M.; Kessie, R.W.; Leddin, J.M.

    1987-05-01

    This report presents two detailed computerized operating procedures developed to assist and control the shearing and dissolution of irradiated fuel rods. The procedures were employed in the destructive analysis of end-of-life fuel rods from the Light Water Breeder Reactor (LWBR) that was designed by the Westinghouse Electric Corporation Bettis Atomic Power Laboratory. Seventeen entire fuel rods from the end-of-life core of the LWBR were sheared into 169 precisely characterized segments, and more than 150 of these segments were dissolved during execution of the LWBR Proof-of-Breeding (LWBR-POB) Analytical Support Project at Argonne National Laboratory. The procedures illustrate our approaches to process monitoring, data reduction, and quality assurance during the LWBR-POB work

  3. Procedure for extraction of disparate data from maps into computerized data bases

    Science.gov (United States)

    Junkin, B. G.

    1979-01-01

    A procedure is presented for extracting disparate sources of data from geographic maps and for the conversion of these data into a suitable format for processing on a computer-oriented information system. Several graphic digitizing considerations are included and related to the NASA Earth Resources Laboratory's Digitizer System. Current operating procedures for the Digitizer System are given in a simplified and logical manner. The report serves as a guide to those organizations interested in converting map-based data by using a comparable map digitizing system.

  4. Computerized tomography

    International Nuclear Information System (INIS)

    1980-01-01

    Improvements in the design of computerized tomographic X-ray equipment are described which lead to improvements in the mechanical properties, speed and size of scanning areas. The method envisages the body being scanned as a two-dimensional matrix of elements arising from a plurality of concentric rings. The concentric centre need not coincide with the axis of rotation. The procedures for rotation of the X-ray beam and detectors around the patient and for translating the measured information into attenuation coefficients for each matrix element of the body are described in detail. Explicit derivations are given for the mathematical formulae used. (U.K.)

  5. Computerized tomography

    International Nuclear Information System (INIS)

    Rubashov, I.B.

    1985-01-01

    Operating principle is described for the devices of computerized tomography used in medicine for diagnosis of brain diseases. Computerized tomography is considered as a part of computerized diagnosis, as a part of information science. It is shown that computerized tomography is a real existed field of investigations in medicine and industrial production

  6. X-ray computerized tomography based on the method of reciprocal projection with filtration by double differentiation. Procedure and information peculiarities

    International Nuclear Information System (INIS)

    Vajnberg, Eh.I.; Kazak, I.A.; Fajngojz, M.L.

    1985-01-01

    The results of experimental evaluation of procedure and information peculiarities of the method of reciprocal projection with filtration of projections by double differentiation (RPFDD) for the monitoring of industrial products are generalized. Succession of stages n the RPFDD method permits to separately optimize reconstruction of high-frequeny and low-frequency tomogram structure which sharply reduces the acuteness of contradictions of conventional scheme between the required increase of accuracy and intolerable growth of computerized charges. High accuracy of evaluation of the linear attenuation factor of low-frequency structures in a wide range of densities at the last stage of RPFDD scheme is attained despite the non-conventionally small range of values at earlier stages of computerized processing

  7. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Guide to data processing and revision: Part 2, Human error probability data entry and revision procedures

    International Nuclear Information System (INIS)

    Gilmore, W.E.; Gertman, D.I.; Gilbert, B.G.; Reece, W.J.

    1988-11-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability (HEP) and hardware component failure data (HCFD). The NUCLARR system software resides on an IBM (or compatible) personal micro-computer. Users can perform data base searches to furnish HEP estimates and HCFD rates. In this manner, the NUCLARR system can be used to support a variety of risk assessment activities. This volume, Volume 3 of a 5-volume series, presents the procedures used to process HEP and HCFD for entry in NUCLARR and describes how to modify the existing NUCLARR taxonomy in order to add either equipment types or action verbs. Volume 3 also specifies the various roles of the administrative staff on assignment to the NUCLARR Clearinghouse who are tasked with maintaining the data base, dealing with user requests, and processing NUCLARR data. 5 refs., 34 figs., 3 tabs

  8. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Guide to data processing and revision: Part 3, Hardware component failure data entry and revision procedures

    International Nuclear Information System (INIS)

    Gilmore, W.E.; Gertman, D.I.; Gilbert, B.G.; Reece, W.J.

    1988-11-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability (HEP) and hardware component failure data (HCFD). The NUCLARR system software resides on an IBM (or compatible) personal micro-computer. Users can perform data base searches to furnish HEP estimates and HCFD rates. In this manner, the NUCLARR system can be used to support a variety of risk assessment activities. This volume, Volume 3 of a 5-volume series, presents the procedures used to process HEP and HCFD for entry in NUCLARR and describes how to modify the existing NUCLARR taxonomy in order to add equipment types of action verbs. Volume 3 also specifies the various roles of the administrative staff on assignment to the NUCLARR Clearinghouse who are tasked with maintaining the data base, dealing with user requests, and processing NUCLARR data

  9. Spectrophotometric and computerized evaluation of tooth bleaching employing 10 different home-bleaching procedures: In-vitro study

    Science.gov (United States)

    Peskersoy, Cem; Tetik, Ayhan; Ozturk, Veli Ozgen; Gokay, Necmi

    2014-01-01

    Objective: The aim of this in-vitro study was to evaluate the efficacy of bleaching products, determine the applicability and validation of the measurement methods. Materials and Methods: Freshly extracted 110 human incisor teeth were stained with whole blood and hemolysate solution prior to the application of 10 different home-bleaching products. Spectrophotometric measurements of the tooth shades were performed for each specimen before and after bleaching at the 1st, 3rd, 7th, and 14 days. Differences in lightness (Δl), chroma (Δc), hue (Δh) values and shade changes were measured to evaluate process. Computerized digital imaging analyses to determine the color changes were performed with Photoshop CS4 software (Adobe, San Jose, CA, USA). Statistical analyses were performed with analysis of variance, Scheffe and Tukey tests. Results: In all of the test groups regardless of the material used, a significant increase in lightness and hue, and decrease of chroma were observed, as compared to the control group. After recommended bleaching applications, Δl and Δh values respectively increased in group Zaris White and Brite (ZWB) and group Pola Night and Δc values showed significant decrease in groups ZWB and Rembrandt REM3 (P bleaching systems showed slower but almost permanent bleaching effect likewise office-based methods. Both software and spectrophotometric analyses have advantages such as evaluating the results objectively and numerically, also treatment outcomes could be preserved. PMID:25512738

  10. Design-related influencing factors of the computerized procedure system for inclusion into human reliability analysis of the advanced control room

    International Nuclear Information System (INIS)

    Kim, Jaewhan; Lee, Seung Jun; Jang, Seung Cheol; Ahn, Kwang-Il; Shin, Yeong Cheol

    2013-01-01

    This paper presents major design factors of the computerized procedure system (CPS) by task characteristics/requirements, with individual relative weight evaluated by the analytic hierarchy process (AHP) technique, for inclusion into human reliability analysis (HRA) of the advanced control rooms. Task characteristics/requirements of an individual procedural step are classified into four categories according to the dynamic characteristics of an emergency situation: (1) a single-static step, (2) a single-dynamic and single-checking step, (3) a single-dynamic and continuous-monitoring step, and (4) a multiple-dynamic and continuous-monitoring step. According to the importance ranking evaluation by the AHP technique, ‘clearness of the instruction for taking action’, ‘clearness of the instruction and its structure for rule interpretation’, and ‘adequate provision of requisite information’ were rated as of being higher importance for all the task classifications. Importance of ‘adequacy of the monitoring function’ and ‘adequacy of representation of the dynamic link or relationship between procedural steps’ is dependent upon task characteristics. The result of the present study gives a valuable insight on which design factors of the CPS should be incorporated, with relative importance or weight between design factors, into HRA of the advanced control rooms. (author)

  11. Development, test and evaluation of a computerized procedure for using Landsat data to estimate spring small grains acreage

    Science.gov (United States)

    Mohler, R. R. J.; Palmer, W. F.; Smyrski, M. M.; Baker, T. C.; Nazare, C. V.

    1982-01-01

    A number of methods which can provide information concerning crop acreages on the basis of a utilization of multispectral scanner (MSS) data require for their implementation a comparatively large amount of labor. The present investigation is concerned with a project designed to improve the efficiency of analysis through increased automation. The Caesar technique was developed to realize this objective. The processability rates of the Caesar procedure versus the historical state-of-the-art proportion estimation procedures were determined in an experiment. Attention is given to the study site, the aggregation technology, the results of the aggregation test, and questions of error characterization. It is found that the Caesar procedure, which has been developed for the spring small grains region of North America, is highly efficient and provides accurate results.

  12. Integrated System Validation Usability Questionnaire: Computerized Procedures; Desarrollo del Cuestionario de Facilidad de Uso para la Validación de Sistemas Integrados: Procedimientos de Operacion

    Energy Technology Data Exchange (ETDEWEB)

    Garcés, Ma. I.; Torralba, B.

    2015-07-01

    The Research and Development (R&D) project on “Theoretical and Methodological Approaches to Integrated System Validation of Control Rooms, 2014-2015”, in which the research activities described in this report are framed, has two main objectives: to develop the items for an usability methodology conceived as a part of the measurement framework for performance-based control room evaluation that the OECD Halden Reactor Project will test in the experiments planned for 2015; and the statistical analysis of the data generated in the experimental activities of the Halden Man-Machine Laboratory (HAMMLAB) facility, with previous usability questionnaires, in 2010 and 2011. In this report, the procedure designed to meet the first goal of the project is described, in particular, the process followed to identify the items related to operating procedures, both computer and paper-based, one of the elements to be included in the usability questionnaire. Three phases are performed, in the first one, the approaches developed by the United States Nuclear Regulatory Commission, NRC, are reviewed, the models used by the nuclear industry and their technical support organizations, mainly, the Electric Power Research Institute, EPRI, are analyzed, and scientist advances are also explored. In the remaining stages, general and specific guidelines for computerized and paper-based procedures are compared and criteria for the preliminary selection of the items that should be incorporated into the usability questionnaire are defined. This proposal will be reviewed and adapted by the Halden Reactor Project to the design of the specific experiments performed in HAMLAB.

  13. Computerized procedure for protection coordination in distribution primary circuits; Procedimiento computarizado para coordinacion de protecciones en circuitos primarios de distribucion

    Energy Technology Data Exchange (ETDEWEB)

    Carrillo, Victor M; Velazquez Sanchez, Raul [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1987-12-31

    Nowadays, the method employed to study the protection coordination are based in the hand outlining of curves time- current and in the visual comparison in log sheets. Due to the large amount of distribution circuits, the engineer makes a considerable effort to perform this type of studies, which besides are routinist and time consuming. In this article a program for the computer aided design for the protection coordination in primary distribution circuits is presented. Such a program -carried out in the Transmission and Distribution Department of the Power Systems Division of the Instituto de Investigaciones Electricas (IIE)- substitutes in an efficient manner, the manual procedures that are performed in the protection coordination studies. The coordination principles, suggested by the equipment manufacturers, were respected, trying, at the same time, to keep the procedures of the Comision Federal de Electricidad personnel (CFE) emerged from the field experience. The algorithm basically consists of an iterative process in the selection of the adjustments taking as a reference the of three-phase short- circuit and of phase to ground, values, as well as the operating times. [Espanol] Actualmente, los metodos que se emplean para estudiar la coordinacion de protecciones se basan en el trazado manual de curvas de tiempo-corriente y en la comparacion visual sobre hojas logaritmicas. Debido a la gran cantidad de circuitos de distribucion, el ingeniero hace un esfuerzo considerable para realizar este tipo de estudios, los que ademas, son rutinarios y tardados. En este articulo, se presenta un programa para el diseno asistido por computadora del proceso de coordinacion de protecciones en circuitos primarios de distribucion. Dicho programa -realizado en el Departamento de Transmision y Distribucion, de la Division de Sistemas de Potencia, del Instituto de Investigaciones Electricas (IIE)- sustituye de manera eficaz los procedimientos manuales que se efectuan en los estudios

  14. Computerized procedure for protection coordination in distribution primary circuits; Procedimiento computarizado para coordinacion de protecciones en circuitos primarios de distribucion

    Energy Technology Data Exchange (ETDEWEB)

    Carrillo, Victor M.; Velazquez Sanchez, Raul [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1986-12-31

    Nowadays, the method employed to study the protection coordination are based in the hand outlining of curves time- current and in the visual comparison in log sheets. Due to the large amount of distribution circuits, the engineer makes a considerable effort to perform this type of studies, which besides are routinist and time consuming. In this article a program for the computer aided design for the protection coordination in primary distribution circuits is presented. Such a program -carried out in the Transmission and Distribution Department of the Power Systems Division of the Instituto de Investigaciones Electricas (IIE)- substitutes in an efficient manner, the manual procedures that are performed in the protection coordination studies. The coordination principles, suggested by the equipment manufacturers, were respected, trying, at the same time, to keep the procedures of the Comision Federal de Electricidad personnel (CFE) emerged from the field experience. The algorithm basically consists of an iterative process in the selection of the adjustments taking as a reference the of three-phase short- circuit and of phase to ground, values, as well as the operating times. [Espanol] Actualmente, los metodos que se emplean para estudiar la coordinacion de protecciones se basan en el trazado manual de curvas de tiempo-corriente y en la comparacion visual sobre hojas logaritmicas. Debido a la gran cantidad de circuitos de distribucion, el ingeniero hace un esfuerzo considerable para realizar este tipo de estudios, los que ademas, son rutinarios y tardados. En este articulo, se presenta un programa para el diseno asistido por computadora del proceso de coordinacion de protecciones en circuitos primarios de distribucion. Dicho programa -realizado en el Departamento de Transmision y Distribucion, de la Division de Sistemas de Potencia, del Instituto de Investigaciones Electricas (IIE)- sustituye de manera eficaz los procedimientos manuales que se efectuan en los estudios

  15. Numerical analysis of APR1400 Steam Generator by CUPID/MARS heat structure coupling

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Ryong Lee; Lee, Seung Jun; Pakr, Ik Kyu; Yoon, Han Young [KAERI, Daejeon (Korea, Republic of); Cho, Hyoung Kyu [Seoul National University, Seoul (Korea, Republic of)

    2015-05-15

    To design and analyze steam generators, many computer codes have been developed and used around the world. In this study, the coupled CUPID and MARS code was used for the simulation of boiler side of the PWR steam generator. This paper presents the description of the coupling method, validation for porous media approach against the rod bundle experiment and the preliminary simulation results of PWR steam generator using the coupled code. In the present study, the multi-scale thermal-hydraulic analysis method using the coupled CUPID/MARS code was applied for the simulation of the steam generator. The primary side of the steam generator and other RCS was simulated by MARS and the secondary side was calculated by CUPID with porous media approach. For coupled simulation, the porous medium was applied in order to take into account the effect of the U-tube bundle and other supporting structure which play a role to be a flow resistance. More realistic physical model such as moisture separator slug behavior should be developed for the near future. The application of the coupled simulation should be extended to the accident scenario.

  16. Study on the VFD (Variable Frequency Drive) for RCP (Reactor Coolant Pump) Motors of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jung Ha; Robert, M. Field; Kim, Tae Ryong [Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    Most industrial facilities are continually searching for ways to reduce energy costs while increasing or maintaining current production. In terms of electric motors, Variable Frequency Drive (VFD) units represent a critical opportunity for energy savings. Currently, VFDs are used on about ten (10) percent of industrial process motors, and this percentage is increasing every year. Properly applied VFDs have been documented to save as much as fifty percent of the energy consumed by certain industrial processes. Nuclear Power - Power plants in general and Nuclear Power Plants (NPPs) in particular are slow to adopt new technology. The nuclear power industry requires a nearly absolute demonstration through operating experience in other industries in which the new approach will result in a net improvement in plant reliability without any surprises. Only recently has the nuclear industry begun to adapt VFD units for large motors. Specifically, there are several examples in the Boiling Water Reactor (BWR) fleet of replacing Motor-Generator (M-G) sets with VFD units for Reactor Recirculation (RR) pump motor service. At one station, VFD units were introduced upstream of the Circulating Water (CWP) pump motors to address environmental issues. They units are taking advantage of VFD technology whose benefits include increased reliability, reduction in electrical house load, improved flow control, and reduced maintenance. RCP Application - In the case of new generation, it has been reported that the Westinghouse AP1000 will make use of VFD units for the Reactor Coolant Pump (RCP) motors.

  17. System Function Evaluation due to Hardware Failure of NSSS Control Systems in the APR1400

    International Nuclear Information System (INIS)

    Kim, Juyoung; Ahn, Myunghoon; Kim, Woogoon; Yim, Hyeongsoon

    2016-01-01

    As the performance and failure modes of the control systems may affect the plant response to accidents or disturbances, an evaluation is done to identify potential control system failure modes resulting from single hardware failures. These failure modes are for use in the analytical evaluations that will be performed to assess the plant responses to various disturbances from the viewpoint of postulated system malfunctions. Failure modes that fall into any of the above categories will affect the performance of the control system and should be considered in the analytical evaluation of the NSSS responses to disturbances. An evaluation was performed to identify the failure modes of the NSSS Control Systems, caused by a hardware component, a common sensing device, and a common power supply. The multiple failure modes across the NSSS control Systems are limited by the improved design features, redundancy within each systems, and segmentation between systems. Also, the effects from the failure modes are expected to be acceptably terminated by the Plant Protection System. The failure modes derived through this evaluation will be further considered in the analytical evaluation of the NSSS responses to disturbances in order to identify the single failures which could create the most adverse conditions during a given transient

  18. Preliminary Evaluations of CSPACE for a Station Blackout Transient in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Lee, T. B.; Lee, D. K.; Lee, H. S.; Lee, G. W.; Choi, T. S. [KEPCO, Daejeon (Korea, Republic of); Park, R. J.; Kim, D. H. [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    This paper discusses the preliminary results of the simulated station blackout (SBO) transients using the CSPACE code and presents the information pertinent to the related safety issues. CSPACE is a merged program of a master processer of Safety and Performance Analysis Code (SPACE) for nuclear power plants and a child processer of Core Meltdown Progression Accident Simulation Software (COMPASS) generated as a dynamic-link library (DLL) codes. It has been developed to predict the best-estimate transient in the pressurized water reactor (PWR) for severe accidents. SPACE and COMPASS codes take charge of the thermal-hydraulic response of PWRs and the analysis of the severe accident progression in a vessel, respectively. The initial phase is estimated starting from time zero when the loss of off-site and on-site powers occurs simultaneously. Shortly after the RCS pressure initially falls and rises slightly due to the effects of the reactor and turbine trips, the RCS pressure declines in response to the cooling provided by heat removed to the SGs. During the period of the primary heat-up and boil-off, the RCS pressure increase is limited by two cycles of the POSRV. The RCS fluid mass is lost through the pressurizer POSRV and then the core uncovers and superheated steam flows out from the RV into the coolant loops starting at 5513.0 seconds.

  19. Reliability Centered Maintenance (RCM) Methodology and Application to the Shutdown Cooling System for APR-1400 Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Faragalla, Mohamed M.; Emmanuel, Efenji; Alhammadi, Ibrahim; Awwal, Arigi M.; Lee, Yong Kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    Shutdown Cooling System (SCS) is a safety-related system that is used in conjunction with the Main Steam and Main or Auxiliary Feedwater Systems to reduce the temperature of the Reactor Coolant System (RCS) in post shutdown periods from the hot shutdown operating temperature to the refueling temperature. In this paper RCM methodology is applied to (SCS). RCM analysis is performed based on evaluation of Failure Modes Effects and Criticality Analysis (FME and CA) on the component, system and plant. The Logic Tree Analysis (LTA) is used to determine the optimum maintenance tasks. The main objectives of RCM is the safety, preserve the System function, the cost-effective maintenance of the plant components and increase the reliability and availability value. The RCM methodology is useful for improving the equipment reliability by strengthening the management of equipment condition, and leads to a significant decrease in the number of periodical maintenance, extended maintenance cycle, longer useful life of equipment, and decrease in overall maintenance cost. It also focuses on the safety of the system by assigning criticality index to the various components and further selecting maintenance activities based on the risk of failure involved. Therefore, it can be said that RCM introduces a maintenance plan designed for maximum safety in an economical manner and making the system more reliable. For the SCP, increasing the number of condition monitoring tasks will improve the availability of the SCP. It is recommended to reduce the number of periodic maintenance activities.

  20. Conceptual Design of Condenser using PCM as PCCS for APR1400

    International Nuclear Information System (INIS)

    Jung, Hwa-Young; Ko, A-Reum; Lee, Jeong Ik; Yoon, Ho Joon

    2016-01-01

    In this study, the conceptual design of the condenser using the phase change material (PCM) is proposed as another PCCS concept for PWRs. It is possible to install the condenser for the existing nuclear power plants under operation without PCCS. Most of all, this condenser has to be designed to reduce the pressure and temperature in the containment until the containment spray system is available. A feature of the condenser as shown in Fig. 2 is the composition of PCM and wire mesh connected with the fins to improve heat transfer. As the first step, a preliminary study was conducted to find the optimum design of the part at which the condensation occurs under the given conditions. The results show that the fin base area as well as the total heat transfer area of fins are generally in inversely proportional to the average condensation heat transfer coefficient. Also, the point at which the gradient is changed is when the flow regime is changed from wavy flow to turbulent flow. However, the number of fins shows the different trend. Thus, in order to achieve better average condensation heat transfer coefficient under the identical heat capacity condition, the shorter the fin length and the more fins are necessary for the optimum design the condenser in wavy flow region

  1. Conceptual Design of Condenser using PCM as PCCS for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Hwa-Young; Ko, A-Reum; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of); Yoon, Ho Joon [KUSTAR, Abu Dhabi (United Arab Emirates)

    2016-10-15

    In this study, the conceptual design of the condenser using the phase change material (PCM) is proposed as another PCCS concept for PWRs. It is possible to install the condenser for the existing nuclear power plants under operation without PCCS. Most of all, this condenser has to be designed to reduce the pressure and temperature in the containment until the containment spray system is available. A feature of the condenser as shown in Fig. 2 is the composition of PCM and wire mesh connected with the fins to improve heat transfer. As the first step, a preliminary study was conducted to find the optimum design of the part at which the condensation occurs under the given conditions. The results show that the fin base area as well as the total heat transfer area of fins are generally in inversely proportional to the average condensation heat transfer coefficient. Also, the point at which the gradient is changed is when the flow regime is changed from wavy flow to turbulent flow. However, the number of fins shows the different trend. Thus, in order to achieve better average condensation heat transfer coefficient under the identical heat capacity condition, the shorter the fin length and the more fins are necessary for the optimum design the condenser in wavy flow region.

  2. A Comparison of Item Selection Procedures Using Different Ability Estimation Methods in Computerized Adaptive Testing Based on the Generalized Partial Credit Model

    Science.gov (United States)

    Ho, Tsung-Han

    2010-01-01

    Computerized adaptive testing (CAT) provides a highly efficient alternative to the paper-and-pencil test. By selecting items that match examinees' ability levels, CAT not only can shorten test length and administration time but it can also increase measurement precision and reduce measurement error. In CAT, maximum information (MI) is the most…

  3. Computerized radiation treatment planning

    International Nuclear Information System (INIS)

    Laarse, R. van der.

    1981-01-01

    Following a general introduction, a chain consisting of three computer programs which has been developed for treatment planning of external beam radiotherapy without manual intervention is described. New score functions used for determination of optimal incidence directions are presented and the calculation of the position of the isocentre for each optimum combination of incidence directions is explained. A description of how a set of applicators, covering fields with dimensions of 4 to 20 cm, for the 6 to 20 MeV electron beams of a MEL SL75-20 linear accelerator was developed, is given. A computer program for three dimensional electron beam treatment planning is presented. A microprocessor based treatment planning system for the Selectron remote controlled afterloading system for intracavitary radiotherapy is described. The main differences in treatment planning procedures for external beam therapy with neutrons instead of photons is discussed. A microprocessor based densitometer for plotting isodensity lines in film dosimetry is described. A computer program for dose planning of brachytherapy is presented. Finally a general discussion about the different aspects of computerized treatment planning as presented in this thesis is given. (Auth.)

  4. Human error probability evaluation as part of reliability analysis of digital protection system of advanced pressurized water reactor - APR 1400

    International Nuclear Information System (INIS)

    Varde, P. V.; Lee, D. Y.; Han, J. B.

    2003-03-01

    A case of study on human reliability analysis has been performed as part of reliability analysis of digital protection system of the reactor automatically actuates the shutdown system of the reactor when demanded. However, the safety analysis takes credit for operator action as a diverse mean for tripping the reactor for, though a low probability, ATWS scenario. Based on the available information two cases, viz., human error in tripping the reactor and calibration error for instrumentations in protection system, have been analyzed. Wherever applicable a parametric study has also been performed

  5. Experimental analysis of ex-vessel core catcher cooling system performance for EU-APR1400 during severe accident

    Energy Technology Data Exchange (ETDEWEB)

    Song, K. W.; Park, H. S.; Revankar, S. T. [POSTECH, Pohang (Korea, Republic of); Kim, H. Y. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In the coolant channel which has a unique design and large scale flow paths, natural circulation is passively activated by buoyancy driven force. Since two-phase flow behavior in a large scale channel is different from that in a small scale channel, the two-phase flow affecting the cooling capability is difficult to be predicted in the large channel. Therefore, cooling experiment in the core catcher coolant path is necessary. Cooling Experiment - Passive Ex-vessel corium retaining and Cooling System(CE-PECS) is constructed in full scale(in height and width) slice of half prototype. It actually simulates steam-water flow in the coolant channel for different decay heat condition of the corium. In this study, thermal power considering of total amount of decay heat 190 kW which corresponds to 40MW of thermal power in the prototype is loaded on the top wall of the CE-PECS coolant channel. Natural circulation flow rate and pressure drops at the two-phase region are measured in various power level. Temperatures of heater block and working fluid in various position along the flow path enable to calculate heat fluxes and heat transfer coefficients distribution. These results are used for evaluating heat removal capability of core catcher facility. Two-phase natural circulation experiment is carried out in CE-PECS facility. Based on the prototypic condition, 190 kW of total power is supplied to the top of the coolant path. Uniform distribution of heat load on the downward facing heater bock produces -300 kW/m2 at 100 % power ratio. Although the experiment should consider the heat loss and heat flux uniformity, several noticeable conclusions have been made as followings; 1. Mass flow rate and two-phase pressure drop are measured in various power conditions. 2. Slightly inclined top wall at the downstream of the channel shows better heat exchange performance than horizontal top wall because enhanced convection due to the increase of void fraction improves local cooling. This effect is more clear in high power region.

  6. Computerizing Maintenance Management Improves School Processes.

    Science.gov (United States)

    Conroy, Pat

    2002-01-01

    Describes how a Computerized Maintenance Management System (CMMS), a centralized maintenance operations database that facilitates work order procedures and staff directives, can help individual school campuses and school districts to manage maintenance. Presents the benefits of CMMS and things to consider in CMMS selection. (EV)

  7. Computerized management of plant intervention tasks

    International Nuclear Information System (INIS)

    Remacle, J.; Quoidbach, G.

    1993-01-01

    The concept of 'computerized management' of plant intervention tasks was developed by TRACTEBEL in 1983 for the Belgian power plants of ELECTRABEL. The main objective of the 'Computerized Management of Plant Intervention Tasks' is to help the staff of a nuclear or a conventional power plant in planning, organizing, and carrying out any (preventive or corrective) maintenance task. It consists of a group of interconnected functional modules acting on a unique and homogeneous data base. A short description of 3 modules is given, i.e., the 'User' Module, the 'Equipment' Module and the 'Periodic Procedure' Module. (Z.S.)

  8. Computerized Italian criticality guide, description and validation

    International Nuclear Information System (INIS)

    Carotenuto, M.; Landeyro, P.A.

    1988-10-01

    Our group is developing an 'expert system' for collecting engineering know-how on back-end nuclear plant design. An expert system is the most suitable software tool for our problem. During the analysis, the design process was divided into different branches. At each branch of the design process the Expert System relates a computerized design procedure. Any design procedure is composed of a set of design methods, together with their condition of application and reliability limits. In the framework of this expert system, the nuclear criticality safety analysis procedure was developed, in the form of a computerized criticality guide, attempting to reproduce the designer's normal 'reasoning' process. The criticality guide is composed of two parts: A computerized text, including theory, a description of the accidents occurred in the past and a description of the italian design experience; An interactive computer aided calculation module, containing a graphical facility for critical parameter curves. In the present report are presented the criticality guide (computerized Italian Criticality Guide) and its validation test. (author)

  9. Computerized Italian criticality guide, description and validation

    Energy Technology Data Exchange (ETDEWEB)

    Carotenuto, M; Landeyro, P A [ENEA - Dipartimento Ciclo del Combustibile, Centro Ricerche Energia, Casaccia (Italy)

    1988-10-15

    Our group is developing an 'expert system' for collecting engineering know-how on back-end nuclear plant design. An expert system is the most suitable software tool for our problem. During the analysis, the design process was divided into different branches. At each branch of the design process the Expert System relates a computerized design procedure. Any design procedure is composed of a set of design methods, together with their condition of application and reliability limits. In the framework of this expert system, the nuclear criticality safety analysis procedure was developed, in the form of a computerized criticality guide, attempting to reproduce the designer's normal 'reasoning' process. The criticality guide is composed of two parts: A computerized text, including theory, a description of the accidents occurred in the past and a description of the italian design experience; An interactive computer aided calculation module, containing a graphical facility for critical parameter curves. In the present report are presented the criticality guide (computerized Italian Criticality Guide) and its validation test. (author)

  10. Celebral computerized tomography

    International Nuclear Information System (INIS)

    Lofteroed, B.; Sortland, O.

    1985-01-01

    Indications for cerebral computerized tomography (CT) and the diagnostic results from this examination are evaluated in 127 children. Pathological changes were found in 31 children, mostly based on such indications as increasing head size, suspicion of brain tumor, cerebral paresis, delayed psychomotor development and epileptic seizures. A list of indications for CT in children is given

  11. Computerized industrial tomography

    International Nuclear Information System (INIS)

    Ashraf, M.M.

    1999-01-01

    Computerized Tomographic (CT) has been used for a number of applications in the field of medicine and industry. For the last couple of years, the technique has been applied for the material characterization and detection of defects and flaws inside the industrial components of nuclear, aerospace and missile industries. A CT scanner of first generation was developed at the institute. The scanner has been used to demonstrate couple of applications of CT in the field of non destructive testing of materials. The data acquired by placing the test objects at various angles and scanning the object through a source detector assembly has been processed on a Pentium computer for image reconstruction using a filtered back projection method. The technique has been developed which can be modified and improved to study various other applications in materials science and a modern computerized tomographic facility can be established. (author)

  12. Highly resolving computerized tomography

    International Nuclear Information System (INIS)

    Kurtz, B.; Petersen, D.; Walter, E.

    1984-01-01

    With the development of highly-resolving devices for computerized tomography, CT diagnosis of the lumbar vertebral column has gained increasing importance. As an ambulatory, non-invasive method it has proved in comparative studies to be at least equivalent to myelography in the detection of dislocations of inter-vertebral disks (4,6,7,15). Because with modern devices not alone the bones, but especially the spinal soft part structures are clearly and precisely presented with a resolution of distinctly below 1 mm, a further improvement of the results is expected as experience will increase. The authors report on the diagnosis of the lumbar vertebral column with the aid of a modern device for computerized tomography and wish to draw particular attention to the possibility of doing this investigation as a routine, and to the diagnostic value of secondary reconstructions. (BWU) [de

  13. Highly resolving computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, B.; Petersen, D.; Walter, E.

    1984-01-01

    With the development of highly-resolving devices for computerized tomography, CT diagnosis of the lumbar vertebral column has gained increasing importance. As an ambulatory, non-invasive method it has proved in comparative studies to be at least equivalent to myelography in the detection of dislocations of inter-vertebral disks (4,6,7,15). Because with modern devices not alone the bones, but especially the spinal soft part structures are clearly and precisely presented with a resolution of distinctly below 1 mm, a further improvement of the results is expected as experience will increase. The authors report on the diagnosis of the lumbar vertebral column with the aid of a modern device for computerized tomography and wish to draw particular attention to the possibility of doing this investigation as a routine, and to the diagnostic value of secondary reconstructions.

  14. Computerized plant maintenance management

    International Nuclear Information System (INIS)

    Kozusko, A.M.

    1986-01-01

    The evolution of the computer has and continues to have a great impact on industry. We are in an adjustment cycle with the current computer evolution, and will need to adapt to make the changes for the coming decade. Hardware and software are continually being enhanced. Computers are becoming more powerful and will eventually provide an effective man-machine interface. This paper shares experiences encountered during implementations of computerized maintenance systems

  15. Computerized medical convocations

    International Nuclear Information System (INIS)

    Roche, Annie; Gilbert, Jean-Francois; Chiadot, Pierre; Vanzetto, Rene; Darnault, Jean

    1969-06-01

    Thanks to a close collaboration between the Medical and Social department and the Numerical Calculation Laboratory, a computerized convocation system has been implemented to reduce the administrative workload and to introduce more rigor in medical management, patient historical background and statistics. This work comprises: - a preliminary study of the data generating medical convocations and the related practical requirements; - the programming work according to these data; - the realisation of the mechano-graphical file covering the overall personnel [fr

  16. Computerized operator decision aids

    International Nuclear Information System (INIS)

    Long, A.B.

    1984-01-01

    This article explores the potential benefits associated with the use of computers in nuclear plants by the operating crew as an aid in making decisions. Pertinent findings are presented from recently completed projects to establish the context in which operating decisions have to be made. Key factors influencing the decision-making process itself are also identified. Safety parameter display systems, which are being implemented in various forms by the nuclear industry, are described within the context of decision making. In addition, relevant worldwide research and development activities are examined as potential enhancements to computerized operator decision aids to further improve plant safety and availability

  17. Computerized spleen volumetry

    International Nuclear Information System (INIS)

    Jahnke, T.; Mohring, R.; Schertel, L.

    1981-01-01

    We examined in experimental studies and clinical investigations on 34 patients in how far volumetry of the spleen can be carried out with a commonly available program, a whole-body computerized tomograph (SOMATOM) and an analytic equipment (EVALUSKOP). In this connection the authors tried to find also other ways of spleen volumetry by means of this unit combination. Our final result was that the given program for the usage of labelled areas presents itself as the best-suited technique for spleen volumetry which is also applicable in practice. (orig./MG) [de

  18. Computerized adaptive testing item selection in computerized adaptive learning systems

    NARCIS (Netherlands)

    Eggen, Theodorus Johannes Hendrikus Maria; Eggen, T.J.H.M.; Veldkamp, B.P.

    2012-01-01

    Item selection methods traditionally developed for computerized adaptive testing (CAT) are explored for their usefulness in item-based computerized adaptive learning (CAL) systems. While in CAT Fisher information-based selection is optimal, for recovering learning populations in CAL systems item

  19. Computerized tomographic system

    International Nuclear Information System (INIS)

    Godbarsen, R.; Barrett, D.M.; Garrott, P.M.; Foley, L.E.; Redington, R.W.; Lambert, T.W.; Edelheit, L.S.

    1981-01-01

    A computerized tomographic system for examining human breasts is described in detail. Conventional X-ray scanning apparatus has difficulty in achieving the levels of image definition and examination speeds required for mass screening. A novel method of scanning successive layers of the breast with a rotating X-ray beam is discussed and details of the control circuitry and sequence steps are given. The method involves immersing the breast in an inner fluid (e.g. water) filled container which is stationary during an examination and is surrounded by a large outer container which is also filled with the fluid; the inner and outer containers are always maintained at a constant height and the X-ray absorption across the fan-shaped beam is as close as possible to constant. (U.K.)

  20. A Computerized Approach to Trickle-Process, Random Assignment.

    Science.gov (United States)

    Braucht, G. Nicholas; Reichardt, Charles S.

    1993-01-01

    Procedures for implementing random assignment with trickle processing and ways they can be corrupted are described. A computerized method for implementing random assignment with trickle processing is presented as a desirable alternative in many situations and a way of protecting against threats to assignment validity. (SLD)

  1. Computerized tomography in myotonic dystrophy

    International Nuclear Information System (INIS)

    Gellerich, I.; Mueller, D.; Koch, R.D.

    1986-01-01

    Besides clinical symptoms, progress and electromyography computerized tomography improves the diagnostics of myotonic dystrophy. Even small changes in muscular structure are detectable and especially the musculus soleus exhibits early and pronounced alterations. By means of density distribution pattern an improved characterization of the disease is possible. Additional information is obtained by cerebral computerized tomography. Atrophy of brain tissue is to be expected in all patients with myotonic dystrophy. (author)

  2. Radioactive waste computerized management

    International Nuclear Information System (INIS)

    Communaux, M.; Lantes, B.

    1993-01-01

    Since December 31, 1990, the management of the nuclear wastes for all the power stations has been computerized, using the DRA module of the Power Generation and Transmission Group's data processing master plan. So now EDF has a software package which centralizes all the data, enabling it to declare the characteristics of the nuclear wastes which are to be stored on the sites operated by the National Radioactive Waste Management Agency (ANDRA). Among other uses, this application makes it possible for EDF, by real time data exchange with ANDRA, to constitute an inventory of validated, shippable packs. It also constitutes a data base for all the wastes produced on the various sites. This application was developed to meet the following requirements: give the producers of radioactive waste a means to fully manage all the characteristics and materials that are necessary to condition their waste correctly; guarantee the traceability and safety of data and automatically assure the transmission of this data in real time between the producers and the ANDRA; give the Central Services of EDF an operation and statistical tool permitting an experienced feed-back based on the complete national production (single, centralized data base); and integrate the application within the products of the processing master plan in order to assure its maintenance and evolution

  3. Computerized data treatment technology

    International Nuclear Information System (INIS)

    Ferguson, R.B.; Maddox, J.H.; Wren, H.F.

    1977-01-01

    The Savannah River Laboratory (SRL) has accepted responsibility for a hydrogeochemical and stream-sediment reconnaissance in 25 eastern states as part of the National Uranium Resource Evaluation (NURE). SRL has developed a computerized program for recording, processing, updating, retrieving, and analyzing hydrogeochemical data from this reconnaissance. This program will handle an expected 150 million bytes of hydrogeochemical data from 150,000 to 200,000 sample sites over the next four years. The SRL--NURE hydrogeochemical data management system is written in FORTRAN IV for an IBM System 360/195 computer and is designed to easily accommodate changes in types of collected data and input format. As the data become available, they are accepted and combined with relevant data already in the system. SRL also developed a sample inventory and control system and a graphics and analysis system. The sample inventory and control system accounts for the movements of all samples and forms from initial receipt through final storage. Approximately six million sample movements are expected. The graphics and analysis system provides easily usable programs for reporting and interpreting data. Because of the large volume of data to be interpreted, the graphics and analysis system plays a central role in the hydrogeochemical program. Programs developed to provide two- and three-dimensional plots of sampled geographic areas show concentrations and locations of individual variables which are displayed and reproduced photographically. Pattern recognition techniques are also available, and they allow multivariate data to be categorized into ''clusters,'' which may indicate sites favorable for uranium exploration

  4. Handbook of radiologic procedures

    International Nuclear Information System (INIS)

    Hedgcock, M.

    1986-01-01

    This book is organized around radiologic procedures with each discussed from the points of view of: indications, contraindications, materials, method of procedures and complications. Covered in this book are: emergency radiology chest radiology, bone radiology, gastrointestinal radiology, GU radiology, pediatric radiology, computerized tomography, neuroradiology, visceral and peripheral angiography, cardiovascular radiology, nuclear medicine, lymphangiography, and mammography

  5. Computerized operation of the DIII-D neutral beams

    International Nuclear Information System (INIS)

    Glad, A.S.; Tooker, J.F.

    1986-01-01

    Operation of the DIII-D neutral beams utilizes computerized control to provide routine tokamak beam heating shots and an effective method for automatic ion source operation. Computerized control reduces operational complexity, thus providing consistent reliability and availability of beams and a significant reduction in the the costs of routine operation. The objectives in implementing computerized control for operation were: (1) to improve operator efficiency for controlling multiple beam lines and increasing beam availability through standard procedures, (2) to provide a simplified scheme that operators and coordinators can construct and maintain, and (3) to provide a single integrated mechanism for both tokamak operation and automatic source conditioning. The years of experience in operating neutral beams at Doublet III provided the data necessary to meet the objectives. The method for computerized control consisted of three integrated functions: (1) a structured command language was implemented to provide the mechanism for automatically sequencing beams, (2) a historical file was constructed from the operational parameters to characterize the ion source, and consists of data from approximately 100,000 beam shots, and (3) procedures were developed integrating the language to the historical file for normal operation and source conditioning. This paper describes the method for sequencing beams automatically, the structure of the historical data file, and the procedures which integrate the historical data with tokamak operation and automatic source conditioning

  6. Experience feedback of computerized controlled nuclear power plants

    International Nuclear Information System (INIS)

    Poizat, F.

    2004-01-01

    The N4 step of French PWR-type nuclear power plants is characterized by an instrumentation and control system entirely computerized (operation procedures including normal and accidental operation). Four power plants of this type (Chooz and Civaux sites) of 1450 MWe each were connected to the power grid between August 1996 and December 1999. The achievement of this program make it possible and necessary to carry out an experience feedback about the development, successes and difficulties encountered in order to draw out some lessons for future realizations. This is the aim of this article: 1 - usefulness and difficulties of such an experience feedback: evolution of instrumentation and control systems, necessary cautions; 2 - a successful computerized control: checking of systems operation, advantages, expectations; 3 - efficiency of computerized systems: demonstration of operation safety, profitability; 4 - conclusions and interrogations: system approach instead of 'micro-software' approach, commercial or 'made to measure' products, contract agreement with a supplier, when and how upgrading. (J.S.)

  7. Cognitive task analysis and the design of computerized operator aids

    International Nuclear Information System (INIS)

    Andersson, H.

    1985-01-01

    The new technological possibilities have led to the initiation of many projects for the design and evaluation of computerized operator support systems to be implemented in nuclear power plant control rooms. A typical finding so far has been that operators often have a positive attitude towards such systems but still don't use them very much, mostly because they find almost the same information on the conventional control boards which they are accustomed to use. Still, however, there is a widely shared belief that conventional control rooms have short-comings that make the use of computerized aids necessary. One reason for the limited success so far is that the new systems often are poorly integrated with the existing conventional instrumentation and with the working procedures. The reluctance to use new computer based aids, despite their nice features, is therefore probably caused by an inadequate task analysis made prior to the design of these computerized operator support systems

  8. Hand-held electronic data collection and procedure environment

    International Nuclear Information System (INIS)

    Kennedy, E.; Doniz, K.

    1996-01-01

    As part of a CANDU Owners Group project, AECL has developed a hand-held electronic data collection and procedure environment. Integral to this environment is the C omputerized Procedure Engine . The development of the CPE allows operators, maintainers, and technical support staff to execute virtually any type of station procedure on a general-purpose PC-compatible hand-held computer. There are several advantages to using the computerized procedures: less paper use and handling, reduction in human error, reduction in rework in the field, an increase in procedural compliance, and immediate availability of data to download to databases and plant information systems. The paper describes: the advantages of using computerized procedures, why early forms of computerized procedures were inadequate, the features that the C omputerized Procedure Engine o ffers to the user, the streamlined life cycle of a computerized procedure, and field experience. The paper concludes that computerized procedures are ready for pilot applications at stations. (author)

  9. Computerized tomography system

    International Nuclear Information System (INIS)

    Hellstrom, M.; Kutlik, E.; Perlin, A.

    1980-01-01

    A method for non-mechanically linking the motions of an x-ray source with an x-ray receptor during a tomographic procedure to produce a tomograph of a section of an object under examination comprising the steps of: effecting motion of said source and receptor to respective reference positions; thereafter during a tomographic procedural mode generating from at least one fixed frequency signal source first and second pulse trains, adapted to drive respective stepper motors, for effecting motion of said source and receptor, said pulse trains having a predetermined mathematical relationship dependent upon the desired fulcrum height of the tomographic section to be produced; and applying said first and second pulse trains to the respective stepper motors for a predetermined number of pulse counts to effect motion with respect to said respective reference positions and effecting a tomographic sweep thereby

  10. Patient surface doses in computerized tomography examinations

    International Nuclear Information System (INIS)

    Vekic, B; Kovacevic, S.; Ranogajec-Komor, M.; Duvnjak, N.; Marusic, P.; Anic, P.; Dolencic, P.

    1996-01-01

    The diagnostic value of computerized tomography has increased due to very rapid technical advances in both equipment and techniques. When the CT scanners were introduced, a significant problem for the specification of the radiation dose imparted to the patient undergoing CT examination has been created. In CT, the conditions of exposure are quite different from those in conventional X-ray imaging. CT procedure involves the continuous tomography of thin layers. Some of these layers touch each other while others overlap. The radiation doses received by patients can vary considerably. In addition to the radiation from the collimated primary beam, patients are exposed to significant scattered doses in unpredictable amounts. Every effort should be made to keep these doses to a reasonable minimum, without sacrificing the image quality. The aims of this work were to determine the surface doses delivered to various organs of patients during various computerized tomography examinations (head, thorax, kidney, abdomen and pelvis). Particular attention was directed to the precise determination of doses received by the eyes (during CT of head) and gonads (during CT of pelvis and lower abdomen) since these organs can be near or even in the primary X-ray beam

  11. Technologies in computerized lexicography | Kruyt | Lexikos

    African Journals Online (AJOL)

    Although the topic of this paper is technology, focus is on functional rather than technical aspects of computerized lexicography. Keywords: computerized lexicography, electronic dictionary, electronic text corpus, lexicographer's workbench, integrated language database, automatic linguistic analysis, information retrieval, ...

  12. Computerized radioautographic grain counting

    International Nuclear Information System (INIS)

    McKanna, J.A.; Casagrande, V.A.

    1985-01-01

    In recent years, radiolabeling techniques have become fundamental assays in physiology and biochemistry experiments. They also have assumed increasingly important roles in morphologic studies. Characteristically, radioautographic analysis of structure has been qualitative rather than quantitative, however, microcomputers have opened the door to several methods for quantifying grain counts and density. The overall goal of this chapter is to describe grain counting using the Bioquant, an image analysis package based originally on the Apple II+, and now available for several popular microcomputers. The authors discuss their image analysis procedures by applying them to a study of development in the central nervous system

  13. Computerized Proof Techniques for Undergraduates

    Science.gov (United States)

    Smith, Christopher J.; Tefera, Akalu; Zeleke, Aklilu

    2012-01-01

    The use of computer algebra systems such as Maple and Mathematica is becoming increasingly important and widespread in mathematics learning, teaching and research. In this article, we present computerized proof techniques of Gosper, Wilf-Zeilberger and Zeilberger that can be used for enhancing the teaching and learning of topics in discrete…

  14. Computerized adaptive testing in computer assisted learning?

    NARCIS (Netherlands)

    Veldkamp, Bernard P.; Matteucci, Mariagiulia; Eggen, Theodorus Johannes Hendrikus Maria; De Wannemacker, Stefan; Clarebout, Geraldine; De Causmaecker, Patrick

    2011-01-01

    A major goal in computerized learning systems is to optimize learning, while in computerized adaptive tests (CAT) efficient measurement of the proficiency of students is the main focus. There seems to be a common interest to integrate computerized adaptive item selection in learning systems and

  15. Pain Perception: Computerized versus Traditional Local Anesthesia in Pediatric Patients.

    Science.gov (United States)

    Mittal, M; Kumar, A; Srivastava, D; Sharma, P; Sharma, S

    2015-01-01

    Local anesthetic injection is one of the most anxiety- provoking procedure for both children and adult patients in dentistry. A computerized system for slow delivery of local anesthetic has been developed as a possible solution to reduce the pain related to the local anesthetic injection. The present study was conducted to evaluate and compare pain perception rates in pediatric patients with computerized system and traditional methods, both objectively and subjectively. It was a randomized controlled study in one hundred children aged 8-12 years in healthy physical and mental state, assessed as being cooperative, requiring extraction of maxillary primary molars. Children were divided into two groups by random sampling - Group A received buccal and palatal infiltration injection using Wand, while Group B received buccal and palatal infiltration using traditional syringe. Visual Analog scale (VAS) was used for subjective evaluation of pain perception by patient. Sound, Eye, Motor (SEM) scale was used as an objective method where sound, eye and motor reactions of patient were observed and heart rate measurement using pulse oximeter was used as the physiological parameter for objective evaluation. Patients experienced significantly less pain of injection with the computerized method during palatal infiltration, while less pain was not statistically significant during buccal infiltration. Heart rate increased during both buccal and palatal infiltration in traditional and computerized local anesthesia, but difference between traditional and computerized method was not statistically significant. It was concluded that pain perception was significantly more during traditional palatal infiltration injection as compared to computerized palatal infiltration, while there was no difference in pain perception during buccal infiltration in both the groups.

  16. Plan for Structural Analysis of Fuel Assembly for Seismic and Loss of Coolant Accident Loading Considering End-Of-Life Condition for APR1400 NRC Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong-Hak [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The evaluation of fuel assembly structural response to externally applied forces by earthquakes and postulated pipe breaks in the reactor coolant system is described in standard review plan (SRP) 4.2, appendix A. SRP 4.2, appendix A, section III, states, 'While P(crit) [the crushing load] will increase with irradiation, ductility will be reduced. The extra margin in P(crit) for irradiated spacer grids is thus assumed to offset the unknown deformation behavior of irradiated spacer grids beyond P(crit).' The assumption in the SRP concerning irradiated grids may suggest that only the beginning-of-life (BOL) condition for spacer grid strength needs to be evaluated for fuel assembly integrity under externally applied forces. However, U.S. NRC issued the NRC. To consider the EOL conditions for the structural analysis of the fuel assembly under a seismic and LOCA loading, the simulated fuel assembly for EOL conditions should be considered by determining the gap between the spacer grid and fuel rod. Using the simulated fuel assembly, spacer grid test and fuel assembly mechanical test should be conducted to determine the simplified model of fuel assembly which is used for the structural analysis. The structural analysis will be conducted using the fuel assembly model for EOL condition. The flow damping value will be also used for the structural analysis to reduce the impact force.

  17. Comparison of THALES and VIPRE-01 Subchannel Codes for Loss of Flow and Single Reactor Coolant Pump Rotor Seizure Accidents using Lumped Channel APR1400 Geometry

    Energy Technology Data Exchange (ETDEWEB)

    Oezdemir, Erdal; Moon, Kang Hoon; Oh, Seung Jong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of); Kim, Yongdeog [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    Subchannel analysis plays important role to evaluate safety critical parameters like minimum departure from nucleate boiling ratio (MDNBR), peak clad temperature and fuel centerline temperature. In this study, two different subchannel codes, VIPRE-01 (Versatile Internals and Component Program for Reactors: EPRI) and THALES (Thermal Hydraulic AnaLyzer for Enhanced Simulation of core) are examined. In this study, two different transient cases for which MDNBR result play important role are selected to conduct analysis with THALES and VIPRE-01 subchannel codes. In order to get comparable results same core geometry, fuel parameters, correlations and models are selected for each code. MDNBR results from simulations by both code are agree with each other with negligible difference. Whereas, simulations conducted by enabling conduction model in VIPRE-01 shows significant difference from the results of THALES.

  18. Preliminary H{sub 2} Combustion Analysis in the Containment of APR1400 for SBLOCA Accident using a Multi-Dimensional H{sub 2} Analysis System

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Hyung Seok; Kim, Jongtae; Kim, Sang-Baik; Hong, Seong-Wan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The COM3D analyze an overpressure buildup resulting from a propagation of hydrogen flame along the structure and wall in the containment using the hydrogen distribution result calculated by the GASFLOW. The MAAP evaluates a hydrogen source during a severe accident and transfer it to the GASFLOW. We performed a hydrogen combustion analysis using the multidimensional hydrogen analysis system for a station blackout (SBO) accident under the assumption of 100% metal-water reaction in the reactor vessel. The COM3D results showed that the pressure buildup was about 250 kPa because the flame speed was not increased above 300 m/s and the pressure wave passed through the open spaces in the large containment. To increase the reliability of the COM3D calculation, it is necessary to perform the hydrogen combustion analysis for another accident such as a small break loss of coolant (SBLOCA). KAERI performed a hydrogen combustion analysis for a SBLOCA accident using the multi-dimensional hydrogen analysis system under the assumption of 100% metal-water reaction in the reactor vessel. From the COM3D results, we can know that the pressure buildup was approximately 310 kPa because the flame speed was not increased above 100 m/s owing to the high steam concentration and low oxygen concentration in the hydrogen distributed region of the containment. The predicted maximum overpressure in the SBLOCA accident is similar to that of the COM3D results for the SBO accident. Thus, we found that the maximum overpressure due to the hydrogen combustion in the containment may depend on the amount of hydrogen mass released from the reactor vessel.

  19. Experimental study on two-phase flow natural circulation in a core catcher cooling channel for EU-APR1400 using air-water system

    Energy Technology Data Exchange (ETDEWEB)

    Song, Ki Won [Division of Advanced Nuclear Engineering, POSTECH, Pohang 790-784 (Korea, Republic of); Korea Atomic Energy Research Institute, Daejeon 34057 (Korea, Republic of); Nguyen, Thanh Hung [School of Nuclear Engineering, Purdue University, West Lafayette, IN 47906 (United States); Ha, Kwang Soon; Kim, Hwan Yeol; Song, Jinho [Korea Atomic Energy Research Institute, Daejeon 34057 (Korea, Republic of); Park, Hyun Sun [Division of Advanced Nuclear Engineering, POSTECH, Pohang 790-784 (Korea, Republic of); Revankar, Shripad T., E-mail: shripad@postech.ac.kr [Division of Advanced Nuclear Engineering, POSTECH, Pohang 790-784 (Korea, Republic of); School of Nuclear Engineering, Purdue University, West Lafayette, IN 47906 (United States); Kim, Moo Hwan [Division of Advanced Nuclear Engineering, POSTECH, Pohang 790-784 (Korea, Republic of); Korea Institute of Nuclear Safety, Daejeon 305-338 (Korea, Republic of)

    2017-05-15

    Highlights: • Two-phase flow regimes and transition behavior were observed in the coolant channel. • Test were conducted for natural circulation with air-water. • Data were obtained on flow regime, void fraction, flow rates and re-wetting time. • The data were related to a cooling capability of core catcher system. - Abstract: Ex-vessel core catcher cooling system driven by natural circulation is designed using a full scaled air-water system. A transparent half symmetric section of a core catcher coolant channel of a pressurized water reactor was designed with instrumentations for local void fraction measurement and flow visualization. Two designs of air-water top separator water tanks are studied including one with modified ‘super-step’ design which prevents gas entrainment into down-comer. In the experiment air flow rates are set corresponding to steam generation rate for given corium decay power. Measurements of natural circulation flow rate, spatial local void fraction distribution and re-wetting time near the top wall are carried out for various air flow rates which simulate boiling-induced vapor generation. Since heat transfer and critical heat flux are strongly dependent on the water mass flow rate and development of two-phase flow on the heated wall, knowledge of two-phase flow characteristics in the coolant channel is essential. Results on flow visualization showing two phase flow structure specifically near the high void accumulation regions, local void profiles, rewetting time, and natural circulation flow rate are presented for various air flow rates that simulate corium power levels. The data are useful in assessing the cooling capability of and safety of the core catcher system.

  20. 45 CFR 310.40 - What requirements apply for accessing systems and records for monitoring Computerized Tribal IV-D...

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false What requirements apply for accessing systems and records for monitoring Computerized Tribal IV-D Systems and Office Automation? 310.40 Section 310.40... COMPUTERIZED TRIBAL IV-D SYSTEMS AND OFFICE AUTOMATION Accountability and Monitoring Procedures for...

  1. A COMPUTERIZED OPERATOR SUPPORT SYSTEM PROTOTYPE

    Energy Technology Data Exchange (ETDEWEB)

    Thomas A. Ulrich; Roger Lew; Ronald L. Boring; Ken Thomas

    2015-03-01

    A computerized operator support system (COSS) is proposed for use in nuclear power plants to assist control room operators in addressing time-critical plant upsets. A COSS is a collection of technologies to assist operators in monitoring overall plant performance and making timely, informed decisions on appropriate control actions for the projected plant condition. A prototype COSS was developed in order to demonstrate the concept and provide a test bed for further research. The prototype is based on four underlying elements consisting of a digital alarm system, computer-based procedures, piping and instrumentation diagram system representations, and a recommender module for mitigation actions. The initial version of the prototype is now operational at the Idaho National Laboratory using the Human System Simulation Laboratory.

  2. Computerized tomographic evaluation of cerebral cysticercosis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bo Young; Lee, Mi Sook; Jeon, Doo Sung; Kim, Hong Soo; Rhee, Hak Song [Precbyterian Medical Center, Chonju (Korea, Republic of)

    1988-08-15

    Cerebral cysticercosis, unfortunately frequent in Korea, is a parastic disease in which man serve as the intermediate host of taenia solium. The larvae have a predilection for the central nervous system and can cause a variety of neurologic symptoms. The authors reviewed 19 cases of surgically proven cerebral cysticercosis and following results were obtained. 1. The most frequent age distribution was 5th and 6th decade and male to female ratio was 14:5. 2. The most frevalent involving site was cerebral parenchyme and following by ventricles. 3. Clinical manifestations were symtom and sign of increased ICP, seizure and focal neurological dificit. 4. It was assumed that computerized tomography was the procedure of choice for the diagnosis of these parasitic brain disease.

  3. A New Human-Machine Interfaces of Computer-based Procedure System to Reduce the Team Errors in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sa Kil; Sim, Joo Hyun; Lee, Hyun Chul [Korea Atomic Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room of Korea. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Organizational errors sometimes increase the likelihood of operator errors through the active failure pathway and, at the same time, enhance the possibility of adverse outcomes through defensive weaknesses. We incorporate the crew resource management as a representative approach to deal with the team factors of the human errors. We suggest a set of crew resource management training procedures under the unsafe environments where human errors can have devastating effects. We are on the way to develop alternative interfaces against team error in a condition of using a computer-based procedure system in a digitalized main control room. The computer-based procedure system is a representative feature of digitalized control room. In this study, we will propose new interfaces of computer-based procedure system to reduce feasible team errors. We are on the way of effectiveness test to validate whether the new interface can reduce team errors during operating with a computer-based procedure system in a digitalized control room.

  4. A New Human-Machine Interfaces of Computer-based Procedure System to Reduce the Team Errors in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Sa Kil; Sim, Joo Hyun; Lee, Hyun Chul

    2016-01-01

    In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room of Korea. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Organizational errors sometimes increase the likelihood of operator errors through the active failure pathway and, at the same time, enhance the possibility of adverse outcomes through defensive weaknesses. We incorporate the crew resource management as a representative approach to deal with the team factors of the human errors. We suggest a set of crew resource management training procedures under the unsafe environments where human errors can have devastating effects. We are on the way to develop alternative interfaces against team error in a condition of using a computer-based procedure system in a digitalized main control room. The computer-based procedure system is a representative feature of digitalized control room. In this study, we will propose new interfaces of computer-based procedure system to reduce feasible team errors. We are on the way of effectiveness test to validate whether the new interface can reduce team errors during operating with a computer-based procedure system in a digitalized control room

  5. Computerized ECT data analysis system

    International Nuclear Information System (INIS)

    Miyake, Y.; Fukui, S.; Iwahashi, Y.; Matsumoto, M.; Koyama, K.

    1988-01-01

    For the analytical method of the eddy current testing (ECT) of steam generator tubes in nuclear power plants, the authors have developed the computerized ECT data analysis system using a large-scale computer with a high-resolution color graphic display. This system can store acquired ECT data up to 15 steam generators, and ECT data can be analyzed immediately on the monitor in dialogue communication with a computer. Analyzed results of ECT data are stored and registered in the data base. This system enables an analyst to perform sorting and collecting of data under various conditions and obtain the results automatically, and also to make a plan of tube repair works. This system has completed the test run, and has been used for data analysis at the annual inspection of domestic plants. This paper describes an outline, features and examples of the computerized eddy current data analysis system for steam generator tubes in PWR nuclear power plants

  6. Quantitative inspection by computerized tomography

    International Nuclear Information System (INIS)

    Lopes, R.T.; Assis, J.T. de; Jesus, E.F.O. de

    1989-01-01

    The computerized Tomography (CT) is a method of nondestructive testing, that furnish quantitative information, that permit the detection and accurate localization of defects, internal dimension measurement, and, measurement and chart of the density distribution. The CT technology is much versatile, not presenting restriction in relation to form, size or composition of the object. A tomographic system, projected and constructed in our laboratory is presented. The applications and limitation of this system, illustrated by tomographyc images, are shown. (V.R.B.)

  7. Computerized accounting methods. Final report

    International Nuclear Information System (INIS)

    1994-01-01

    This report summarizes the results of the research performed under the Task Order on computerized accounting methods in a period from 03 August to 31 December 1994. Computerized nuclear material accounting methods are analyzed and evaluated. Selected methods are implemented in a hardware-software complex developed as a prototype of the local network-based CONMIT system. This complex has been put into trial operation for test and evaluation of the selected methods at two selected ''Kurchatov Institute'' Russian Research Center (''KI'' RRC) nuclear facilities. Trial operation is carried out since the beginning of Initial Physical Inventory Taking in these facilities that was performed in November 1994. Operation of CONMIT prototype system was demonstrated in the middle of December 1994. Results of evaluation of CONMIT prototype system features and functioning under real operating conditions are considered. Conclusions are formulated on the ways of further development of computerized nuclear material accounting methods. The most important conclusion is a need to strengthen computer and information security features supported by the operating environment. Security provisions as well as other LANL Client/Server System approaches being developed by Los Alamos National Laboratory are recommended for selection of software and hardware components to be integrated into production version of CONMIT system for KI RRC

  8. Computer assisted procedure maintenance

    International Nuclear Information System (INIS)

    Bisio, R.; Hulsund, J. E.; Nilsen, S.

    2004-04-01

    The maintenance of operating procedures in a NPP is a tedious and complicated task. Through the whole life cycle of the procedures they will be dynamic, 'living' documents. Several aspects of the procedure must be considered in a revision process. Pertinent details and attributes of the procedure must be checked. An organizational structure must be created and responsibilities allotted for drafting, revising, reviewing and publishing procedures. Available powerful computer technology provides solutions within document management and computerisation of procedures. These solutions can also support the maintenance of procedures. Not all parts of the procedure life cycle are equally amenable to computerized support. This report looks at the procedure life cycle in todays NPPs and discusses the possibilities associated with introduction of computer technology to assist the maintenance of procedures. (Author)

  9. Computerized tomography of orbital lesions

    International Nuclear Information System (INIS)

    Kuroiwa, Mayumi

    1981-01-01

    Two different types of computerized tomography scanners (CT scanner), i.e. a whole-body CT scanner (GE-CT/T8800) and a cerebral CT scanner (EMI-1010), were compared in the assessment and diagnosis of various orbital lesions. The whole-body CT scanner was found to be advantageous over the cerebral CT scanner for the following reasons: (1) CT images were more informative due to thinner slices associated with smaller-sized and larger-numbered matrices; (2) less artifacts derived from motion of the head or eyeball were produced because of the shorter scanning time; (3) with a devised gantry, coronal dissections were available whenever demanded. (author)

  10. DOE transporation programs - computerized techniques

    Energy Technology Data Exchange (ETDEWEB)

    Joy, D.S.; Johnson, P.E.; Fore, C.S.; Peterson, B.E.

    1983-01-01

    One of the major thrusts of the transportation programs at the Oak Ridge National Laboratory has been the development of a number of computerized transportation programs and data bases. The U.S. Department of Energy (DOE) is supporting these efforts through the Transportation Technology Center at Sandia National Laboratories and the Tranportation Operations and Traffic Management (TOTM) organization at DOE Headquarters. Initially this project was centered upon research activities. However, since these tools provide traffic managers and key personnel involved in preshipment planning with a unique resource for ensuring that the movement of radioactive materials can be properly accomplished, additional interest and support is coming from the operational side of DOE. The major accomplishments include the development of two routing models (one for rail shipments and the other for highway shipments), an emergency response assistance program, and two data bases containing pertinent legislative and regulatory information. This paper discusses the mose recent advances in, and additions to, these computerized techniques and provides examples of how they are used.

  11. Computerized index for teaching files

    International Nuclear Information System (INIS)

    Bramble, J.M.

    1989-01-01

    A computerized index can be used to retrieve cases from a teaching file that have radiographic findings similar to an unknown case. The probability that a user will review cases with a correct diagnosis was estimated with use of radiographic findings of arthritis in hand radiographs of 110 cases from a teaching file. The nearest-neighbor classification algorithm was used as a computer index to 110 cases of arthritis. Each case was treated as an unknown and inputted to the computer index. The accuracy of the computer index in retrieving cases with the same diagnosis (including rheumatoid arthritis, gout, psoriatic arthritis, inflammatory osteoarthritis, and pyrophosphate arthropathy) was measured. A Bayes classifier algorithm was also tested on the same database. Results are presented. The nearest-neighbor algorithm was 83%. By comparison, the estimated accuracy of the Bayes classifier algorithm was 78%. Conclusions: A computerized index to a teaching file based on the nearest-neighbor algorithm should allow the user to review cases with the correct diagnosis of an unknown case, by entering the findings of the unknown case

  12. Computerized Classification Testing with the Rasch Model

    Science.gov (United States)

    Eggen, Theo J. H. M.

    2011-01-01

    If classification in a limited number of categories is the purpose of testing, computerized adaptive tests (CATs) with algorithms based on sequential statistical testing perform better than estimation-based CATs (e.g., Eggen & Straetmans, 2000). In these computerized classification tests (CCTs), the Sequential Probability Ratio Test (SPRT) (Wald,…

  13. Computerizing primary schools in rural kenya

    DEFF Research Database (Denmark)

    Ogembo, J.G.; Ngugi, B.; Pelowski, Matthew John

    2012-01-01

    questions surrounding this endeavour. Specifically: 1.) what problems do rural schools actually want to solve with computerization; 2.) is computerization the most important priority for rural schools; 3.) are schools ready, in terms of infrastructure, for a computer in the classroom; or 4.) might...... and protective roofing -posing severe challenges to the outstanding conception of computerization. We consider these results and make recommendations for better adapting programs for computer introduction, and also suggest the use of new innovative devices, such as cell phones, which might already have overcome......This paper investigates the outstanding challenges facing primary schools' computerization in rural Kenya. Computerization of schools is often envisaged as a 'magic', or at least a particularly efficient, solution to many of the problems that developing countries face in improving primary school...

  14. Psychometrics behind Computerized Adaptive Testing.

    Science.gov (United States)

    Chang, Hua-Hua

    2015-03-01

    The paper provides a survey of 18 years' progress that my colleagues, students (both former and current) and I made in a prominent research area in Psychometrics-Computerized Adaptive Testing (CAT). We start with a historical review of the establishment of a large sample foundation for CAT. It is worth noting that the asymptotic results were derived under the framework of Martingale Theory, a very theoretical perspective of Probability Theory, which may seem unrelated to educational and psychological testing. In addition, we address a number of issues that emerged from large scale implementation and show that how theoretical works can be helpful to solve the problems. Finally, we propose that CAT technology can be very useful to support individualized instruction on a mass scale. We show that even paper and pencil based tests can be made adaptive to support classroom teaching.

  15. Chinese computerized nuclear data library

    International Nuclear Information System (INIS)

    Liang Qichang; Cai Dunjiu

    1996-01-01

    The Second Version of Chinese Evaluated Nuclear Data Library (CENDL-2) includes the complete neutron nuclear data sets of 54 important elements and isotopes used for nuclear science and engineering with the incident neutron energy from 10 -5 eV to 20 MeV, the international universal format ENDF/B-6 was adopted. Now, the Chinese Computerized nuclear data library has been developed and put into operation. That is, the users can make on-line use of the main data libraries for evaluated neutron reaction data in the world of EXFOR experimental nuclear data library on the terminal of computer via the perfect computer software system, carry out directly the nuclear engineering calculation or nuclear data evaluation, enjoy the use of the resource of our nuclear data libraries for their development of nuclear energy and nuclear technology applications

  16. Computerized evaluation of flood impact

    International Nuclear Information System (INIS)

    Gagnon, J.; Quach, T.T.; Marche, C.; Lessard, G.

    1998-01-01

    A computerized evaluation process for assessing the economic impacts of a potential dam failure is described. The DOMINO software, which was developed by Hydro-Quebec, takes into account flow data from dam break simulations of floods, the territory involved, plus the economic evaluations of the real estate and infrastructures affected. Some examples of software applications and impact evaluations are presented. The principal elements involved in estimating economic or other types of impacts induced by natural flooding or dam failure, are: (1) flow forecasting, (2) defining the contour of the involved territory, and (3) accounting for the various impacts identified in the affected zone. Owing to its wide range of functions and utilities, DOMINO has proven to be a very useful, user-friendly and portable decision-making tool. 5 refs., 6 tabs

  17. Patient radiation exposure in computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Pavlov, V [Meditsinska Akademiya, Sofia (Bulgaria)

    1980-01-01

    Radiation exposure to patients undergoing axial computerized tomography as a tool of neurological X-ray diagnostics was studied. Doses thereby delivered were compared with those from routine head films at X-ray tube parameters 200 W, 70 kV, and 70 cm target-to-patient distance. Radiation exposures were analyzed with a view to improving shielding and procedural techniques. Comparisons were made using LiF TLD measurements with an Alderson phantom (standard for axial computer tomography). Skin and intracranial space doses were compared using two computers, Siretom I and Siretom 2000, for various positionings: frontal, fronto-lateral, temporal, temporo-occipital, and occipital. In addition, patient body doses with or without shielding and doses to subjects attending sick children or restless adults were examined. Achievable protection was estimated for lead shields of 0.5 mm lead equivalent. It was concluded that radiation doses delivered to neurologic patients undergoing axial computer tomography are smaller than those resulting from conventional X-ray examinations.

  18. Computerized 50 liter volume calibration system

    International Nuclear Information System (INIS)

    Proffitt, T.H.

    1990-01-01

    A system has been designed for the Savannah River Site that will be used to calibrate product shipping containers. For accountability purposes, it is necessary that these containers be calibrated to a very high precision. The Computerized 50 Liter Volume Calibration System (CVCS), which is based on the Ideal Gas Law (IGL), will use reference volumes with precision of no less ±0.03%, and helium to calibrate the containers to have a total error of no greater than ±0.10%. A statistical interpretation of the system has given a theoretical total calculated error of ±0.08%. Tests with the system will be performed once fabrication is complete to experimentally verify the calculated error. Since the total error was calculated using the worst case scenario, the actual error should be significantly less than the calculated value. The computer controlled, totally automated system is traceable to the National Institute of Standards and Technology. The design, calibration procedure, and statistical interpretation of the system will be discussed. 1 ref

  19. Strategy generator in computerized accident management support system

    International Nuclear Information System (INIS)

    Sirola, M.

    1994-02-01

    An increased interest for research in the field of accident management of nuclear power plants can be noted. Several international programmes have been started in order to be able to understand the basic physical and chemical phenomena in accident conditions. A feasibility study has shown that it would be possible to design and develop a computerized support system for plant staff in accident situations. To achieve this goal the Halden Project has initiated a research programme on Computerized Accident Management Support (CAMS project). The aim is to utilize the capabilities of computerized tools to support the plant staff during the various accident stages. The system will include identification of the accident state, assessment of the future development of the accident and planning of accident mitigation strategies. A prototype is developed to support operators and the Technical Support Centre in decision making during serious accidents in nuclear power plants. A rule based system has been built to take care of the strategy generation. This system assists plant personnel in planning control proposals and mitigation strategies from normal operation to severe accident conditions. The idea of a safety objective tree and knowledge from the emergency procedures have been used. Future prediction requires good state identification of the plant status and some knowledge about the history of some critical variables. The information needs to be validated as well. Accurate calculations in simulators and a large database including all important information from the plant will help the strategy planning. (orig.). (40 refs., 20 figs.)

  20. Computerized tomography used as a routine procedure at postmortem investigations

    DEFF Research Database (Denmark)

    Leth, Peter Mygind

    2009-01-01

    not found at the CT-scanning. The cause of death could be established by CT in 31%, by autopsy in 74%, and by toxicology in 22%. CT combined with data from the inquest could establish the cause of death in a majority of deaths due to severe trauma, but only in a minority of deaths caused by disease...

  1. Reflecting on the ethical administration of computerized medical records

    Science.gov (United States)

    Collmann, Jeff R.

    1995-05-01

    This presentation examines the ethical issues raised by computerized image management and communication systems (IMAC), the ethical principals that should guide development of policies, procedures and practices for IMACS systems, and who should be involved in developing a hospital's approach to these issues. The ready access of computerized records creates special hazards of which hospitals must beware. Hospitals must maintain confidentiality of patient's records while making records available to authorized users as efficiently as possible. The general conditions of contemporary health care undermine protecting the confidentiality of patient record. Patients may not provide health care institutions with information about themselves under conditions of informed consent. The field of information science must design sophisticated systems of computer security that stratify access, create audit trails on data changes and system use, safeguard patient data from corruption, and protect the databases from outside invasion. Radiology professionals must both work with information science experts in their own hospitals to create institutional safeguards and include the adequacy of security measures as a criterion for evaluating PACS systems. New policies and procedures on maintaining computerized patient records must be developed that obligate all members of the health care staff, not just care givers. Patients must be informed about the existence of computerized medical records, the rules and practices that govern their dissemination and given the opportunity to give or withhold consent for their use. Departmental and hospital policies on confidentiality should be reviewed to determine if revisions are necessary to manage computer-based records. Well developed discussions of the ethical principles and administrative policies on confidentiality and informed consent and of the risks posed by computer-based patient records systems should be included in initial and continuing

  2. The evolution of computerized displays in accident management

    International Nuclear Information System (INIS)

    DeBor, J.

    1988-01-01

    Key regulations implemented by the NRC in 1982, which included requirements such as upgraded emergency operating procedures, detailed control room design reviews, the addition of a safety parameter display system, and the inclusion of a degreed shift technical advisor as part of the operating staff, have enabled the use of computerized displays to evolve as an integral part of accident management within each of the four main vendor groups. Problems, however, remain to be resolved in the area of technical content, information reliability, and rules for use in order to achieve the goal of more reliable accident management in nuclear power plants

  3. [Computerized medical record: deontology and legislation].

    Science.gov (United States)

    Allaert, F A; Dusserre, L

    1996-02-01

    Computerization of medical records is making headway for patients' follow-up, scientific research, and health expenses control, but it must not alter the guarantees provided to the patients by the medical code of ethics and the law of January 6, 1978. This law, modified on July 1, 1994, requires to register all computerized records of personal data and establishes rights to protect privacy against computer misdemeanor. All medical practitioners using computerized medical records must be aware that the infringement of this law may provoke suing in professional, civil or criminal court.

  4. Microcomputer Network for Computerized Adaptive Testing (CAT)

    Science.gov (United States)

    1984-03-01

    PRDC TR 84-33 \\Q.�d-33- \\ MICROCOMPUTER NETWOJlt FOR COMPUTERIZED ADAPTIVE TESTING ( CAT ) Baldwin Quan Thomas A . Park Gary Sandahl John H...ACCEIIION NO NPRDC TR 84-33 4. TITLE (-d Sul>tlllo) MICROCOMP UTER NETWORK FOR COMPUTERIZED ADA PTIVE TESTING ( CAT ) 1. Q B. uan T. A . Park...adaptive testing ( CAT ) Bayesian sequential testing 20. ABSTitACT (Continuo on ro•••• aide II noco .. _, _., ld-tlly ,.,. t.loclt _._.) DO Computerized

  5. A computerized legal information management system | Ohiagu ...

    African Journals Online (AJOL)

    A computerized legal information management system. ... process through the filling system using the survey research methodology. ... A framework for the design and implementation of a legal information management system was presented.

  6. Computerizing marine biota: a rational approach

    Digital Repository Service at National Institute of Oceanography (India)

    Chavan, V.S.; Chandramohan, D.; Parulekar, A.H.

    Data on marine biota while being extensive are also patchy and scattered; thus making retrieval and dissemination of information time consuming. This emphasise the need for computerizing information on marine biota with the objective to collate...

  7. Computerized Interpretation of Dynamic Breast MRI

    National Research Council Canada - National Science Library

    Chen, Weijie; Giger, Maryellen Lissak

    2005-01-01

    ... and prognosis of breast cancer. The research involves investigation of automatic methods for image artifacts correction, tumor segmentation, and extraction of computerized features that help distinguish between benign and malignant lesions...

  8. Strategies for Controlling Item Exposure in Computerized Adaptive Testing with the Generalized Partial Credit Model

    Science.gov (United States)

    Davis, Laurie Laughlin

    2004-01-01

    Choosing a strategy for controlling item exposure has become an integral part of test development for computerized adaptive testing (CAT). This study investigated the performance of six procedures for controlling item exposure in a series of simulated CATs under the generalized partial credit model. In addition to a no-exposure control baseline…

  9. Computerized transverse tomography of vascular lesions of the brain. II. Aneurysms

    International Nuclear Information System (INIS)

    Pressman, B.D.; Gilbert, G.E.; Davis, D.O.

    1975-01-01

    Computerized transverse tomography (CTT) is an excellent screening examination for intracerebral disease. Unfortunately, the detection rate of small aneurysms by this procedure is not high. Nevertheless, CTT may be useful in aneurysm cases since it may indicate the need for further evaluation in patients with associated hematomas, encephalomalacia, or ventricular dilatation, even if the aneurysm itself is not delineated. (U.S.)

  10. Computerized provider order entry systems.

    Science.gov (United States)

    2001-01-01

    Computerized provider order entry (CPOE) systems are designed to replace a hospital's paper-based ordering system. They allow users to electronically write the full range of orders, maintain an online medication administration record, and review changes made to an order by successive personnel. They also offer safety alerts that are triggered when an unsafe order (such as for a duplicate drug therapy) is entered, as well as clinical decision support to guide caregivers to less expensive alternatives or to choices that better fit established hospital protocols. CPOE systems can, when correctly configured, markedly increase efficiency and improve patient safety and patient care. However, facilities need to recognize that currently available CPOE systems require a tremendous amount of time and effort to be spent in customization before their safety and clinical support features can be effectively implemented. What's more, even after they've been customized, the systems may still allow certain unsafe orders to be entered. Thus, CPOE systems are not currently a quick or easy remedy for medical errors. ECRI's Evaluation of CPOE systems--conducted in collaboration with the Institute for Safe Medication Practices (ISMP)--discusses these and other related issues. It also examines and compares CPOE systems from three suppliers: Eclipsys Corp., IDX Systems Corp., and Siemens Medical Solutions Health Services Corp. Our testing focuses primarily on the systems' interfacing capabilities, patient safeguards, and ease of use.

  11. Computerized automated remote inspection system

    International Nuclear Information System (INIS)

    The automated inspection system utilizes a computer to control the location of the ultrasonic transducer, the actual inspection process, the display of the data, and the storage of the data on IBM magnetic tape. This automated inspection equipment provides two major advantages. First, it provides a cost savings, because of the reduced inspection time, made possible by the automation of the data acquisition, processing, and storage equipment. This reduced inspection time is also made possible by a computerized data evaluation aid which speeds data interpretation. In addition, the computer control of the transducer location drive allows the exact duplication of a previously located position or flaw. The second major advantage is that the use of automated inspection equipment also allows a higher-quality inspection, because of the automated data acquisition, processing, and storage. This storage of data, in accurate digital form on IBM magnetic tape, for example, facilitates retrieval for comparison with previous inspection data. The equipment provides a multiplicity of scan data which will provide statistical information on any questionable volume or flaw. An automatic alarm for location of all reportable flaws reduces the probability of operator error. This system has the ability to present data on a cathode ray tube as numerical information, a three-dimensional picture, or ''hard-copy'' sheet. One important advantage of this system is the ability to store large amounts of data in compact magnetic tape reels

  12. Computerized Adaptive Personality Testing: A Review and Illustration With the MMPI-2 Computerized Adaptive Version.

    Science.gov (United States)

    Forbey, Johnathan D.; Ben-Porath, Yossef S.

    2007-01-01

    Computerized adaptive testing in personality assessment can improve efficiency by significantly reducing the number of items administered to answer an assessment question. Two approaches have been explored for adaptive testing in computerized personality assessment: item response theory and the countdown method. In this article, the authors…

  13. The computerized OMAHA system in microsoft office excel.

    Science.gov (United States)

    Lai, Xiaobin; Wong, Frances K Y; Zhang, Peiqiang; Leung, Carenx W Y; Lee, Lai H; Wong, Jessica S Y; Lo, Yim F; Ching, Shirley S Y

    2014-01-01

    The OMAHA System was adopted as the documentation system in an interventional study. To systematically record client care and facilitate data analysis, two Office Excel files were developed. The first Excel file (File A) was designed to record problems, care procedure, and outcomes for individual clients according to the OMAHA System. It was used by the intervention nurses in the study. The second Excel file (File B) was the summary of all clients that had been automatically extracted from File A. Data in File B can be analyzed directly in Excel or imported in PASW for further analysis. Both files have four parts to record basic information and the three parts of the OMAHA System. The computerized OMAHA System simplified the documentation procedure and facilitated the management and analysis of data.

  14. Evaluation of brain scintigraphy and computerized tomography

    International Nuclear Information System (INIS)

    Cavailloles, F.; Dairou, R.; Desbleds, M.T.; Benoit, C.; Larmande, P.; Bok, B.; Alperovitch, A.

    1983-01-01

    In order to assess the clinical usefulness of brain computerized tomography and radionuclide scan, a prospective study was performed on a series of 554 patients. The detection rate was assessed as well as the identification rate of lesions. In addition, the usefulness of both tests was appreciated subjectively by two neurologists reviewing the patients' files. Both give reasonably similar results: computerized tomography is superior to radionuclide scan in the diagnosis of tumors and intracerebral hematomas, the radionuclide scan being slightly superior in the diagnosis of purely ischemic CVA and subdural hematomas. The superiority which was subjectively conceded to computerized tomography was greater than that objectively demonstrated. However, clinical usefulness of computerized tomography was judged important in only 50% of the cases. Moreover, to request both computerized tomography and radionuclide scan appeared as having no interest in 83% of the cases. In that series, the diagnostic hypotheses were in agreement with the final diagnosis in 88% of the cases. Bias encountered in this type of studies are discussed [fr

  15. Computerized occlusal analysis in bruxism

    Directory of Open Access Journals (Sweden)

    Lazić Vojkan

    2006-01-01

    Full Text Available Introduction. Sleep bruxism as nocturnal parafunction, also known as tooth grinding, is the most common parasomnia (sleep disorder. Most tooth grinding occurs during rapid eye movement - REM sleep. Sleep bruxism is an oral habit characterized by rhythmic activity of the masticatory muscles (m. masseter that causes forced contact between dental surfaces during sleep. Sleep bruxism has been associated with craniomandibular disorders including temporomandibular joint discomfort, pulpalgia, premature loss of teeth due to excessive attrition and mobility, headache, muscle ache, sleep interruption of an individual and problems with removable and fixed denture. Basically, two groups of etiological factors can be distinguished, viz., peripheral (occlusal factors and central (pathophysiological and psychological factors. The role of occlusion (occlusal discrepancies as the causative factor is not enough mentioned in relation to bruxism. Objective. The main objective of this paper was to evaluate the connection between occlusal factors and nocturnal parafunctional activities (occlusal disharmonies and bruxism. Method. Two groups were formed- experimental of 15 persons with signs and symptoms of nocturnal parafunctional activity of mandible (mean age 26.6 years and control of 42 persons with no signs and symptoms of bruxism (mean age 26.3 yrs.. The computerized occlusal analyses were performed using the T-Scan II system (Tekscan, Boston, USA. 2D occlusograms were analyzed showing the occlusal force, the center of the occlusal force with the trajectory and the number of antagonistic tooth contacts. Results. Statistically significant difference of force distribution was found between the left and the right side of the arch (L%-R% (t=2.773; p<0.02 in the group with bruxism. The difference of the centre of occlusal force - COF trajectory between the experimental and control group was not significant, but the trajectory of COF was longer in the group of

  16. Computerized tomography in orthopaedics and traumatology

    International Nuclear Information System (INIS)

    Boettger, E.; Heckl, R.; Rehabilitations-Krankenhaus Langensteinbach, Karlsbad

    1981-01-01

    Computerized tomography in traumatology is the selected method for the indications mentioned, so that angiographic investigations are only necessary in exceptional cases. Computerized tomography is also better than other methods when diagnozing soft part tumours, however, angiography is still indicated preoperatively for individual cases. CT is only good as additional help to conventional diagnostics with bone tumours. The differential diagnosis cysts-tumour is possible using contrast medium injections. The frequently large soft part share of tumours is recognizable with osteolytic tumours so that a better irradiation and operation planning can be effected. Diseases in the spinal canal can only be assessed with reservation using modern equipment. Lumbar dislocations of the disk can mostly not be sufficiently determined. Perivertebral abscesses can be certainly detected using computerized tomography. This is particularly so for abscesses prior to calcification. (orig.) [de

  17. Guidelines for the presentation of emergency operating procedures using advanced information technology

    International Nuclear Information System (INIS)

    Green, M.; Hollnagel, E.; Niwa, Yuji

    1994-01-01

    New methods of information presentation and interface design are changing the conditions for work in the modern NPP control room. One area receiving considerable attention is that of Emergency Operating Procedures (EOP). Conventionally such procedures are presented using hard copy manuals; however, development in IT means that there are new opportunities for the computerization of such procedures. This paper reports on the development of human factors guidelines for the computerized presentation of EOPs. After identifying the principle stages in the transition from procedures as documents to fully automated procedures, computerised procedure presentation is briefly discussed. Guidelines for the presentation of such procedures are outlined starting with the high level goals for guidelines themselves. Such goals also constitute the criteria against which the computerized procedures are measured during implementation. Six dimensions describing computerized procedure presentation are presented and two are explore in more detail by identifying points along each dimension that characterize different levels of IT sophistication. (author). 8 refs, 1 tab

  18. Computerization of the safeguards analysis decision process

    International Nuclear Information System (INIS)

    Ehinger, M.H.

    1990-01-01

    This paper reports that safeguards regulations are evolving to meet new demands for timeliness and sensitivity in detecting the loss or unauthorized use of sensitive nuclear materials. The opportunities to meet new rules, particularly in bulk processing plants, involve developing techniques which use modern, computerized process control and information systems. Using these computerized systems in the safeguards analysis involves all the challenges of the man-machine interface experienced in the typical process control application and adds new dimensions to accuracy requirements, data analysis, and alarm resolution in the regulatory environment

  19. Computerized tomography in the diagnosis of hyperparathyroidism

    International Nuclear Information System (INIS)

    Sobota, J.; Girl, J.; Sotornik, I.; Kocandrle, V.

    1990-01-01

    Long-term experience in the application of computerized tomography to the diagnosis of hyperparathyroidism is summarized. Based on a large number of examinations (164) of parathyroid glands associated with the possibility of verification and comparison with the results of ultrasonography and other imaging methods, the potential of computerized tomography in the diagnosis of hyperparathyroidism and its advantages and limitations are summarized. It is concluded that owing to its high diagnostic precision, this technique can be regarded reliable in detecting enlarged parathyroid glands. (author). 11 figs., 1 tab., 19 refs

  20. Feasibility study for a computerized emergency preparedness simulation facility

    International Nuclear Information System (INIS)

    Gerhardstein, L.H.; Schroeder, J.O.; Sandusky, W.F.

    1979-11-01

    This report details the feasibility of a computerized Emergency Preparedness Simulation Facility (EPSF) for use by the Nuclear Regulatory Commission (NRC). The proposed facility would be designed to provide the NRC and other federal, state, and local government agencies with a capability to formulate, test, and evaluate the Emergency Preparedness Plans (EPP) which local and state agencies have/will establish for use during nuclear emergencies. In cases of any state emergency (including a nuclear emergency), high level state government officials will direct emergency procedures and insure that state and local emergency teams carry out tasks which have been established in their EPP. When an emergency exists, rapid mobilization of emergency teams, efficient communication, and effective coordination of individual team efforts is essential to safety, preservation of property, and overall public welfare. Current EPP evaluation procedures are qualitative in nature and while they do compare emergency drill performance with the EPP, the nature of the drills often does not provide enough realism to actual emergency conditions. Automated simulation of real emergency conditions using modern computer equipment and programming techniques will provide the NRC emergency evaluation teams a simulated environment which closely approximates conditions which would actually exist during a real emergency. In addition, the computer can be used to collect and log performance and event data which will aid the evaluation team in making assessments of the state or local area's EPP and their Emergency Preparedness Teams performance during emergency drills. Overall, a computerized EPSF can improve drill testing and evaluation efficiency, provide approximate emergency condition realism, and improve public awareness of local emergency procedures

  1. A Computerized Version of the Scrambled Sentences Test

    Directory of Open Access Journals (Sweden)

    Roberto Viviani

    2018-01-01

    Full Text Available The scrambled sentences test (SST, an experimental procedure that involves participants writing down their cognitions, has been used to elicit individual differences in depressiveness and vulnerability to depression. We describe here a modification of the SST to adapt it to computerized administration, with a particular view of its use in large samples and functional neuroimaging applications. In a first study with the computerized version, we reproduce the preponderance of positive cognitions in the healthy and the inverse association of these cognitions with individual measures of depressiveness. We also report a tendency of self-referential cognitions to elicit higher positive cognition rates. In a second study, we describe the patterns of neural activations elicited by emotional and neutral sentences in a functional neuroimaging study, showing that it replicates and extends previous findings obtained with the original version of the SST. During the formation of emotional cognitions, ventral areas such as the ventral anterior cingulus and the supramarginal gyrus were relatively activated. This activation pattern speaks for the recruitment of mechanisms coordinating motivational and associative processes in the formation of value-based decisions.

  2. Robinson's Computerized Strabismus Model Comes of Age

    NARCIS (Netherlands)

    H.J. Simonsz (Huib); H. Spekreijse (Henk)

    1996-01-01

    textabstractIn this article we review our further development of D.A. Robinson's computerized strabismus model. First, an extensive literature study has been carried out to get more accurate data on the anatomy of the average eye and the eye muscles, and about how these vary with age and with

  3. Computerized management information systems and organizational structures

    Science.gov (United States)

    Zannetos, Z. S.; Sertel, M. R.

    1970-01-01

    The computerized management of information systems and organizational structures is discussed. The subjects presented are: (1) critical factors favoring centralization and decentralization of organizations, (2) classification of organizations by relative structure, (3) attempts to measure change in organization structure, and (4) impact of information technology developments on organizational structure changes.

  4. Implementation of a Computerized Maintenance Management System

    Science.gov (United States)

    Shen, Yong-Hong; Askari, Bruce

    1994-01-01

    A primer Computerized Maintenance Management System (CMMS) has been established for NASA Ames pressure component certification program. The CMMS takes full advantage of the latest computer technology and SQL relational database to perform periodic services for vital pressure components. The Ames certification program is briefly described and the aspects of the CMMS implementation are discussed as they are related to the certification objectives.

  5. The limited angle problem in computerized tomography

    International Nuclear Information System (INIS)

    Louis, A.K.

    1984-01-01

    Fast reconstruction formulae in X-ray computerized tomography demand the directions, in which the measurements are taken, to be equally distributed over the whole circle. In many applications data can only be provided in a restricted range. Here the intrinsic difficulties are studied by giving a singular value decomposition of the Radon transform in a restricted range. Practical limitations are deduced. (orig.)

  6. Ethics and the Computerization of Pharmacy.

    Science.gov (United States)

    McCarthy, Robert L.; Perrolle, Judith A.

    1991-01-01

    The current and potential impact of computerization on pharmacy practice is discussed, focusing on ethical dilemmas in the pharmacist-patient relationship, confidentiality of records, and the role of artificial intelligence in decision making about drug therapy. Case studies for use by teachers of pharmaceutical ethics are provided. (Author/MSE)

  7. Individual Differences in Computerized Adaptive Testing.

    Science.gov (United States)

    Kim, JinGyu

    Research on the major computerized adaptive testing (CAT) strategies is reviewed, and some findings are reported that examine effects of examinee demographic and psychological characteristics on CAT strategies. In fixed branching strategies, all examinees respond to a common routing test, the score of which is used to assign examinees to a…

  8. Computerized management support for swine breeding farms

    NARCIS (Netherlands)

    Huirne, R.B.M.

    1990-01-01

    1. INTRODUCTION

    The investigations described in this thesis have been directed towards computerized management support for swine breeding farms, focused on sow productivity and profitability. The study is composed of three basic parts: (1) basic description and

  9. Computerized three-dimensional normal atlas

    International Nuclear Information System (INIS)

    Mano, Isamu; Suto, Yasuzo; Suzuki, Masataka; Iio, Masahiro.

    1990-01-01

    This paper presents our ongoing project in which normal human anatomy and its quantitative data are systematically arranged in a computer. The final product, the Computerized Three-Dimensional Normal Atlas, will be able to supply tomographic images in any direction, 3-D images, and coded information on organs, e.g., anatomical names, CT numbers, and T 1 and T 2 values. (author)

  10. The Computerized Reference Department: Buying the Future.

    Science.gov (United States)

    Kriz, Harry M.; Kok, Victoria T.

    1985-01-01

    Basis for systematic computerization of academic research library's reference, collection development, and collection management functions emphasizes productivity enhancement for librarians and support staff. Use of microcomputer and university's mainframe computer to develop applications of database management systems, electronic spreadsheets,…

  11. Computerized system for measuring cerebral metabolism

    International Nuclear Information System (INIS)

    McGlone, J.S.; Hibbard, L.S.; Hawkins, R.A.; Kasturi, R.

    1987-01-01

    A computerized stereotactic measurement system for evaluating rat brain metabolism was developed to utilize the large amount of data generated by quantitative autoradiography. Conventional methods of measurement only analyze a small percent of these data because these methods are limited by instrument design and the subjectiveness of the investigator. However, a computerized system allows digital images to be analyzed by placing data at their appropriate three-dimensional stereotactic coordinates. The system automatically registers experimental data to a standard three-dimensional image using alignment, scaling, and matching operations. Metabolic activity in different neuronal structures is then measured by generating digital masks and superimposing them on to experimental data. Several experimental data sets were evaluated and it was noticed that the structures measured by the computerized system, had in general, lower metabolic activity than manual measurements had indicated. This was expected because the computerized system measured the structure over its volume while the manual readings were taken from the most active metabolic area of a particular structure

  12. How will computerization revolutionize managed care?

    Science.gov (United States)

    Trabin, T

    1994-01-01

    Computerization of behavioral health care information systems is revolutionizing how payors, managed care companies, and providers exchange information. In this article, an imaginary scenario is depicted of how patient data will be accessed and communicated to facilitate care management of behavioral health care services in the near future.

  13. Geometrical efficiency in computerized tomography: generalized model

    International Nuclear Information System (INIS)

    Costa, P.R.; Robilotta, C.C.

    1992-01-01

    A simplified model for producing sensitivity and exposure profiles in computerized tomographic system was recently developed allowing the forecast of profiles behaviour in the rotation center of the system. The generalization of this model for some point of the image plane was described, and the geometrical efficiency could be evaluated. (C.G.C.)

  14. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

    The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

  15. 39 CFR 501.15 - Computerized Meter Resetting System.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Computerized Meter Resetting System. 501.15... AND DISTRIBUTE POSTAGE EVIDENCING SYSTEMS § 501.15 Computerized Meter Resetting System. (a) Description. The Computerized Meter Resetting System (CMRS) permits customers to reset their postage meters at...

  16. Computerized asset management and maintenance systems in ST

    CERN Document Server

    Sánchez-Corral, E

    1999-01-01

    The ST division manages and therefore maintains the CERN technical installations. A maintenance database application exists for every technical domain. A total of six different databases were built during the last 10 years and are based on the RAPIER maintenance program. As the Computerized Asset Management and Maintenance Systems (CAMMS) technology has evolved, the RAPIER system has become obsolete. Therefore we are forced to migrate to its latest version, MP5, before the year 2000. The migration path must be defined, leading from the current situation to a fully operational MP5 application. The major elements of each migration path consist in determining the functionality to use, defining the operation of it, adapting and/or creating procedures, converting data and providing training. A migration is always a process of change. The migration presents a unique opportunity to evaluate the current implementations, adapt them to the requirements and exploit the new features offered. Obsolete data and inconsisten...

  17. Computerized tomography using water to render the gastrointestinal tract opaque

    International Nuclear Information System (INIS)

    Gaa, J.; Deininger, H.K.; Georgi, M.

    1993-01-01

    An account is given of the technical procedure and results of computerized tomography in the examination of various gastrointestinal disorders using water as an oral and rectal contrast medium. The experience gained so far points to the fact that water as a contrast medium is mainly suitable in the preoperative staging of malignant gastric and colorectal tumours. The rectal injection of water further appears to be favourable in investigations for recidivation following deep anterior resection without impairment of the excretory functions. Our own results were contrary to the findings of other authors in that we had no difficulty in visualizing distal sections of the small intestine in patients suffering from Crohn's disease. The use of water as a contrast medium can, however, not be recommended in the presence of intra-abdominal abscesses, ascites or cystic tumours, as such changes cannot clearly be differentiated from intestinal loops filled with water. (orig./MG) [de

  18. Computerized engineering logic for procurement and dedication processes

    International Nuclear Information System (INIS)

    Tulay, M.P.

    1996-01-01

    This paper summarizes the work performed for designing the system and especially for calculating on-line expected performance and gives some significant results. In an attempt to better meet the needs of operations and maintenance organizations, many nuclear utility procurement engineering groups have simplified their procedures, developed on-line tools for performing the specification of replacement items, and developed relational databases containing part-level information necessary to automate the procurement process. Although these improvements have helped to reduce the engineering necessary to properly specify and accept/dedicate items for nuclear safety-related applications, a number of utilities have recognized that additional long-term savings can be realized by integrating a computerized logic to assist technical procurement engineering personnel

  19. Computerized planning system for nuclear power plant evaluation

    International Nuclear Information System (INIS)

    Bonczek, R.H.; Holsapple, C.W.; Whinston, A.B.

    1976-01-01

    A computerized system is described for information storage and query processing adapted to complex socio-technological issues. The system is referred to as GPLAN (Generalized Planning System) and can accommodate both qualitative (verbal) and quantitative data. The issue illustrated is the construction of a nuclear power plant, and involves interdisciplinary research and planning. The system's outstanding features are the use of the network variety of data base, the selective retrieval of any configuration of data from a particular network structure, automatic execution of any desired application program from a standard or special library of applications, user interface with a data base and applications by submitting English-like, non-procedural queries, and generality which allows tailoring to specific applications and provides a basis for integration of planning and research activities. The system is general and can be used for a wide variety of socio-technological issues which involve complex data relationships

  20. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual

    International Nuclear Information System (INIS)

    Gilbert, B.G.; Reece, W.J.; Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.

    1990-12-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal computer. NUCLARR can furnish the end user with data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented is a five-volume series of reports. Volume V: Data Manual provides a hard-copy representation of all data and related information available within the NUCLARR system software. This document is organized in three sections. Part 1 is the summary description, which presents an overview of the NUCLARR system and data processing procedures. Part 2 contains all data and information relevant to the human error probability (HEP) data side of NUCLARR. Data and information for the hardware component failure data (HCFD) side are presented in Part 3. 7 refs

  1. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR)

    International Nuclear Information System (INIS)

    Gilbert, B.G.; Reece, W.J.; Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.

    1990-12-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal computer. NUCLARR can furnish the end user with data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. Volume 5: Data Manual provides a hard-copy representation of all data and related information available within the NUCLARR system software. This document is organized in three sections. Part 1 is the summary description, which presents an overview of the NUCLARR system and data processing procedures. Part 2 contains all data and information relevant to the human error probability (HEP) data side of NUCLARR. Data and information for the hardware component failure data (HCFD) side are presented in Part 3. 7 refs

  2. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual

    International Nuclear Information System (INIS)

    Gilbert, B.G.; Reece, W.J.; Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.

    1990-12-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal computer. NUCLARR can furnish the end user with data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. Volume V: Data Manual provides a hard-copy representation of all data and related information available within the NUCLARR system software. This document is organized in three sections. Part 1 is the summary description, which presents an overview of the NUCLARR system and data processing procedures. Part 2 contains all data and information relevant to the human error probability (HEP) side of NUCLARR. Data and information for the hardware component failure data (HCFD) side are presented in Part 3. 7 refs., 1 fig

  3. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Summary description

    International Nuclear Information System (INIS)

    Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.; Groh, M.R.; Gentillon, C.D.; Gilbert, B.G.; Reece, W.J.

    1990-05-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automate data base management system for storing and processing human error probability and hardware component failure rate data. The NUCLARR system software resides on an IBM (or compatible) personal microcomputer. NUCLARR can be accessed by the end user to furnish data suitable for input in human and/or hardware reliability analysis to support a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. This document Volume 1, of this series is the Summary Description, which presents an overview of the data management system, including a description of data collection, data qualification, data structure, and taxonomies. Programming activities, procedures for processing data, a user's guide, and hard copy data manual are presented in Volumes 2 through 5, NUREG/CR-4639

  4. Computerized automatic tip scanning operation

    International Nuclear Information System (INIS)

    Nishikawa, K.; Fukushima, T.; Nakai, H.; Yanagisawa, A.

    1984-01-01

    In BWR nuclear power stations the Traversing Incore Probe (TIP) system is one of the most important components in reactor monitoring and control. In previous TIP systems, however, operators have suffered from the complexity of operation and long operation time required. The system presented in this paper realizes the automatic operation of the TIP system by monitoring and driving it with a process computer. This system significantly reduces the burden on customer operators and improves plant efficiency by simplifying the operating procedure, augmenting the accuracy of the measured data, and shortening operating time. The process computer is one of the PODIA (Plant Operation by Displayed Information Automation) systems. This computer transfers control signals to the TIP control panel, which in turn drives equipment by microprocessor control. The process computer contains such components as the CRT/KB unit, the printer plotter, the hard copier, and the message typers required for efficient man-machine communications. Its operation and interface properties are described

  5. Computerized tomography-guided neurolytic splanchnic nerve block

    International Nuclear Information System (INIS)

    Henriquet, Franco; De Martini, Giuseppe; Roy, Maria Teresa; Pretrolesi, Fabio; Martinoli, Carlo; Cariati, Maurizio; Fiorentini, Franco.

    1997-01-01

    Computerized tomography-guided neurolytic splanchnic nerve block is a technique for relieving abdominal cancer pain; the goal is the alcoholic neurolytic interruption of the sensitive structures in retroperitoneal space. Computerized tomography yields accurate anatomical detailing and the course for needle placement and alcohol spread. January, 1993, to July, 1996, twenty-one bilateral splanchnic nerve blocks were performed through the posterior access. Forty-eight hours after alcoholism. 14 patients (66%) had complete pain regression; 52% of the patients needed no analgesics for 6 to 54 days and only 9 patients (42%) needed another low opioid therapy. Complications included hypotension and diarrhea in all cases. One had a cardiac arrest and diet 8 days after the procedure. There were no other complications. The whole procedure usually lasted 60 min (range: 45 to 90 min). Splanchnic nerve neurolysis is a useful treatment in the patients with severe chronic abdominal pain. It is used as a second line treatment when large lesions change celia anatomy and complicate the percutaneous block of the celiac plexus. Endosulfan, Malathion and Methyl parathion, on the metabolic rate of the estuarine clam, Villorita cyprinoides var. cochinensis, have been investigated. The animals exposed to the lower sublethal concentrations of Endosulfan, Malthion and Methyl parathion consumed oxygen at the rate of 1.60, 1.98 and 2.09 ml. 0 2 g - 1 h -1 respectively, while at the higher concentrations of the pesticides, consumption of oxygen by the animal dropped to nearly half the control value. When compared to Malathion and Methyl parathion. Endosulfan induced animals recorded a greater reduction in her percentage deviation (from control) of oxygen consumption, possibly due to hypoxia induced by the pollutants

  6. Computerized Virtual Reality Simulation in Preclinical Dentistry: Can a Computerized Simulator Replace the Conventional Phantom Heads and Human Instruction?

    Science.gov (United States)

    Plessas, Anastasios

    2017-10-01

    In preclinical dental education, the acquisition of clinical, technical skills, and the transfer of these skills to the clinic are paramount. Phantom heads provide an efficient way to teach preclinical students dental procedures safely while increasing their dexterity skills considerably. Modern computerized phantom head training units incorporate features of virtual reality technology and the ability to offer concurrent augmented feedback. The aims of this review were to examine and evaluate the dental literature for evidence supporting their use and to discuss the role of augmented feedback versus the facilitator's instruction. Adjunctive training in these units seems to enhance student's learning and skill acquisition and reduce the required faculty supervision time. However, the virtual augmented feedback cannot be used as the sole method of feedback, and the facilitator's input is still critical. Well-powered longitudinal randomized trials exploring the impact of these units on student's clinical performance and issues of cost-effectiveness are warranted.

  7. Computerized real-time materials accountability system for safeguards material control

    International Nuclear Information System (INIS)

    Spencer, W.F.; Affel, R.G.; Austin, H.C.; Nichols, J.P.; Stoutt, B.H.; Wachter, J.W.

    1975-01-01

    A real-time, computer-based system is described which provides safeguards material control at the Oak Ridge National Laboratory. Originally installed in 1972 to provide computerized real-time fissile materials accountability for criticality control purposes, the system has been expanded to provide accountability of all source and nuclear materials (SNM) and to utilize the on-line inventory files in support of the Laboratory physical protection and surveillance procedures. (auth)

  8. Computerized tomography in atypical Pott's disease

    International Nuclear Information System (INIS)

    Cabrera, M.N.B.; Wang, E.H.M.

    1993-01-01

    Classical Pott's disease is described as a two-vertebrae disease with the destruction of the intervening invertebral disc. Computerized tomography has been used in the differential diagnosis of spine infections and neoplasms. We reviewed CT scans of patients seen at the Philippine General Hospital over a two-year period with atypical presentations of atypical tuberculous spondylitis. We used the computerized tomography findings described as characteristic of classical Pott's disease as criteria in evaluating the CT scans of patients diagnosed to have Atypical Pott's Disease. Although the number of patients prevented sensitivity and specificity studies to be done, our results strongly suggest that the same CT criteria used to diagnose Classical Pott's Disease may also be used to diagnose Pott's disease in its atypical form. (Author.). 13 refs

  9. Computerized flow monitors detect small kicks

    Energy Technology Data Exchange (ETDEWEB)

    McCann, D.; White, D. (Sedco Forex, Paris (FR))

    1992-02-24

    This paper reports on a smart alarm system installed on a number of offshore rigs and one land rig which can detect kicks more quickly than conventional systems. This rapid kick detection improves rig safety because the smaller the detected influx, the easier it is to control the well. The extensive computerized monitoring system helps drilling personnel detect fluid influxes and fluid losses before the changes in flow would normally be apparent.

  10. The EORTC emotional functioning computerized adaptive test

    DEFF Research Database (Denmark)

    Gamper, Eva-Maria; Grønvold, Mogens; Petersen, Morten Aa

    2014-01-01

    The European Organisation for Research and Treatment of Cancer (EORTC) Quality of Life Group is currently developing computerized adaptive testing measures for the Quality of Life Questionnaire Core-30 (QLQ-C30) scales. The work presented here describes the development of an EORTC item bank for e...... for emotional functioning (EF), which is one of the core domains of the QLQ-C30....

  11. 10 years of computerized tomography reviewed

    International Nuclear Information System (INIS)

    Duemmling, K.

    1984-01-01

    The history and some highlights of computerized tomography are reviewed. The various technologies employed in the course of CT development are described along with the limitations that led to their disappearance. The problems still to be solved in medicine, the increasing influence of nuclear magnetic resonance, and some scientific aspects have opened up new lines of development which are briefly mentioned. (orig./WU) [de

  12. Computerized reactor pressure vessel materials information system

    International Nuclear Information System (INIS)

    Strosnider, J.; Monserrate, C.; Kenworthy, L.D.; Tether, C.D.

    1980-10-01

    A computerized information system for storage and retrieval of reactor pressure vessel materials data was established, as part of Task Action Plan A-11, Reactor Vessel Materials Toughness. Data stored in the system are necessary for evaluating the resistance of reactor pressure vessels to flaw-induced fracture. This report includes (1) a description of the information system; (2) guidance on accessing the system; and (3) a user's manual for the system

  13. Computerized reactor power regulation with logarithmic controller

    International Nuclear Information System (INIS)

    Gossanyi, A.; Vegh, E.

    1982-11-01

    A computerized reactor control system has been operating at a 5 MW WWR-SM research reactor in the Central Research Institute for Physics, Budapest, for some years. This paper describes the power controller used in the SPC operating mode of the system, which operates in a 5-decade wide power range with +-0.5% accuracy. The structure of the controller easily limits the minimal reactor period and produces a reactor transient with constant period if the power demand changes. (author)

  14. COMPRESS - a computerized reactor safety system

    International Nuclear Information System (INIS)

    Vegh, E.

    1986-01-01

    The computerized reactor safety system, called COMPRESS, provides the following services: scram initiation; safety interlockings; event recording. The paper describes the architecture of the system and deals with reliability problems. A self-testing unit checks permanently the correct operation of the independent decision units. Moreover the decision units are tested by short pulses whether they can initiate a scram. The self-testing is described in detail

  15. Computerized UT system for stud bolt

    International Nuclear Information System (INIS)

    Kisanuki, T.; Uchida, K.; Fushimi, T.; Onda, K.

    1988-01-01

    Cracking of stud bolts used in steam turbine casing, valve and pressure vessel has caused concern regarding the safety and reliability of power plants. In order to detect harmful cracks in early state, the improvement of UT technique is required. As regarding the ultrasonic inspection technique, a longitudinal beam technique and/or an angle beam technique are generally used. The authors report their development of a computerized UT system for bolt inspection and improvement of the angle beam technique

  16. Computerized tomography of gall bladder cancer

    International Nuclear Information System (INIS)

    Todua, F.I.; Karmazanovskij, G.G.

    1989-01-01

    The authors have summed up the experience in the use of computerized tomography (CT) in diagnosis of gall bladder cancer. The investigation of 17 patients with cancer of this site showed a high informative value of the method. A retrospective comparative study of the results of CT and surgical interventions was carried out. It has been concluded that CT makes it possible not only to diagnose malignant lesions of the bile ducts but also to assess a possible scope of a forthcoming operation

  17. Computerized dosimetry management systems within EDF

    International Nuclear Information System (INIS)

    Daubert, G.

    1996-01-01

    EDF, using the ALARA approach, has embarked an ambitious project of optimising the doses received in its power plants. In directing its choice of actions and the effectiveness of such actions, the French operator is using a computerized personal and collective dosimetry management system. This system provides for ongoing monitoring of dosimetry at personal, site and unit level or indeed for the entire population of EDF nuclear power plants. (author)

  18. Increased intracranial pressure: evaluation by computerized tomography

    International Nuclear Information System (INIS)

    Lightfoote, W.E.; Pressman, B.D.

    1975-01-01

    Computerized tomography is clearly very useful in the evaluation of patients with increased intracranial pressure and suspected pseudotumor cerebri. It provides an index of ventricular size and configuration and has the capability of demonstrating intracranial lesions. Moreover, this new technique is rapid and non-invasive, and is without attendant risks. Examinations may be performed serially as the clinical process evolves, thereby giving roentgenographic correlation to the clinical features. (U.S.)

  19. Computerized tomographic diagnosis of basal skull fracture

    International Nuclear Information System (INIS)

    Tanaka, Tokutaro; Shimoyama, Ichiro; Endoh, Mitsutoshi; Ninchoji, Toshiaki; Uemura, Kenichi.

    1984-01-01

    The diagnosis of basal skull fractures used to be difficult, particularly on the basis of routine skull roentgenography alone. We have now examined the diagnostic value of conventional computerized tomography in basal skull fractures. We studied 82 cases clinically diagnosed as basal skull fractures. We examined them based on at least one of the following computerized tomographic criteria for basal skull fractures: 1) fracture line(s), 2) intracranial air, 3) fluid in the paranasal sinuses, and 4) fluid in the middle ear, including the mastoid air cells. The signs of the fracture line and of the intracranial air are definite indications of basal skull fracture, but the signs of fluid in the paranasal sinuses and/or in the middle ear are not definite. When combined, however, with such other clinical signs as black eye, Battle's sign, CSF leakage, CSF findings, and profuse nasal or ear bleeding, the diagnosis is more reliable. Seventy cases (85.4%) in this series had basal skull fractures according to our computerized tomographic criteria. Among them , 26 cases (31.7%) were diagnosed with fracture lines, 17 cases (20.7%) with intracranial air, 16 cases (19.5%) with fluid in the paranasal sinuses, 10 cases (12.2%) with fluid in the middle ear, and one case (1.2%) with fluid in both. Twelve cases (14.6%) of the 82 cases clinically diagnosed as basal skull fractures could not have been diagnosed on our computerized tomographic criteria alone. We diagnosed them because of CSF leakage, CSF findings, surgical findings, etc. (author)

  20. Computerized materials protection, control, and accountability

    International Nuclear Information System (INIS)

    Whiteson, R.; Seitz, S.; Landry, R.P.; Hadden, M.L.; Painter, J.A.

    1997-01-01

    The proliferation of nuclear weapons, along with the technical knowledge and materials needed to make these weapons, is an enduring problem of international urgency. Current international nuclear nonproliferation efforts are aimed at deterring, detecting, and responding to proliferation of weapons of mass destruction. These safeguards efforts are being implemented by applying preeminent science and technology to the management and control of nuclear materials. By strengthening systems of nuclear material protection, control, and accountability (MPC and A), one can reduce the threat of nuclear weapons proliferation. Two major programs of international cooperation are now underway to achieve this goal. The first is between the US Department of Energy (DOE) and the Institutes of the Russian Federation (Laboratory-to-Laboratory Program), and the second is between the US Government and Governments of the former Soviet Republics (Government-to-Government Program). As part of these programs, the DOE is working with facilities to assist them in implementing computerized MPC and A systems. This work is a collaboration between computer scientists and safeguards experts in both the US and the new Republics. The US is making available technology and expertise to enable Russian experts to build on computerized MPC and A software developed in the US. This paper describes the joint efforts of these international teams to develop sophisticated computerized MPC and A systems using modern computer hardware and software technology. These systems are being customized to meet the site-specific needs of each facility

  1. Computerized analysis of brain perfusion parameter images

    International Nuclear Information System (INIS)

    Turowski, B.; Haenggi, D.; Wittsack, H.J.; Beck, A.; Aurich, V.

    2007-01-01

    Purpose: The development of a computerized method which allows a direct quantitative comparison of perfusion parameters. The display should allow a clear direct comparison of brain perfusion parameters in different vascular territories and over the course of time. The analysis is intended to be the basis for further evaluation of cerebral vasospasm after subarachnoid hemorrhage (SAH). The method should permit early diagnosis of cerebral vasospasm. Materials and Methods: The Angiotux 2D-ECCET software was developed with a close cooperation between computer scientists and clinicians. Starting from parameter images of brain perfusion, the cortex was marked, segmented and assigned to definite vascular territories. The underlying values were averages for each segment and were displayed in a graph. If a follow-up was available, the mean values of the perfusion parameters were displayed in relation to time. The method was developed under consideration of CT perfusion values but is applicable for other methods of perfusion imaging. Results: Computerized analysis of brain perfusion parameter images allows an immediate comparison of these parameters and follow-up of mean values in a clear and concise manner. Values are related to definite vascular territories. The tabular output facilitates further statistic evaluations. The computerized analysis is precisely reproducible, i. e., repetitions result in exactly the same output. (orig.)

  2. Computerized management of plant intervention tasks

    International Nuclear Information System (INIS)

    Quoidbach, G.

    2004-01-01

    The main objective of the 'Computerized Management of Plant Intervention Tasks' is to help the staff of a nuclear or a conventional power plant or of any other complex industrial facility (chemical industries, refineries, and so on) in planning, organizing, and carrying out any (preventive or corrective) maintenance task. This 'Computerized Management of Plant Intervention Tasks' is organized around a data base of all plant components in the facility that might be subjected to maintenance or tagout. It allows to manage, by means of intelligent and configurable 'mail service', the course of the intervention requests as well as various treatments of those requests, in a safe and efficient way, adapted to each particular organization. The concept of 'Computerized Management' of plant intervention tasks was developed by BELGATOM in 1983 for the Belgian nuclear power plants of ELECTRABEL. A first implementation of this concept was made at that time for the Doel NPP under the name POPIT (Programming Of Plant Intervention Tasks). In 1988, it was decided to proceed to a functional upgrade of the application, using advanced software and hardware techniques and products, and to realize a second implementation in the Tihange NPP under the name ACM (Application Consignation Maintenance). (author)

  3. Diversity in computerized reactor protection systems

    International Nuclear Information System (INIS)

    Fischer, H.D.; Piel, L.

    1999-01-01

    Based on engineering judgement, the most important measures to increase the independency of redundant trains of a computerized safety instrumentation and control system (I and C) in a nuclear power plant are evaluated with respect to practical applications. This paper will contribute to an objective discussion on the necessary and justifiable arrangement of diversity in a computerized safety I and C system. Important conclusions are: - (i) diverse equipment may be used to control dependent failures only if measures necessary for designing, licensing, and operating a computerized safety I and C system homogeneous in equipment are neither technically nor economically feasible; - (ii) the considerable large operating experience in France with a non-diverse equipment digital reactor protection system does not call for equipment diversity. Although there are no generally accepted methods, the licensing authority is still required to take into account dependent failures in a probabilistic safety analysis; - (ii) the frequency of postulated initiating events implies which I and C functionality should be implemented on diverse equipment. Using non-safety I and C equipment in addition to safety I and C equipment is attractive because its necessary unavailability to control an initiating event in teamwork with the safety I and C equipment is estimated to range from 0.01 to 0.1. This can be achieved by operational experience

  4. Staging of bronchogenic carcinoma by computerized tomography

    International Nuclear Information System (INIS)

    Sommer, B.; Bauer, W.M.; Rath, M.; Fenzl, G.; Stelter, W.J.; Lissner, J.

    1981-01-01

    It was possible to check the information obtained by CT scanning in 36 patients out of 49 who had been subjected to computerized tomography, in respect of the extension of the primary tumour (T stage), and in 25 patients in respect of the degree of mediastinal lymphatic node involvement (N stage). In all 49 patients, the presence of bronchogenic carcinoma had been safely established. In 97% of the cases, assessment of the extension of the primary tumour was found to be correct. Assessment of the N stage, however, is more problematic, since detection of mediastinal lymphatic nodes by computerized tomography does not necessarily tell us something about their metastatic involvement. If all recognizable lymphatic nodes are interpreted as potential metastases, we have no false negative but 61% false positive results because of the frequency of postinflammatory or anthracotic lymphatic nodes. In case of exclusive assessment of lymphatic node enlargement above 1 cm diameter, the rate of metastatic nodes increases considerably (83%). Computerized tomography is definitely superior to all roentgenological methods in assessing the stage of a bronchogenic carcinoma; hence, it could occupy a key position in determining the diagnostic and therapeutic approach in patients with this disease. (orig.) [de

  5. Case of neurosarcoidosis monitored by computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Kubota, T; Kimura, M; Komai, T; Yamamoto, S; Yamamura, I [Kanazawa Univ. (Japan). School of Medicine

    1979-12-01

    A 21-year-old man complaining of impaired visual acuity was admitted to the hospital. Physical examinations showed asymptomatic bilateral hilar lymphadenopathy and cardiomyopathy. Neurological findings disclosed left blindness and right temporal hemianopsia. Computerized tomography, pneumoencephalography and carotid angiography revealed a suprasellar mass. After the admission, the following symptoms deteriorated rapidly: diabetes insipidus, anterior pituitary dysfunction, visual loss of the right eye and hepatomegaly, subsequently consciousness disorder developed during a month though he was given steroids. The more deteriorated the clinical course, the larger the suprasellar mass with expanding hydrocephalus in repeated computerized tomographies. After the ventriculo-peritoneal shunt operation, consciousness improved. Diabetes insipidus also improved after Diabenese administration. On the operation, adhesive arachnoiditis over all the frontotemporal cortex and swollen purplishly red optic chiasm were exposed. Microscopically the specimen from the optic chiasm evidenced a sarcoid granuloma which composed of epitheroid cells, lymphocytes and multi-nucleated giant cells with numerous hemosiderin droplets. The specimen from the surface of the left frontal lobe showed thick fibrosis in the subarachnoid space. By steroids therapy, diabetes insipidus and hepatomegaly disappeared five months after the admission, whereas blindness never recovered. He died of developed status epilepticus eleven months after the admission. The authors reviewed neuroradiological findings of neurocarcoidosis based on pathological findings in the literature, and emphasized that computerized tomography was the most useful for diagnosis and treatment of neurosarcoidosis.

  6. Challenges to a Man-Machine Interface System in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Yeon Sub [KHNP, Daejeon (Korea, Republic of)

    2009-10-15

    When the APR1400 project started nearly 20 years ago, advanced features such as intelligent alarms, computer-based procedures, and soft control technology were introduced. Although some of these technologies had been utilized in fossil plants, APR1400 opened a new horizon in MMIS for nuclear power plants. Currently, however, it appears that further challenges do not exist in the MMIS area. Engineers are simply busy in designing and constructing the next nuclear plant without exploiting the new features of MMIS. This paper explains newly emerging and feasible technology and suggests new ideas for MMIS compared with other industries.

  7. Challenges to a Man-Machine Interface System in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jung, Yeon Sub

    2009-01-01

    When the APR1400 project started nearly 20 years ago, advanced features such as intelligent alarms, computer-based procedures, and soft control technology were introduced. Although some of these technologies had been utilized in fossil plants, APR1400 opened a new horizon in MMIS for nuclear power plants. Currently, however, it appears that further challenges do not exist in the MMIS area. Engineers are simply busy in designing and constructing the next nuclear plant without exploiting the new features of MMIS. This paper explains newly emerging and feasible technology and suggests new ideas for MMIS compared with other industries

  8. Analysis of concrete material through gamma ray computerized tomography

    International Nuclear Information System (INIS)

    Oliveira Junior, J.M. de

    2004-01-01

    Computerized Tomography (CT) refers to the cross sectional imaging of an object from both transmission or reflection data collected by illuminating the object from many different directions. The most important contribution of CT is to greatly improve abilities to distinguish regions with different gamma ray transmittance and to separate over-lying structures. The mathematical problem of the CT imaging is that of estimating an image from its projections. These projections can represent, for example, the linear attenuation coefficient of γ-rays along the path of the ray. In this work we will present some new results obtained by using tomographic techniques to analyze column samples of concrete to check the distribution of various materials and structural problems. These concrete samples were made using different proportions of stone, sand and cement. Another set of samples with different proportions of sand and cement were also used to verify the outcome from the CT analysis and the differences between them. Those samples were prepared at the Material Laboratory of Faculdade de Engenharia de Sorocaba, following the same procedures used in real case of concrete tests. The projections used in this work was obtained by Mini Computerized Tomograph of Uniso (MTCU), located at the Experimental Nuclear Physics Laboratory at University of Sorocaba. This tomograph operates with a gamma ray source of 241 Am (photons of 60 keV and 100 mCi of intensity) and a NaI(Tl) solid state detector. The system features translation and rotation scanning modes, a 100 mm effective field of view, and 1 mm spatial resolution. The image reconstruction problem is solved using Discrete Filtered Backprojection (FBP). (author)

  9. Review of trends in computerized systems for operator support

    International Nuclear Information System (INIS)

    Cain, D.G.

    1985-01-01

    The major trends shaping the development of computerized operator support systems in nuclear power plants are reviewed. These trends are the result of prior research in disturbance analysis systems that provided the technology base, and the SPDS requirement, which has been the impetus for change. The process is expected to result in hybrid control rooms with computer-driven supervisory workstations that complement conventional control board lay-outs. In the next three to five year period substantial upgrading of computer hardware will allow new and more sophisticated applications routines to be developed for operator support. Greater attention is being given to on-line validation of input signals for computer applications. A general movement towards operating strategies that are not based upon pre-analyzed event sequences is expected to influence the development of operator aids. The integration of displays with operating procedures will enable the computer system to a better coupling between problem detection and its resolution. Improved design methodology will assure that computer applications are accepted and used by operations personnel. Greater on-line analysis capability is stimulating the trend towards more on-site analysis and decision-making at nuclear power plants. Software standardization reflects the high cost of software development and the desire by utilities to gain greater independence from suppliers. There is growing realization that control rooms are beset by many of the demands and limitations of other office settings and that some of these may be addressed by the burgeoning office automation technology. Trends beyond the next five years are difficult to predict; however, there will be a trend towards more intelligent software. Artificial intelligence technology may play a pivotal role in future applications. Taking these trends into perspective, the author concludes that a promising future exists for computerized operator support in nuclear

  10. The Use of Statistical Process Control-Charts for Person-Fit Analysis on Computerized Adaptive Testing. LSAC Research Report Series.

    Science.gov (United States)

    Meijer, Rob R.; van Krimpen-Stoop, Edith M. L. A.

    In this study a cumulative-sum (CUSUM) procedure from the theory of Statistical Process Control was modified and applied in the context of person-fit analysis in a computerized adaptive testing (CAT) environment. Six person-fit statistics were proposed using the CUSUM procedure, and three of them could be used to investigate the CAT in online test…

  11. Emergency procedures

    International Nuclear Information System (INIS)

    Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

    2004-01-01

    The following subjects are discussed - Emergency Procedures: emergency equipment, emergency procedures; emergency procedure involving X-Ray equipment; emergency procedure involving radioactive sources

  12. Comparing imaging procedures: techniques and examples. Gastroenterology

    International Nuclear Information System (INIS)

    Malmud, L.S.

    1982-01-01

    The distinct advantages of nuclear medicine procedures, in comparison to radiography, contrast studies, computerized tomography and ultrasound, are emphasized. Scintigraphic methods offer quantitative data regarding function which competing imaging modalities are unable to provide, and make them the studies of choice in the evaluation of gastrointestinal physiology and functional abnormalities

  13. Percutaneous nephrolithotomy in pediatric patients: is computerized tomography a must?

    Science.gov (United States)

    Gedik, Abdullah; Tutus, Ali; Kayan, Devrim; Yılmaz, Yakup; Bircan, Kamuran

    2011-02-01

    The aim of this study was to retrospectively evaluate the results of pediatric percutaneous nephrolithotomy (PNL) cases, and discuss the results and necessity of non-contrast computerized tomography (CT) in these cases. In all, 48 pediatric patients who underwent PNL were retrospectively evaluated. Before PNL, either intravenous urography or CT was performed. In all patients, we evaluated the PNL time, scopy time with stone burden, and complications. During the PNL procedure, we switched to open surgery in two cases: in one because of renal pelvis perforation and in the other because of transcolonic access. In one patient who was scheduled to undergo PNL, we performed open surgery, primarily because we detected a retrorenal colon with CT. The stone burden in 45 patients who underwent PNL was 445 ± 225 mm(2), the PNL time was 51 ± 23 min, and the scopy time was 6.1 ± 2.7 min. We removed nephrostomy tubes 1-4 days after the procedure. In two patients, 24 h after removal of nephrostomy tubes, we inserted double J stents because of prolonged urine extravasation from the tract. In all, 34 of the 45 patients were stone-free, 5 patients had clinically insignificant stone fragments, and 6 patients had residual stones. PNL is a safe and effective method in the treatment of pediatric patients with kidney stones. Clinical experience is the most important factor in obtaining stone-free results. CT should be performed in all pediatric patients in order to prevent colon perforation.

  14. Computerized Operator Support System – Phase II Development

    Energy Technology Data Exchange (ETDEWEB)

    Ulrich, Thomas A.; Boring, Ronald L.; Lew, Roger T.; Thomas, Kenneth D.

    2015-02-01

    A computerized operator support system (COSS) prototype for nuclear control room process control is proposed and discussed. The COSS aids operators in addressing rapid plant upsets that would otherwise result in the shutdown of the power plant and interrupt electrical power generation, representing significant costs to the owning utility. In its current stage of development the prototype demonstrates four advanced functions operators can use to more efficiently monitor and control the plant. These advanced functions consist of: (1) a synthesized and intuitive high level overview display of system components and interrelations, (2) an enthalpy-based mathematical chemical and volume control system (CVCS) model to detect and diagnose component failures, (3) recommended strategies to mitigate component failure effects and return the plant back to pre-fault status, and (4) computer-based procedures to walk the operator through the recommended mitigation actions. The COSS was demonstrated to a group of operators and their feedback was collected. The operators responded positively to the COSS capabilities and features and indicated the system would be an effective operator aid. The operators also suggested several additional features and capabilities for the next iteration of development. Future versions of the COSS prototype will include additional plant systems, flexible computer-based procedure presentation formats, and support for simultaneous component fault diagnosis and dual fault synergistic mitigation action strategies to more efficiently arrest any plant upsets.

  15. Study of Pelvicaliceal Anatomy by Helical Computerized Tomography

    International Nuclear Information System (INIS)

    Al-Qahtani, Fahd N.; Ali, Gaber A.; Kamal, Baher A.; Taha, Saud A.

    2003-01-01

    To evaluate the role of 3-dimensional images produced by computerized tomography (CT), using intravenous contrast, to study pelvicaliceal anatomy.This might be of help in endourological procedure. The study was conducted in the King Fahd Hospital of the University, King Faisal University. Dammam,Kingdom of Saudi Arabia. The study took place from July 2002 through to October 2002 .Helical CT was carried for patients who were investigated using excretory urography for any reason. A CT was carried out to the kidneys only within 10 minutes ( between 5 and 15 minute films of excretory urography).Images were reprocessed by 3-dimension construction after subtracting all structures except for the palvicaliceal system. Thity-six normal kidneys were studied. The upper pole was drained by a single caliceal infundibulum in all 36(100%) kidneys.the middle segement of the kidney was drained by 2 infundibula in 32 (89%) kidneys. Four (11%) kidneys have no middle caliceal infudibula. The lower pole was drained by 2 caliceal infundibula in 23 (64%) and a single infundibulum in 13 (36%) kidneys. The minor calices draining each renal segment were seen clearly. Three-dimensional images derived by helical CT are feasible for evaluating the anatomy of palvicaliceal system,and, can be of help in endourological procedures. (author)/

  16. Ultrasonic and computerized tomographic semiotics of cholelithiasis

    International Nuclear Information System (INIS)

    Kishkovskij, A.N.; Kuznetsov, S.V.; Fadeev, V.D.

    1986-01-01

    Altogether 447 patients with suspected cholelithiasis were examined by means of routine X-ray methods, ultrasound (US) and computerized tomography (CT).Of them in 104 (23.3%) chole- and/or choledocholithiasis were later confirmed. An US and CT-picture of the biliferous tracts in health were described.In cholelithiasis during US examination echogenic concrements producing a stable acoustic shadow were defined in the gall bladder cavity and/or in the biliferous ducts. A study was made of the features of the US picture with relation to size, quantity, echodensity and grouping of concrements in the biliferous ducts. CT-symptomatology of cholelithiasis was described

  17. Computerized tomography in radiodiagnosis of pneumonia

    International Nuclear Information System (INIS)

    Degtyareva, I.A.; Mamaev, V.V.; Savchenko, A.P.

    1989-01-01

    Experience in the use of computerized tomography (CT) in combined radiodiagnosis of pneumonia was analysed. It has been concluded that CT objectively reflects morphological inflammatory changes and permits their all-round assessment over time. The diagnosis of pneumonia in CT is based on classical x-ray symptoms. As compared to survery radiography CT reveals symptoms of pneumonia to the full at earlier stages. CT is an important additional method of investigation of inflammatory pulmonary diseases but it should not be used separately without survey radiography. In a majority of cases when CT is performed there is no need in x-ray tomography

  18. Visualization in the age of computerization

    CERN Document Server

    Carusi, Annamaria; Webmoor, Timothy; Woolgar, Steve

    2014-01-01

    Digitalization and computerization are now pervasive in science. This has deep consequences for our understanding of scientific knowledge and of the scientific process, and challenges longstanding assumptions and traditional frameworks of thinking of scientific knowledge. Digital media and computational processes challenge our conception of the way in which perception and cognition work in science, of the objectivity of science, and the nature of scientific objects. They bring about new relationships between science, art and other visual media, and new ways of practicing science and organizing

  19. Development of a computerized tomographic system

    International Nuclear Information System (INIS)

    Borges, J.C.; Santos, C.A.C.

    1986-01-01

    The Nuclear Instrumentation Laboratory at COPPE/UFRJ has been developing techniques for detection and applications of nuclear radiations. A lot of research work has been done and resulted in several M.Sc. and D.Sc. thesis, concerning subjects like neutrongraphy, gammagraphy, image reconstruction, special detectors, etc. Recent progress and multiple applications of the computerized tomography to medical and industrial non-destructive tests, pushed the Laboratory to a vast program in this field of research. In this paper, we report what has been done and the results obtained. (Author) [pt

  20. Computerized tomography in diagnosis of cerebrocranial injury

    International Nuclear Information System (INIS)

    Kornienko, V.N.; Vasin, N.Ya.; Kuz'menko, V.A.

    1987-01-01

    The method of computerized tomographical examination are presented. Th KT-characters of concussion of the brain, its contusion of different severity, compressions in case of traumatic intracranial hematomas, contusion injuries, brain edema and different aftereffects of cerebrocranial injury are given. On the basis of comparison of the data of clinical and KT examination the dynamics of intracranial traumatic injuries in the course of treatment is described. The problems of therapeutic and surgical tactics depending on the degree and form of intracranial structure injuries and the phase of clinical course of posttraumatic process are discussed

  1. Computerized abdominal tomography in Wilson's disease

    Energy Technology Data Exchange (ETDEWEB)

    Tsuchikura, Keiko; Ogawa, Teruyuki; Nakajima, Akihisa; Ono, Yasuhiko

    1986-05-01

    Cranial and abdominal computerized tomography (CT) was performed in a 10-year-old boy with Wilson's disease complicated by liver cirrhosis. Abdominal CT showed diffuse high density areas over the whole part of the liver propably due to copper sediments, although there was no abnormal cranial CT findings. Decreased high density area of the liver was seen 60 days after the administration of D-penicillamine, suggesting the excretion of copper from the liver. Abdominal CT, as well as cranial CT, may be of help to diagnose Wilson's disease and evaluate therapeutic effects. (Namekawa, K.).

  2. Sonography and computerized tomography in a comparison in renal mass diseases

    International Nuclear Information System (INIS)

    Brommer, M.

    1981-01-01

    One hundred and thirteen patients with renal mass processes were examined sonographically and by computized tomography. The diagnosis was assured in 32 cases histologically, in 40 cases angiographically clinically and by the course and in 41 cases only clinically and by the course resp. by sonographic and computerized tomography control studies. The accuracy of a hit in sonography is smaller compared with computerized tomography with fast image formation. However, due to its relative safety, it is judged as the most useful technique for a first diagnossis of renal masses after ureographic diagnostic of excreta. A diagnostic procedure is proposed in which the number of necessary angiographies and diagnostic sampling surgery can be considerably reduced. (orig.) [de

  3. Computerized systems for high level information processing and decision making in the field of PSA

    International Nuclear Information System (INIS)

    Kafka, P.; Kunitz, H.

    1990-01-01

    A comprehensive review of Probabilistic Safety Assessment (PSA) related program packages is made. Three fields in methodological succession are covered: plant modeling, data quantification procedures and decision-making support. Packages for fault tree construction and minimal cut sets evaluation are referred to and the performances of three of them: RALLY, ORCHARD and SALP-PC, are discussed and compared. Notions on the raw data sources are presented and the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is given as an example for data base management system generating PSA data. Aggregated risk models for support in safety assessment, plant operation and accident management (SARA, ESSM, PRISIM) are cited. Examples of systems supporting 'living PSA' (SAIS, SUPER-NET, LESSEPS 1300, NUPRA, SPSA) are given. The concluding remarks outline the state-of-the-art developments of computerized systems for reliability analyses. 1 fig., 1 tab., 51 refs. (R.Ts)

  4. Modernizing computerized nuclear material accounting systems

    International Nuclear Information System (INIS)

    Erkkila, B.H.; Claborn, J.

    1995-01-01

    DOE Orders and draft orders for nuclear material control and accountability address a complete material control and accountability (MC and A) program for all DOE contractors processing, using, or storing nuclear materials. A critical element of an MC and A program is the accounting system used to track and record all inventories of nuclear material and movements of materials in those inventories. Most DOE facilities use computerized accounting systems to facilitate the task of accounting for all their inventory of nuclear materials. Many facilities still use a mixture of a manual paper system with a computerized system. Also, facilities may use multiple systems to support information needed for MC and A. For real-time accounting it is desirable to implement a single integrated data base management system for a variety of users. In addition to accountability needs, waste management, material management, and production operations must be supported. Information in these systems can also support criticality safety and other safety issues. Modern networked microcomputers provide extensive processing and reporting capabilities that single mainframe computer systems struggle with. This paper describes an approach being developed at Los Alamos to address these problems

  5. Computerized tomographic in non-destructive testing

    International Nuclear Information System (INIS)

    Lopes, R.T.

    1988-01-01

    The process of computerized tomography has been developed for medical imaging purposes using tomographs with X-ray, and little attention has been given to others possibles applications of technique, because of its cost. As an alternative for the problem, we constructed a Tomographic System (STAC-1), using gamma-rays, for nonmedical applications. In this work we summarize the basic theory of reconstructing images using computerized tomography and we describe the considerations leading to the development of the experimental system. The method of reconstruction image implanted in the system is the filtered backprojection or convolution, with a digital filters system to carried on a pre-filtering in the projections. The experimental system is described, with details of control and the data processing. An alternative and a complementary system, using film as a detector is shown in preliminary form . This thesis discuss and shows the theorical and practical aspects, considered in the construction of the STAC-1, and also its limitations and apllications [pt

  6. A prototype of a computerized patient record.

    Science.gov (United States)

    Adelhard, K; Eckel, R; Hölzel, D; Tretter, W

    1995-01-01

    Computerized medical record systems (CPRS) should present user and problem oriented views of the patient file. Problem lists, clinical course, medication profiles and results of examinations have to be recorded in a computerized patient record. Patient review screens should give a synopsis of the patient data to inform whenever the patient record is opened. Several different types of data have to be stored in a patient record. Qualitative and quantitative measurements, narratives and images are such examples. Therefore, a CPR must also be able to handle these different data types. New methods and concepts appear frequently in medicine. Thus a CPRS must be flexible enough to cope with coming demands. We developed a prototype of a computer based patient record with a graphical user interface on a SUN workstation. The basis of the system are a dynamic data dictionary, an interpreter language and a large set of basic functions. This approach gives optimal flexibility to the system. A lot of different data types are already supported. Extensions are easily possible. There is also almost no limit concerning the number of medical concepts that can be handled by our prototype. Several applications were built on this platform. Some of them are presented to exemplify the patient and problem oriented handling of the CPR.

  7. Radiographic analysis of body composition by computerized axial tomography

    International Nuclear Information System (INIS)

    Heymsfield, S.B.

    1986-01-01

    Radiographic methods of evaluating body composition have been applied for over five decades. A marked improvement in this approach occurred in the mid-nineteen-seventies with the introduction of computerized axial tomography. High image contrast, cross-sectional imaging and rapid computerized data processing make this technique a sophisticated clinically applicable tool. (author)

  8. Direct coronary and sagittal computerized tomography of the pelvis

    International Nuclear Information System (INIS)

    Maier, W.; Bargon, G.

    1981-01-01

    Whereas quite a number of reports have been published on direct coronary and sagittal computed tomography of the cranium, no extensive experience has been collected on multidimensional computerized tomography of the pelvis. In this article, the authors report on their preliminary experiences in direct approximately sagittal and coronary computerized tomography of the pelvis in a group of 76 patients. (orig.) [de

  9. Computerized tomography in evaluation of the pulmonary hilum

    International Nuclear Information System (INIS)

    Secaf, M.; Ferreira, J.L.N.; Secaf, E.

    1987-01-01

    The use of computerized tomography as a method for evaluating the pulmonary hilum and its application in the diagnosis of endobronchial lesions, hilar masss, contiguous involvement of the mediastinum by hilar mass, and vascular hilar lesions are discussed. A comparative evaluation between conventional tomograms and computerized tomography is presented. (M.A.C.) [pt

  10. Computerized accountability program is operating - DYMCAS

    International Nuclear Information System (INIS)

    Combs, S.W.; Mee, W.T.

    1983-01-01

    The nuclear materials control and accountability program in the Oak Ridge Y-12 Plant has been placed on a computerized system identified as DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). The primary gola of the DYMCAS is to assist in detecting the diversion of special nuclear material (SNM). Secondly, the system is expected to assure quality inventory reconciliations both under normal and emergency situations. The system has been installed and was placed on active status in April 1982. Since that time numerous problems have surfaced and been resolved; i.e., delays of input, hardware breakdown, and misunderstandings of needs. An explanation of these problems, including examples and alterations that have made the system workable, are presented

  11. A computerized accountability program is operating - DYMCAS

    International Nuclear Information System (INIS)

    Combs, S.W.; Mee, W.T.

    1983-01-01

    The nuclear materials control and accountability program in the Oak Ridge Y-12 Plant has been placed on a computerized system identified as DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). The primary goal of the DYMCAS is to assist in detecting the diversion of special nuclear material (SNM). Secondly, the system is expected to assure quality inventory reconciliations both under normal and emergency situations. The system has been installed and was placed on active status in April 1982. Since that time numerous problems have surfaced and been resolved; i.e., delays of input, hardware breakdown, and misunderstandings of needs. An explanation of these problems, including examples and alterations that have made the system workable, are presented

  12. Computerized tomographic scanner with shaped radiation filter

    International Nuclear Information System (INIS)

    Carlson, R.W.; Walters, R.G.

    1981-01-01

    The invention comprises a shaped filter and a filter correction circuitry for computerized tomographic scanners. The shaped filter is a generally u-shaped block of filter material which is adapted to be mounted between the source of radiation and the scan circle. The u-shaped block has a parabolic recess. The filter material may be beryllium, aluminum, sulphur, calcium, titanium, erbium, copper, and compounds including oxides and alloys thereof. The filter correction circuit comprises a first filter correction profile adding circuit for adding a first scaler valve to each intensity valve in a data line. The data line is operated on by a beam hardness correction polynomial. After the beam hardness polynomial correction operation, a second filter correction circuit adds a second filter correction profile consisting of a table of scalor values, one corresponding to each intensity reading in the data line

  13. Computerized tomography findings in nasolacrimal dysfunction

    International Nuclear Information System (INIS)

    Ishida, Toshio; Nakamura, Yasuhisa; Kumagai, Michiasa

    1985-01-01

    We examined 17 cases (22 lesions) with stenosis or obstruction in the lacrimal drainage system with the use of computerized tomography (CT). In idio pathic cases, the site of obstruction was located either in the upper nasolacrimal duct or at the junction of the lacrimal sac and the nasolacrimal duct. In post-traumatic cases, it was located in the lower nasolacrimal duct. The obstructed areas appeared as homogenous in CT image with CT values ranging between +60 and +80. These findings were suggestive of granulation tissue. The stenosed areas appeared, on the other hand, as areas of unequal density. Lacrimal passage appeared to be maintained through the low-density portion. The CT values of the lacrimal sac was around +40 in dacryocystitis and around +20 to +30 other cases. (author)

  14. Organ doses from computerized tomography examinations

    Energy Technology Data Exchange (ETDEWEB)

    Janeczek, J.

    1995-12-31

    Estimates of mean organs doses from five typical computerized tomography (CT) examinations were obtained. Measurements were done using Rando-Alderson anthropomorphic phantom and thermoluminescent dosemeters (TLD). Radiation dose distributions within a phantom has been measured for each examination and results were used for organ dose calculation. Doses to organs specified by ICPR 60 Recommendations were measured for five CT scanners (CT/T8800, CT 9800, CT MAX - made by General Electric; CT 1200 SX - made by Picker; SOMATOM 2 - made by Siemens). Dose distributions from scattered radiation were measured and indicate that scattered radiation dose to thyroid and eye lens can be reduced by proper examination limits setting. The lowest mean organ doses were obtained from CT/T8800 scanner. More advanced scanners using high intensity continuous radiation were giving higher organ doses. (author). 23 refs, 6 figs, 13 tabs.

  15. Computerized techniques for collecting the radioprotection data

    International Nuclear Information System (INIS)

    Cenusa, V.; Valeca, S.; Guta, C.; Talpalariu, C.; Stoica, V.

    2016-01-01

    An important component of a computerized radioprotection system is the module for the collection of the radioprotection data. The data collection can be made automatically from the measurement equipment or manually by the operators after they read the values measured by the mobile devices. Database systems are used for storing the data, they offer higher performances, more efficient data organization, ensure data integrity and controlled access to the data into a multiuser environment. The experimental program for the automatic collection of the remote data transfers periodically, at programmable time intervals, data files from the fixed radiation monitoring stations to a centralized system for radioprotection data. For this is used the File Transfer Protocol (FTP). A Radiation Monitoring Equipment designed and assembled in the Electronics Department of ICN Pitesti was used as a data source for the testing of the experimental programs. (authors)

  16. Computerization of a telescope at secondary education

    Science.gov (United States)

    García Santiago, A.; Martos Jumillas, J.

    2017-03-01

    The work we are presenting in this paper is the computerization of a refractor telescope on an EQ3 type equatorial mount through Arduino. The control of the mount is done via three different interfaces: Stellarium, an Android interface for mobile phones and a second interface for PC made with Processing. The aforementioned work was done by the authors with a double purpose: presenting the interest in astronomy in the Mathematics department, and the development of applications within the subject of Technology in 4th ESO. So, it is a collaborative project between both departments. Except for the telescope and the mount, all the resources we have used can be found in any high school: free software (Guadalinex v9), App Inventor and Processing.The project was carried out under the principle of reducing all possible costs given the economic possibilities of the institution.

  17. Development of computerized risk management tool

    International Nuclear Information System (INIS)

    Kil Yoo Kim; Mee Jung Hwang; Seung Cheol Jang; Sang Hoon Han; Tae Woon Kim

    1997-01-01

    The author describes the kinds of efforts for the development of computerized risk management tool; (1) development of a risk monitor, Risk Monster, (2) improvement of McFarm (Missing Cutsets Finding Algorithm for Risk Monitor) and finally (3) development of reliability database management system, KwDBMan. Risk Monster supports for plant operators and maintenance schedulers to monitor plant risk and to avoid high peak risk by rearranging maintenance work schedule. Improved McFarm significantly improved calculation speed of Risk Monster for the cases of supporting system OOS (Out Of Service). KwDBMan manages event data, generic data and CCF (Common Cause Failure) data to support Risk Monster as well as PSA tool, KIRAP (KAERI Integrated Reliability Analysis Package)

  18. Computerized axial tomography in traumatic cervical lesions

    International Nuclear Information System (INIS)

    Koyama, Tsunemaro

    1982-01-01

    Although plain computerized axial tomography cannot routinely demonstrate the spinal cord, it does provide excellent visualization of the bony outline of the spinal canal and vertebral column. So it should be reasonable to use this technique in cases of cervical traumatic disorders. In this paper we presented 10 cases of cervical traumatic lesions; 3 atlanto-axial dislocation, 2 cervical canal stenosis, 3 OPLL, 1 intramedullary hematoma and 1 C 2 -neurinoma. In some patients neurologic deficits were induced by cervical trauma. Bony lesions appeared more adequately deliniated than intraspinal lesions, however, in some cases intramedullary changes could also be demonstrated. The use of metrizamide with high resolution CT-scanner could improve the usefullness of this technique. (author)

  19. Organ doses from computerized tomography examinations

    International Nuclear Information System (INIS)

    Janeczek, J.

    1995-01-01

    Estimates of mean organs doses from five typical computerized tomography (CT) examinations were obtained. Measurements were done using Rando-Alderson anthropomorphic phantom and thermoluminescent dosemeters (TLD). Radiation dose distributions within a phantom has been measured for each examination and results were used for organ dose calculation. Doses to organs specified by ICPR 60 Recommendations were measured for five CT scanners (CT/T8800, CT 9800, CT MAX - made by General Electric; CT 1200 SX - made by Picker; SOMATOM 2 - made by Siemens). Dose distributions from scattered radiation were measured and indicate that scattered radiation dose to thyroid and eye lens can be reduced by proper examination limits setting. The lowest mean organ doses were obtained from CT/T8800 scanner. More advanced scanners using high intensity continuous radiation were giving higher organ doses. (author). 23 refs, 6 figs, 13 tabs

  20. Dose evaluation in diagnostic for computerized tomography

    International Nuclear Information System (INIS)

    Flores, W.; Borges, J.C.; Mota, H.

    1998-01-01

    The patients which are subjected to computerized tomography tests are exposed to relatively high doses given as result doses on organs that are not matter to test. It was realized a dose levels raising in patients subjected to tests by T C, utilizing to measure this magnitude, TLD-100 thermoluminescent dosemeters which were put directly on the patient, in eye regions, thyroid, breast and navel; founding doses fluctuating between 29.10-49.39 mGy in organs examined and dose values between 0.21-29.10 mGy for organs that no matter to test. The applications of ionizing radiations in medicine do not have dose limits, but paying attention to the radiological protection optimization principle, it is recommended the use of clothes to anti-rays protection for zones not examined, getting with this to reduce the level doses as low as possible, without this to diminish the test quality. (Author)

  1. Computerized information management for institutional review boards.

    Science.gov (United States)

    Hood, Maureen N; Gugerty, Brian; Levine, Richard; Ho, Vincent B

    2005-01-01

    The use of human subjects for medical research in most industrialized nations requires the scientific and ethical scrutiny of research proposals by a governing institutional review board (IRB) or its equivalent. As part of their primary charge to protect human subjects, IRBs are responsible for the regulatory oversight of not only the research protocol itself but also the research conduct of the investigators and, if applicable, the funding sponsor. This article will discuss the regulatory requirements for an accurate account of IRB protocols and investigators and present an overview of the general flow of information for an IRB protocol. The current and potential uses of information management systems by IRBs will also be reviewed and accompanied by a discussion of the potential advantages and disadvantages of various computerized information systems for management of clinical research.

  2. Normal anatomical measurements in cervical computerized tomography

    International Nuclear Information System (INIS)

    Zaunbauer, W.; Daepp, S.; Haertel, M.

    1985-01-01

    Radiodiagnostically relevant normal values and variations for measurements of the cervical region, the arithmetical average and the standard deviation were determined from adequate computer tomograms on 60 healthy women and men, aged 20 to 83 years. The sagittal diameter of the prevertebral soft tissue and the lumina of the upper respiratory tract were evaluated at exactly defined levels between the hyoid bone and the incisura jugularis sterni. - The thickness of the aryepiglottic folds, the maximal sagittal and transverse diameters of the thyroid gland and the calibre of the great cervical vessels were defined. - To assess information about laryngeal function in computerized tomography, measurements of distances between the cervical spine and anatomical fixed points of the larynx and hypopharynx were made as well as of the degree of vocal cord movement during normal respiration and phonation. (orig.) [de

  3. Computerized radionuclidic analysis in production facilities

    International Nuclear Information System (INIS)

    Gibbs, A.

    1978-03-01

    The Savannah River Plant Laboratories Department has been using a dual computer system to control all radionuclidic pulse height analyses since 1971. This computerized system analyzes 7000 to 8000 samples per month and has allowed the counting room staff to be reduced from three persons to one person. More reliable process information is being returned to the production facilities and for environmental evaluations and being returned faster, even though the sample load has more than tripled. This information is now more easily retrievable for other evaluations. The computer is also used for mass spectrometer data reduction and for quality control data analysis. The basic system is being expanded by interfacing microcomputers which provide data input from all of the laboratory modules for quality assurance programs

  4. Termination Criteria for Computerized Classification Testing

    Directory of Open Access Journals (Sweden)

    Nathan A. Thompson

    2011-02-01

    Full Text Available Computerized classification testing (CCT is an approach to designing tests with intelligent algorithms, similar to adaptive testing, but specifically designed for the purpose of classifying examinees into categories such as - pass- and - fail.- Like adaptive testing for point estimation of ability, the key component is the termination criterion, namely the algorithm that decides whether to classify the examinee and end the test or to continue and administer another item. This paper applies a newly suggested termination criterion, the generalized likelihood ratio (GLR, to CCT. It also explores the role of the indifference region in the specification of likelihood-ratio based termination criteria, comparing the GLR to the sequential probability ratio test. Results from simulation studies suggest that the GLR is always at least as efficient as existing methods.

  5. Failed fuel rod detection system and computerized manipulator during outages

    International Nuclear Information System (INIS)

    Boehm, H.H.; Foerch, H.

    1984-01-01

    During regular outages spent fuel assemblies need to be replaced and relocated within the core. Defective fuel rods in particular fuel assemblies have to be removed from further service and before delivery of such faulty fuel assemblies to a reprocessing plant. The system which Brown Boveri Reaktor GmbH and Krautkraemer have developed in the Federal Republic of Germany is capable of directly locating the defective rods in a proper fuel assembly. Inspection times are comparable to those of standard sipping methods, with the advantages of immediately available results and direct identification of the defective fuel rods. During the repair of fuel assemblies this system allows withdrawal of individual defective rods. With the sipping method all the fuel rods of a defective fuel assembly need to be removed and inspected by eddy current testing. During steam generator inspection and repair personnel are exposed to ample radiation. A remotely controlled, computerized manipulator was used to significantly reduce the radiation dose by automating steps in the procedures; at the same time inspection and repair times were reduced. The main features of the manipulator are a rigid component construction of the leg and two arms, and a resolver control for horizontal and vertical motion that enables rapid and accurate access to a desired tube (author)

  6. The Initial Development of a Computerized Operator Support System

    Energy Technology Data Exchange (ETDEWEB)

    Roger Lew; Ronald L Boring; Thomas A Ulrich; Ken Thomas

    2014-08-01

    A computerized operator support system (COSS) is a collection of resilient software technologies to assist operators in monitoring overall nuclear power plant performance and making timely, informed decisions on appropriate control actions for the projected plant condition. The COSS provides rapid assessments, computations, and recommendations to reduce workload and augment operator judgment and decision-making during fast- moving, complex events. A prototype COSS for a chemical volume control system at a nuclear power plant has been developed in order to demonstrate the concept and provide a test bed for further research. The development process identified four underlying elements necessary for the prototype, which consist of a digital alarm system, computer-based procedures, piping and instrumentation diagram system representations, and a recommender module for mitigation actions. An operational prototype resides at the Idaho National Laboratory (INL) using the U.S. Department of Energy’s (DOE) Light Water Reactor Sustainability (LWRS) Human Systems Simulation Laboratory (HSSL). Several human-machine interface (HMI) considerations are identified and incorporated in the prototype during this initial round of development.

  7. Computerized Clinical Decision Support: Contributions from 2015

    Science.gov (United States)

    Bouaud, J.

    2016-01-01

    Summary Objective To summarize recent research and select the best papers published in 2015 in the field of computerized clinical decision support for the Decision Support section of the IMIA yearbook. Method A literature review was performed by searching two bibliographic databases for papers related to clinical decision support systems (CDSSs) and computerized provider order entry (CPOE) systems. The aim was to identify a list of candidate best papers from the retrieved papers that were then peer-reviewed by external reviewers. A consensus meeting between the two section editors and the IMIA editorial team was finally conducted to conclude in the best paper selection. Results Among the 974 retrieved papers, the entire review process resulted in the selection of four best papers. One paper reports on a CDSS routinely applied in pediatrics for more than 10 years, relying on adaptations of the Arden Syntax. Another paper assessed the acceptability and feasibility of an important CPOE evaluation tool in hospitals outside the US where it was developed. The third paper is a systematic, qualitative review, concerning usability flaws of medication-related alerting functions, providing an important evidence-based, methodological contribution in the domain of CDSS design and development in general. Lastly, the fourth paper describes a study quantifying the effect of a complex, continuous-care, guideline-based CDSS on the correctness and completeness of clinicians’ decisions. Conclusions While there are notable examples of routinely used decision support systems, this 2015 review on CDSSs and CPOE systems still shows that, despite methodological contributions, theoretical frameworks, and prototype developments, these technologies are not yet widely spread (at least with their full functionalities) in routine clinical practice. Further research, testing, evaluation, and training are still needed for these tools to be adopted in clinical practice and, ultimately, illustrate

  8. Radiation conditions for computerized tomography: determination and comparison

    International Nuclear Information System (INIS)

    Andrade, Lucio das Chagas de

    2016-01-01

    Radiology is the practice in which radiation beams, usually radiation X are used to produce an image of the human body in order to obtain a diagnosis, for example, to evaluate a pathological condition by computerized tomography (CT). Although the computerized tomography diagnostic potential is unquestionable, caution must be taken because the doses are almost always higher than the observed in conventional radiology procedures. The ionization chamber used for dosimetry in CT is a unsealed cylindrical chamber with 10 cm and 15 cm of sensitive length. A typical characteristics of this camera is its uniform response to radiation incident at all angles around its axis. The revised edition of IEC 61267 (2005) brought as an innovation the radiation conditions for computed tomography, RQT, that simulate non-attenuated beam and are used in special CT applications. This study aims to establish the necessary conditions to obtain radiation pattern beam computed tomography, RQT, and a calibration laboratory implementation for pencil ionization chambers used in the beam dosimetry produced by these scanners in the Metrology National Laboratory of Ionizing Radiation (LNMRI). In the implementation of RQT conditions we were found that the ratio of kerma rates in the air, with or without additional filtration equivalent to the first HVL (half-value layer), are in accordance with IEC 61267 (2005), which provides a range between 48.5% and 51.5% for each quality. The LNMRI characterized the radiation conditions of RQT series (IEC, 2005), obtaining a percentage of 49.6% for the RQT 8, 50% for the RQT 9 and 50,4% for the RQT 10. With the substitution of the total additional filtration RQT qualities, composed by Al + Cu and by a total filtration composed by copper (Cu) only, it can be seen the emergence of a similar RQT quality named Quality Copper Tomography - QCT. The results of the calibration, the RQT and QCT qualities, had expanded uncertainties with a confidence level 95.45%, less

  9. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Volume 1, Summary description

    International Nuclear Information System (INIS)

    Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.; Groh, M.R.; Gentillon, C.D.; Gilbert, B.G.

    1988-02-01

    A data management system has been implemented which supports a variety of risk-related analyses and provides a repository of hardware component failure and human error probability data to the risk analyst. The Nuclear Computerized Library for Assessing Reactor Reliability, NUCLARR, is an interactive, graphically oriented system which resides on a personal computer (PC) or PC-compatible environment. An overview of the data management system, including a description of data collection, specification, data structure, and taxonomies, is presented in Volume I of this report. Programming activities, procedures for processing data, user's guide, and hard copy data manual are presented in Volumes II through V

  10. Diagnostics of neuromuscular diseases with the aid of computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Visser, M de; Verbeeten, Jr, B J

    1988-06-04

    In this article the diagnosis of neuromuscular diseases with the aid of computerized tomography is treated. Computerized tomography of skeletal muscles give no information which is pathognomonic for particular diseases. But the technique can be used in the following aspects: to choose a muscle for a biopsy; when it is not possible to examine the function of a muscle, a CT scan can visualize morphological deviations; in the differentiation of muscle hypertrophy and pseudo-hypertrophy. For some cases as Becker-type muscular dystrophy, facioscapulohumeral dystrophy and Kugelberg-Welander type spinal muscular atrophy computerized tomography gives characteristic images. 10 refs.; 6 figs.

  11. Diagnostics of neuromuscular diseases with the aid of computerized tomography

    International Nuclear Information System (INIS)

    Visser, M. de; Verbeeten, B.J. Jr.

    1988-01-01

    In this article the diagnosis of neuromuscular diseases with the aid of computerized tomography is treated. Computerized tomography of skeletal muscles give no information which is pathognomonic for particular diseases. But the technique can be used in the following aspects: to choose a muscle for a biopsy; when it is not possible to examine the function of a muscle, a CT scan can visualize morphological deviations; in the differentiation of muscle hypertrophy and pseudo-hypertrophy. For some cases as Becker-type muscular dystrophy, facioscapulohumeral dystrophy and Kugelberg-Welander type spinal muscular atrophy computerized tomography gives characteristic images. 10 refs.; 6 figs

  12. Results of CT brain examinations in cerebrovascular emergency. [computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Pinta, Z; Dolansky, J; Sorfova, J; Jerie, T

    1987-07-01

    Experience is briefly reported with CT (computerized tomography) diagnosis of cerebrovascular emergencies. It is pointed out that the introduction of computerized tomography greatly improved and made more accurate the diagnosis of focal ischemias and revealed significant differences in the foci of ischemia in hypertension patients and atherosclerosis patients without hypertension, and showed a higher incidence of intracerebral and subarachnoidal hemorrhages than previously thought. It is believed that knowledge gained thanks to CT (computerized tomography) will be of benefit to the primary and secondary prevention of cerebrovascular ischemias. (L.O.). 1 fig., 5 refs.

  13. Research on accounting transition from computerization to informationization

    Directory of Open Access Journals (Sweden)

    Shu Chen

    2017-11-01

    Full Text Available The application for computer technology, digitalization technology and network technology in the accounting field has promoted the development of accounting informationization. Accounting informationization is a product integrated with traditional accounting theory and modern information technology, which is an inevitable trend of continuous development of modern accounting. This paper discusses the basic concepts and characteristics of accounting computerization and informationization based on the normative research method and literature data method, analyzes the feasibility of accounting transition from computerization to informationization, and finally puts forward the specific approaches and ultimate goals of accounting transition from computerization to informationization.

  14. Examinations and patient management in radiologic diagnostics by means of a computerized data-processing communications system

    International Nuclear Information System (INIS)

    Klotz, E.; Remplik, V.; Opfer, M.; Wilde, E.

    1986-01-01

    Concept, realization and a two-year experience in routine use of a computerized data-processing communications system supporting the central radiology department in a 1.625-bed, municipal hospital are discussed. Via the hospital ward-linked terminal network, routine X-ray examination is so ordered, that individual medical case information is provided, which certifies qualified clinical and diagnostic procedure along with good patient preparation and transportation. Complete information and documentation are also ensured. It was shown, that good motivation among involved radiologists and their close working-association with other departments are mandatory from the start to maintain exact time schedules and satisfactory completion of ordered X-ray procedures. Subsequently, the assistance through computerized data-processing becomes an accepted help - so far as it is appropriately used - as time goes by in its routine use. (orig.) [de

  15. Computerized data base of the fundamental constants of nature

    International Nuclear Information System (INIS)

    Henry, E.A.; Hampel, V.E.

    1975-01-01

    Fifty-seven fundamental constants of nature were computerized from the up-to-date evaluations of E. R. Cohen and B. N. Taylor. The constants are annotated with regard to symbol, value, uncertainty, and scaling factor. This computerization is part of the scientific data base project of the Information Research Group at Lawrence Livermore Laboratory. The MASTER CONTROL data base management system is used. The computerized fundamental constants can be requested from the ERDA Computer Program Exchange and Information Center of the Argonne National Laboratory or from the National Technical Information Service of the U. S. Department of Commerce. This is the first of a series of releases on preparation of computerized scientific and technological data banks. The next release is a data bank of conversion factors for different units of measurements. 3 figures

  16. Cranial computerized tomography in children suffering from acute leukemia

    International Nuclear Information System (INIS)

    Metz, O.

    1981-01-01

    Cranial computerized (axial) tomography permits a more complete neurologic supervision of children with acute leukemia and a better knowledge of the frequency and varieties of cerebral complications in leukemia. Endocranial complications in acute leukemia are essentially infiltrative, hemorrhagic, infectious or iatrogenic. Cranial computerized tomography can demonstrate cerebral changes in meningeal leukemia, hemorrhages, calcifications, brain atrophy or leukencephalopathy. The preliminary results of cranial computerized tomography in childhood leukemia suggest that the iatrogenic main lesion of the brain due to combined radiation-chemotherapy is atrophy whereas that of the intrathecal cytostatic therapy is demyelination. Accurate diagnostics and control of possible cerebral complications in therapy of leukemia is essentially for appropriate therapeutic management. For that cranial computerized tomography is the best method to a effective supervision of the brain. (author)

  17. Computerized Point of Sale = Faster Service + Better Accountability.

    Science.gov (United States)

    Pannell, Dorothy V.

    1991-01-01

    Describes selecting and installing a computerized point of sale for a district food service program; the equipment needed and preferred; and the training of trainers, managers, and cashiers. Also discusses the direct benefits and side benefits of the system. (MLF)

  18. 381 Developing of a Computerized Brain Diagnosing System for ...

    African Journals Online (AJOL)

    User

    Ogunsanwo O. D. - Department of Computer Science, Gate way ICT ... computerized brain diagnosing system that would be used in carrying out the ..... This aspect explores the techniques use for the design of interface, menus and databases ...

  19. Computerized Tomography and its Applications : a Guided Tour

    NARCIS (Netherlands)

    Roerdink, J.B.T.M.

    1992-01-01

    We present a review of the mathematical principles of computerized tomography. Topics treated include the role of the Radon transform and related transforms, inversion formulas, uniqueness, ill-posedness and stability, practical reconstruction algorithms, and various generalizations such as

  20. Algorithmic fundamentals of computerized tomography and of transverse analogue tomography

    International Nuclear Information System (INIS)

    Heckmann, K.

    1981-01-01

    Computerized tomography and transverse analogue tomography are two different approaches to the same goal, namely, transverse tomography. The algorithm is discussed and compared. Transverse tomography appears capable of further development, judging by this comparison. (orig.) [de

  1. Survey of methods for improving operator acceptance of computerized aids

    International Nuclear Information System (INIS)

    Frey, P.R.; Kisner, R.A.

    1982-04-01

    The success of current attempts to improve the operational performance and safety of nuclear power plants by installing computerized operational aids in the control rooms is dependent, in part, on the operator's attitude toward the aid. Utility experience with process computer systems indicates that problems may already exist with operator acceptance of computerized aids. The growth of the role that computers have in nuclear power plants makes user acceptance of computer technology an important issue for the nuclear industry. The purpose of this report is to draw from the literature factors related to user acceptance of computerized equipment that may also be applicable to the acceptance of computerized aids used in the nuclear power plant control room

  2. Development of a computerized handbook of architectural plans

    NARCIS (Netherlands)

    Koutamanis, A.

    1990-01-01

    The dissertation investigates an approach to the development of visual / spatial computer representations for architectural purposes through the development of the computerized handbook of architectural plans (chap), a knowledge-based computer system capable of recognizing the metric properties of

  3. Survey of methods for improving operator acceptance of computerized aids

    Energy Technology Data Exchange (ETDEWEB)

    Frey, P. R.; Kisner, R. A.

    1982-04-01

    The success of current attempts to improve the operational performance and safety of nuclear power plants by installing computerized operational aids in the control rooms is dependent, in part, on the operator's attitude toward the aid. Utility experience with process computer systems indicates that problems may already exist with operator acceptance of computerized aids. The growth of the role that computers have in nuclear power plants makes user acceptance of computer technology an important issue for the nuclear industry. The purpose of this report is to draw from the literature factors related to user acceptance of computerized equipment that may also be applicable to the acceptance of computerized aids used in the nuclear power plant control room.

  4. Computerized tomographic evaluation of aortic prosthetic graft complications

    International Nuclear Information System (INIS)

    Kay, D.; Kalmar, J.A.

    1985-01-01

    Computerized tomography has been found to be an accurate and sensitive method of diagnosing complications of synthetic aortic grafts. Complications in this series of four cases included aortoesophageal fistula, aortoduodenal fistula, pseudoaneurysm, and retroperitoneal hematoma. 6 references, 5 figures

  5. Computerized Analysis and Detection of Missed Cancer in Screening Mammogram

    National Research Council Canada - National Science Library

    Li, Lihua

    2005-01-01

    This project is to explore an innovative CAD strategy for improving early detection of breast cancer in screening mammograms by focusing on computerized analysis and detection of cancers missed by radiologists...

  6. Computerized Analysis and Detection of Missed Cancer in Screening Mammogram

    National Research Council Canada - National Science Library

    Li, Lihua

    2004-01-01

    This project is to explore an innovative CAD strategy for improving early detection of breast cancer in screening mammograms by focusing on computerized analysis and detection of cancers missed by radiologists...

  7. Journal of EEA, Vol. 30, 2013 COMPUTERIZED FACILITIES ...

    African Journals Online (AJOL)

    dell

    Key words: Computer Aided Layout Design,. Construction ... Commonly used software are ... popular improvement-type methods are. Computerized Relative Allocation of Facilities .... closeness ratings values are given different numerical.

  8. Stratification of mammographic computerized analysis by BI-RADS categories

    Energy Technology Data Exchange (ETDEWEB)

    Lederman, Richard [Department of Radiology, Hadassah University Hospital, Ein Kerem, Jerusalem (Israel); Leichter, Isaac [Department of Electro-Optics, Jerusalem College of Technology, P.O.B. 16031, Jerusalem (Israel); Buchbinder, Shalom [Department of Radiology of The Montefiore Medical Center, The University Hospital for the Albert Einstein College of Medicine, Bronx, New York (United States); Novak, Boris [Department of Applied Mathematics, Jerusalem College of Technology, P.O.B. 16031, Jerusalem 91160 (Israel); Bamberger, Philippe [Department of Electronics, Jerusalem College of Technology, POB 16031, Jerusalem (Israel); Fields, Scott [Department of Radiology, Hadassah University Hospital, Mt. Scopus, Jerusalem (Israel)

    2003-02-01

    The Breast Imaging Reporting and Data System (BI-RADS) was implemented to standardize characterization of mammographic findings. The purpose of the present study was to evaluate in which BI-RADS categories the changes recommended by computerized mammographic analysis are most beneficial. Archival cases including, 170 masses (101 malignant, 69 benign) and 63 clusters of microcalcifications (MCs; 36 malignant, 27 benign), were evaluated retrospectively, using the BI-RADS categories, by several radiologists, blinded to the pathology results. A computerized system then automatically extracted from the digitized mammogram features characterizing mammographic lesions, which were used to classify the lesions. The results of the computerized classification scheme were compared, by receiver operating characteristics (ROC) analysis, to the conventional interpretation. In the ''low probability of malignancy group'' (excluding BI-RADS categories 4 and 5), computerized analysis improved the A{sub z}of the ROC curve significantly, from 0.57 to 0.89. In the ''high probability of malignancy group'' (mostly category 5) the computerized analysis yielded an ROC curve with an A {sub z}of 0.99. In the ''intermediate probability of malignancy group'' computerized analysis improved the A {sub z}significantly, from 0.66 for to 0.83. Pair-wise analysis showed that in the latter group the modifications resulting from computerized analysis were correct in 83% of cases. Computerized analysis has the ability to improve the performance of the radiologists exactly in the BI-RADS categories with the greatest difficulties in arriving at a correct diagnosis. It increased the performance significantly in the problematic group of ''intermediate probability of malignancy'' and pinpointed all the cases with missed cancers in the ''low probability'' group. (orig.)

  9. Computerized systems of NPP operators support. (Psychological problems)

    International Nuclear Information System (INIS)

    Mashin, V.A.

    1995-01-01

    Operator psychological problems arising in the work with NPP operators support computerized systems (OSCS) are considered. The conclusion is made that the OSCS intellectual application will bring the operator into dangerous dependence on his computerized assistant. To avoid this danger it is necessary by creation of the OSCS to divide specially the tasks areas of the operator and OSCS in order to assure the active role of the operator in the NPP control

  10. Stratification of mammographic computerized analysis by BI-RADS categories

    International Nuclear Information System (INIS)

    Lederman, Richard; Leichter, Isaac; Buchbinder, Shalom; Novak, Boris; Bamberger, Philippe; Fields, Scott

    2003-01-01

    The Breast Imaging Reporting and Data System (BI-RADS) was implemented to standardize characterization of mammographic findings. The purpose of the present study was to evaluate in which BI-RADS categories the changes recommended by computerized mammographic analysis are most beneficial. Archival cases including, 170 masses (101 malignant, 69 benign) and 63 clusters of microcalcifications (MCs; 36 malignant, 27 benign), were evaluated retrospectively, using the BI-RADS categories, by several radiologists, blinded to the pathology results. A computerized system then automatically extracted from the digitized mammogram features characterizing mammographic lesions, which were used to classify the lesions. The results of the computerized classification scheme were compared, by receiver operating characteristics (ROC) analysis, to the conventional interpretation. In the ''low probability of malignancy group'' (excluding BI-RADS categories 4 and 5), computerized analysis improved the A z of the ROC curve significantly, from 0.57 to 0.89. In the ''high probability of malignancy group'' (mostly category 5) the computerized analysis yielded an ROC curve with an A z of 0.99. In the ''intermediate probability of malignancy group'' computerized analysis improved the A z significantly, from 0.66 for to 0.83. Pair-wise analysis showed that in the latter group the modifications resulting from computerized analysis were correct in 83% of cases. Computerized analysis has the ability to improve the performance of the radiologists exactly in the BI-RADS categories with the greatest difficulties in arriving at a correct diagnosis. It increased the performance significantly in the problematic group of ''intermediate probability of malignancy'' and pinpointed all the cases with missed cancers in the ''low probability'' group. (orig.)

  11. Computerized adaptive testing--ready for ambulatory monitoring?

    DEFF Research Database (Denmark)

    Rose, Matthias; Bjørner, Jakob; Fischer, Felix

    2012-01-01

    Computerized adaptive tests (CATs) have abundant theoretical advantages over established static instruments, which could improve ambulatory monitoring of patient-reported outcomes (PROs). However, an empirical demonstration of their practical benefits is warranted.......Computerized adaptive tests (CATs) have abundant theoretical advantages over established static instruments, which could improve ambulatory monitoring of patient-reported outcomes (PROs). However, an empirical demonstration of their practical benefits is warranted....

  12. The portable micro-computerized multichannel spectrometer for geological application

    International Nuclear Information System (INIS)

    Fang Fang; Jia Wenyi; Zou Rongsheng; Ma Yingjie; Zhou Jianbin

    1999-01-01

    The portable micro-computerized multichannel spectrometer is based on the book computer and employs the A/D integrated circuit with 12 bits. It is a 2048 channel spectrometer which is consisted of hardware and software. The author analyzed the hardware circuit and software construction of the micro-computerized multichannel spectrometer which is suitable for filed geological application. The main technical specifications and application of the new multichannel spectrometer were also discussed

  13. The portable micro-computerized multichannel spectrometer for geological application

    International Nuclear Information System (INIS)

    Fang Fang; Jia Wenyi; Zhou Rongsheng; Ma Yingjie; Zhou Jianbin

    1999-01-01

    The portable micro-computerized multichannel spectrometer is based on the book computer and employs the A/D integrated circuit with 12 bits. It is a 2048 channel spectrometer which consists of hardware and software. The author analyzed the hardware circuit and software construction of the micro-computerized multichannel spectrometer which is suitable for field geological application. The main technical specifications and application of the new multichannel spectrometer were also discussed

  14. Computerized cost model for pressurized water reactors

    International Nuclear Information System (INIS)

    Meneely, T.K.; Tabata, Hiroaki; Labourey, P.

    1999-01-01

    A computerized cost model has been developed in order to allow utility users to improve their familiarity with pressurized water reactor overnight capital costs and the various factors which influence them. This model organizes its cost data in the standard format of the Energy Economic Data Base (EEDB), and encapsulates simplified relationships between physical plant design information and capital cost information in a computer code. Model calculations are initiated from a base case, which was established using traditional cost calculation techniques. The user enters a set of plant design parameters, selected to allow consideration of plant models throughout the typical three- and four-loop PWR power range, and for plant sites in Japan, Europe, and the United States. Calculation of the new capital cost is then performed in a very brief time. The presentation of the program's output allows comparison of various cases with each other or with separately calculated baseline data. The user can start at a high level summary, and by selecting values of interest on a display grid show progressively more and more detailed information, including links to background information such as individual cost driver accounts and physical plant variables for each case. Graphical presentation of the comparison summaries is provided, and the numerical results may be exported to a spreadsheet for further processing. (author)

  15. Language networks associated with computerized semantic indices.

    Science.gov (United States)

    Pakhomov, Serguei V S; Jones, David T; Knopman, David S

    2015-01-01

    Tests of generative semantic verbal fluency are widely used to study organization and representation of concepts in the human brain. Previous studies demonstrated that clustering and switching behavior during verbal fluency tasks is supported by multiple brain mechanisms associated with semantic memory and executive control. Previous work relied on manual assessments of semantic relatedness between words and grouping of words into semantic clusters. We investigated a computational linguistic approach to measuring the strength of semantic relatedness between words based on latent semantic analysis of word co-occurrences in a subset of a large online encyclopedia. We computed semantic clustering indices and compared them to brain network connectivity measures obtained with task-free fMRI in a sample consisting of healthy participants and those differentially affected by cognitive impairment. We found that semantic clustering indices were associated with brain network connectivity in distinct areas including fronto-temporal, fronto-parietal and fusiform gyrus regions. This study shows that computerized semantic indices complement traditional assessments of verbal fluency to provide a more complete account of the relationship between brain and verbal behavior involved organization and retrieval of lexical information from memory. Copyright © 2014 Elsevier Inc. All rights reserved.

  16. Quality criteria for abdominal computerized tomography

    International Nuclear Information System (INIS)

    Huebener, K.H.; Kurtz, B.; Metzger, H.O.F.

    1985-01-01

    Quality, not only in obdominal computerized tomography, is determined by the measurable technical parameters and, to an important extent, also bei individual factors, among which the diagnostic skill and experience of the examiner is one of the most decisive. These individual factors and the part they play with regard to the quality of CT-assisted diagnosis may well equal the technical parameters, as they significantly influence the course of examinations, resulting indications for contrast medium application, and the sensitivity of the diagnosis. The authors are convinced that especially for abdominal CT, standardized examination techniques inevitably would bring down the diagnostic quality. The technical parameters are of equal significance to achieving the diagnostic optimum, and to these parameters one has to count equipment characteristics as well as the data given by the examiner. Exposure time, spatial resolution and density differentiation are given by the equipment specifications but have to be adapted to and optimised to the clinical problems involved in every case. Another important task is that of routine imaging of given anatomic structures, for adequate evaluation of individual conditions. (orig./MG) [de

  17. Single photon emission computerized tomography (SPECT)

    International Nuclear Information System (INIS)

    Ganatra, R.D.

    1992-01-01

    Tomography in nuclear medicine did not originate after the introduction of X-ray computerized tomography (CT). Even in the days of rectilinear scanner, tomography was attempted with multiple detector heads rotating around the patient, but the counts at each plane were never very high to obtain a satisfactory image. A high resolution focusing collimator can look at different depths but taking several slices in one projection was a time consuming process. Rectilinear scanners lose lot of counts in the collimator to look at one point, at on time, in one plane. It is true that attempts to do tomography with gamma camera really got a boost after the success of CT. By that time, algorithms for doing reconstruction of images also were highly refined and for advanced. Clinical application of SPECT has become widespread now, because of the development of suitable radiopharmaceuticals and improvement in instrumentation. The SPECT provides a direct measure of regional organ function and is performed with nuclides such as 123 I and 99 Tc m that emit a mono-image photon during their decay. SPECT is far less expensive than positron emission tomography

  18. Computerized portable microwave hyperthermia quality assurance kit

    International Nuclear Information System (INIS)

    Cheung, A.Y.; Neyzari, A.

    1985-01-01

    A computerized quality assurance kit to provide precise measurement and calibration of microwave power and temperature, as well as capabilities to map SAR (Specific absorption rate) distribution in phantoms; and survey of hazardous microwave leakage has been designed. The kit is also capable of performing corelation studies on the relationship between SAR and net microwave power delivered at various anatomical sites. The kit consists of a portable microcomputer, a time-multiplexed A/D converter, a 4-channel dual directional microwave power monitor, a 4-channel thin-wire thermocouple thermometry system, an electronic thermal calibrator, a microwave leakage hazard survey meter, and a dynamic phantom tank for dosimetric analysis. Comparative performance studies were made against NBS-traceable power and temperature standards, non-perturbing optical temperature sensors, and established power and temperature measurement devices. The test results indicate that this instrument is providing its user with measurement accuracy of 0.1 0 C in temperature, 10% accuracy in power. The thin-wire thermocouple, with computer assisted error compensation, performs equally well in a strong microwave field in comparison with non-perturbing optical temperature sensors

  19. Single photon emission computerized tomography (SPECT)

    Energy Technology Data Exchange (ETDEWEB)

    Ganatra, R D

    1993-12-31

    Tomography in nuclear medicine did not originate after the introduction of X-ray computerized tomography (CT). Even in the days of rectilinear scanner, tomography was attempted with multiple detector heads rotating around the patient, but the counts at each plane were never very high to obtain a satisfactory image. A high resolution focusing collimator can look at different depths but taking several slices in one projection was a time consuming process. Rectilinear scanners lose lot of counts in the collimator to look at one point, at on time, in one plane. It is true that attempts to do tomography with gamma camera really got a boost after the success of CT. By that time, algorithms for doing reconstruction of images also were highly refined and for advanced. Clinical application of SPECT has become widespread now, because of the development of suitable radiopharmaceuticals and improvement in instrumentation. The SPECT provides a direct measure of regional organ function and is performed with nuclides such as {sup 123}I and {sup 99}Tc{sup m} that emit a mono-image photon during their decay. SPECT is far less expensive than positron emission tomography

  20. Study on forefoot by computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Machida, Eiichi (Nihon Univ., Tokyo. School of Medicine)

    1983-10-01

    Computerized tomography (CT) was used to study coronary sections of the forefoot in both normal and abnormal human feet. CT images of the transverse arches at the metatarsal head, middle and base of the shaft were classified into five patterns. In the pattern most commonly found in normal feet, the second metatarsus appeared elevated above the other metatarsal bones at all points, and there was a gradual and even reduction in elevation from the second to the fifth metatarsal. In cases of hallux valgus, however, a variety of deformities were noted in the arc of the second to fifth metatarsals, particularly at the head. The rotation of the first metatarsus and shift of the sesamoids were measured from CT images at the head of the first metatarsus. In hallux valgus, both the rotation and the sesamoid shift appeared to have a wider angle than in the case of normal feet. In normal feet, the differences between the rotation of the first metatarsus and shift of the sesamoids were relatively small, whereas in hallux valgus there was a much greater degree of variation. Furthermore, while normal feet the variation in rotation of the first metatarsus and sesamoid shift both tended to be either great or small, in hallux valgus a large degree of sesamoid shift was sometimes found in combination with a small degree of rotation of the first metatarsus.

  1. Study on forefoot by computerized tomography

    International Nuclear Information System (INIS)

    Machida, Eiichi

    1983-01-01

    Computerized tomography (CT) was used to study coronary sections of the forefoot in both normal and abnormal human feet. CT images of the transverse arches at the metatarsal head, middle and base of the shaft were classified into five patterns. In the pattern most commonly found in normal feet, the second metatarsus appeared elevated above the other metatarsal bones at all points, and there was a gradual and even reduction in elevation from the second to the fifth metatarsal. In cases of hallux valgus, however, a variety of deformities were noted in the arc of the second to fifth metatarsals, particularly at the head. The rotation of the first metatarsus and shift of the sesamoids were measured from CT images at the head of the first metatarsus. In hallux valgus, both the rotation and the sesamoid shift appeared to have a wider angle than in the case of normal feet. In normal feet, the differences between the rotation of the first metatarsus and shift of the sesamoids were relatively small, whereas in hallux valgus there was a much greater degree of variation. Furthermore, while normal feet the variation in rotation of the first metatarsus and sesamoid shift both tended to be either great or small, in hallux valgus a large degree of sesamoid shift was sometimes found in combination with a small degree of rotatin of the first metatarsus. (author)

  2. A computerized coal-water slurry transportation model

    Energy Technology Data Exchange (ETDEWEB)

    Ljubicic, B.R.; Trostad, B. [Univ. of North Dakota, Grand Forks, ND (United States); Bukurov, Z.; Cvijanovic, P. [Univ. of Novi Sad (Yugoslavia)

    1995-12-01

    Coal-water fuel (CWF) technology has been developed to the point where full-scale commercialization is just a matter of gaining sufficient market confidence in the price stability of alternate fossil fuels. In order to generalize alternative fuel cost estimates for the desired combinations of processing and/or transportation, a great deal of flexibility is required owing to the understood lack of precision in many of the newly emerging coal technologies. Previously, decisions regarding the sequential and spatial arrangement of the various process steps were made strictly on the basis of experience, simplified analysis, and intuition. Over the last decade, computer modeling has progressed from empirically based correlation to that of intricate mechanistic analysis. Nomograms, charts, tables, and many simple rules of thumb have been made obsolete by the availability of complex computer models. Given the ability to view results graphically in real or near real time, the engineer can immediately verify, from a practical standpoint, whether the initial assumptions and inputs were indeed valid. If the feasibility of a project is being determined in the context of a lack of specific data, the ability to provide a dynamic software-based solution is crucial. Furthermore, the resulting model can be used to establish preliminary operating procedures, test control logic, and train plant/process operators. Presented in this paper is a computerized model capable of estimating the delivered cost of CWF. The model uses coal-specific values, process and transport requirements, terrain factors, and input costs to determine the final operating configuration, bill of materials, and, ultimately, the capital, operating, and unit costs.

  3. Efficacy of virtual computerized tomography laparoscopy for retroperitoneoscopic nephrectomy

    International Nuclear Information System (INIS)

    Shigeta, Masanobu; Kadonishi, Yuichi; Yasumoto, Hiroaki; Mita, Koji; Usui, Tsuguru; Marukawa, Kazushi

    2004-01-01

    Retroperitoneoscopic nephrectomy is less invasive than open nephrectomy, and is an alternative surgical procedure for renal tumors and upper urothelial tumors. We evaluated the efficacy of virtual computerized tomography laparoscopy (VCTL) as a navigator for retroperitoneoscopic nephrectomy to ascertain the correct anatomy of the renal hilum pre-operatively under the retroperitoneoscopic view. Seventy-three kidneys with localized renal tumors (n=44), upper urothelial tumors (n=23), or benign renal disease (n=6) underwent multidetector-row CT. VCTL was carried out by the volume-rendered technique. The findings were compared with those of real retroperitoneoscopy. After the operation, each operator scored 1 to 5 in evaluating the usefulness of virtual retroperitoneoscopy (score 5 indicated very useful). The percentages of renal arteries depicted by VCTL compared with those noted during real surgery were 93% for kidneys with renal tumors, 100% for upper urothelial tumors and 83% for benign renal disease. Two renal arteries of 2 kidneys were not detected by virtual imaging. These were about 1 mm in diameter and directly branched from the aorta, however retroperitoneoscopic nephrectomy was performed uneventfully. VCTL depicted all the renal veins. The anatomy of the renal hilum seen on VCTL and real retroperitoneoscopy was identical, without the minor angle deviation caused by drawing the kidney during the operation. The average score for the usefulness of VCTL was 4.1, ranging from 3 to 5. The accurate surgical anatomy of the renal hilum could be predicted in almost all patients pre-operatively. VCTL is an excellent navigator for retroperitoneoscopic nephrectomy. (author)

  4. Integration of computerized operation support systems on a nuclear power plant environment

    International Nuclear Information System (INIS)

    Jaime, Guilherme D.G.; Almeida, Jose C.S.; Oliveira, Mauro V.

    2015-01-01

    Automation of certain tasks in a Nuclear Power Plant (NPP) control room is expected to result in reduced operators' mental workload, which may induce other benefits such as enhanced situation awareness and improved system performance. The final goal should be higher level of operational safety. Thus, recent works are increasingly assessing automation. The LABIHS compact NPP simulator, though, still operates under strictly manual printed hard-copy procedures, despite of the fact that the simulator incorporates several advancements in design of digitalized Human-Interfaces (HSIs). This work presents the development, implementation and integration of selected components to achieve increased level of computerized/automated operation of the LABIHS compact NPP simulator. Specifically, we discuss three components: (I) Automatic Plant Mode Detection, (II) Automatic Alarm Filtering, and (III) Computerized Procedures. Each one of these components has to be carefully designed/integrated so that one can avoid the undesired effects of some known implementations of automated systems on NPP, such as the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills, which could lead to automation-induced system failures. (author)

  5. Integration of computerized operation support systems on a nuclear power plant environment

    Energy Technology Data Exchange (ETDEWEB)

    Jaime, Guilherme D.G.; Almeida, Jose C.S.; Oliveira, Mauro V., E-mail: gdjaime@ien.gov.br, E-mail: jcsa@ien.gov.br, E-mail: mvitor@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Servico de Sistemas Complexos. Divisao de Engenharia Nuclear

    2015-07-01

    Automation of certain tasks in a Nuclear Power Plant (NPP) control room is expected to result in reduced operators' mental workload, which may induce other benefits such as enhanced situation awareness and improved system performance. The final goal should be higher level of operational safety. Thus, recent works are increasingly assessing automation. The LABIHS compact NPP simulator, though, still operates under strictly manual printed hard-copy procedures, despite of the fact that the simulator incorporates several advancements in design of digitalized Human-Interfaces (HSIs). This work presents the development, implementation and integration of selected components to achieve increased level of computerized/automated operation of the LABIHS compact NPP simulator. Specifically, we discuss three components: (I) Automatic Plant Mode Detection, (II) Automatic Alarm Filtering, and (III) Computerized Procedures. Each one of these components has to be carefully designed/integrated so that one can avoid the undesired effects of some known implementations of automated systems on NPP, such as the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills, which could lead to automation-induced system failures. (author)

  6. Computerized Adaptive Testing in the Bundeswehr

    National Research Council Canada - National Science Library

    Storm, Ernst

    1999-01-01

    ... (draftees, volunteers). In a technical concept of quality control in personnel psychology the minimum standards were defined for the introduction, the utilization, and the control of instruments and procedures...

  7. Computerized tomographic evaluation of primary brain tumors

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jin Ok; Lee, Jong Soon; Jeon, Doo Sung; Kim, Hong Soo; Rhee, Hak Song [Presbyterian Mediacal center, Cheonju (Korea, Republic of); Kim, Jong Deok [Inje Medical College, Paik Hospital, Pusan (Korea, Republic of)

    1985-10-15

    In a study of primary brain tumors 104 cases having satisfactory clinical, operative and histological proofs were analyzed by computerized tomography at Presbyterian Medical Center from May, 1982 to April 1985. The results were as follows: 1. The male to female ratio of primary brain tumor was 54 : 46. 2. The 2nd decade group (26%) was the most prevalent age group, followed by the 5th decade (16.3%), 1st decade (14.4%) , 3rd decade (12.5%), 4th decade (11.5%), 6th decade (10.6%), 7th decade (8.7%) in that order. 3. The incidence of primary brain tumors was found to be: glioma 64 cases (61.6%) among the GM, the most frequent 17 cases (16.3%), followed by meningioma 12 cases (11.5%), pituitary adenoma 10 cases (9.6%), craniopharyngioma 6 cases (5.8%), pinealoma and germinoma 3 cases (2.9%) respectively, and dermoid cyst 2 cases (1.9%) in that order. 4. The location of the primary brain tumors were as follows: cb. hemisphere (49%) of these 24.5% in parietal region, 11.9% in temporal region, 9.7% in frontal region, 3.0% in occipital region: juxtasella area (16.3%), cerebellar hemisphere (8.7%), parapineal and intraventricle (7.7%) respectively, cerebello-pontine angle area (5.8%), vermis and 4th ventricular region (4.8%). 5. There were no remarkable differences in the findings of pre- and post-contrast CT scanning of primary brain tumors computed with others.

  8. Neurosurgical operating computerized tomographic scanner system

    International Nuclear Information System (INIS)

    Okudera, Hiroshi; Sugita, Kenichiro; Kobayashi, Shigeaki; Kimishima, Sakae; Yoshida, Hisashi.

    1988-01-01

    A neurosurgical operating computerized tomography scanner system is presented. This system has been developed for obtaining intra- and postoperative CT images in the operating room. A TCT-300 scanner (manufactured by the Toshiba Co., Tokyo) is placed in the operating room. The realization of a true intraoperative CT image requires certain improvements in the CT scanner and operating table. To adjust the axis of the co-ordinates of the motor system of the MST-7000 microsurgical operating table (manufactured by the Mizuho Ika Co., Tokyo) to the CT scanner, we have designed an interface and a precise motor system so that the computer of the CT scanner can directly control the movement of the operating table. Furthermore, a new head-fixation system has been designed for producing artifact-free intraoperative CT images. The head-pins of the head-fixation system are made of carbon-fiber bars and titanium tips. A simulation study of the total system in the operating room with the CT scanner, operating table, and head holder using a skull model yielded a degree of error similar to that in the phantom testing of the original scanner. Three patients underwent resection of a glial tumor using this system. Intraoperative CT scans taken after dural opening showed a bulging of the cortex, a shift in the central structure, and a displacement of the cortical subarachnoid spaces under the influence of gravity. With a contrast medium the edge of the surrounding brain after resection was enhanced and the residual tumor mass was demonstrated clearly. This system makes it possible to obtain a noninvasive intraoperative image in a situation where structural shifts are taking place. (author)

  9. Determining Women’s Sexual Self-Schemas Through Advanced Computerized Text Analysis

    Science.gov (United States)

    Stanton, Amelia M.; Boyd, Ryan L.; Pulverman, Carey S.; Meston, Cindy M.

    2015-01-01

    The meaning extraction method (MEM), an advanced computerized text analysis technique, was used to analyze women’s sexual self-schemas. Participants (n = 239) completed open-ended essays about their personal feelings associated with sex and sexuality. These essays were analyzed using the MEM, a procedure designed to extract common themes from natural language. Using the MEM procedure, we extracted seven unique themes germane to sexual self-schemas: family and development, virginity, abuse, relationship, sexual activity, attraction, and existentialism. Each of these themes is comprised of frequently used words across the participants’ descriptions of their sexual selves. Significant differences in sexual self-schemas were observed to covary with age, relationship status, and sexual abuse history. PMID:26146161

  10. Determining women's sexual self-schemas through advanced computerized text analysis.

    Science.gov (United States)

    Stanton, Amelia M; Boyd, Ryan L; Pulverman, Carey S; Meston, Cindy M

    2015-08-01

    The meaning extraction method (MEM), an advanced computerized text analysis technique, was used to analyze women's sexual self-schemas. Participants (n=239) completed open-ended essays about their personal feelings associated with sex and sexuality. These essays were analyzed using the MEM, a procedure designed to extract common themes from natural language. Using the MEM procedure, we extracted seven unique themes germane to sexual self-schemas: family and development, virginity, abuse, relationship, sexual activity, attraction, and existentialism. Each of these themes is comprised of frequently used words across the participants' descriptions of their sexual selves. Significant differences in sexual self-schemas were observed to covary with age, relationship status, and sexual abuse history. Copyright © 2015 Elsevier Ltd. All rights reserved.

  11. The effects of mild and severe traumatic brain injury on speed of information processing as measured by the computerized tests of information processing (CTIP).

    Science.gov (United States)

    Tombaugh, Tom N; Rees, Laura; Stormer, Peter; Harrison, Allyson G; Smith, Andra

    2007-01-01

    In spite of the fact that reaction time (RT) measures are sensitive to the effects of traumatic brain injury (TBI), few RT procedures have been developed for use in standard clinical evaluations. The computerized test of information processing (CTIP) [Tombaugh, T. N., & Rees, L. (2000). Manual for the computerized tests of information processing (CTIP). Ottawa, Ont.: Carleton University] was designed to measure the degree to which TBI decreases the speed at which information is processed. The CTIP consists of three computerized programs that progressively increase the amount of information that is processed. Results of the current study demonstrated that RT increased as the difficulty of the CTIP tests increased (known as the complexity effect), and as severity of injury increased (from mild to severe TBI). The current study also demonstrated the importance of selecting a non-biased measure of variability. Overall, findings suggest that the CTIP is an easy to administer and sensitive measure of information processing speed.

  12. A Computerized QC Analysis of TLD Glow Curves for Personal Dosimetry Measurements Using Tag QC Program

    International Nuclear Information System (INIS)

    Primo, S.; Datz, H.; Dar, A.

    2014-01-01

    The External Dosimetry Lab (EDL) at the Radiation Safety Division at Soreq Nuclear Research Center (SNRC) is ISO 17025 certified and provides its services to approximately 13,000 users throughout the country from various sectors such as medical, industrial and academic. About 95% of the users are monitored monthly for X-rays, radiation using Thermoluminescence Dosimeter (TLD) cards that contain three LiF:Mg,Ti elements and the other users, who work also with thermal neutrons, use TLD cards that contain four LiF:Mg,Ti elements. All TLD cards are measured with the Thermo 8800pc reader. Suspicious TLD glow curve (GC) can cause wrong dose estimation so the EDL makes great efforts to ensure that each GC undergoes a careful QC procedure. The current QC procedure is performed manually and through a few steps using different softwares and databases in a long and complicated procedure: EDL staff needs to export all the results/GCs to be checked to an Excel file, followed by finding the suspicious GCs, which is done in a different program (WinREMS), According to the GC shapes (Figure 1 illustrates suitable and suspicious GC shapes) and the ratio between the elements result values, the inspecting technician corrects the data. The motivation for developing the new program is the complicated and time consuming process of our the manual procedure to the large amount of TLDs each month (13,000), similarly to other Dosimetry services that use computerized QC GC analysis. it is important to note that only ~25% of the results are above the EDL recorded level (0.10 mSv) and need to be inspected. Thus, the purpose of this paper is to describe a new program, TagQC, which allows a computerized QC GC analysis that identifies automatically, swiftly, and accurately suspicious TLD GC

  13. Computerized photogrammetry used to calculate the brow position index.

    Science.gov (United States)

    Naif-de-Andrade, Naif Thadeu; Hochman, Bernardo; Naif-de-Andrade, Camila Zirlis; Ferreira, Lydia Masako

    2012-10-01

    The orbital region is of vital importance to facial expression. Brow ptosis, besides having an impact on facial harmony, is a sign of aging. Various surgical techniques have been developed to increase the efficacy of brow-lift surgery. However, no consensus method exists for an objective measurement of the eyebrow position due to the curvature of the face. Therefore, this study aimed to establish a method for measuring the eyebrow position using computerized photogrammetry. For this study, 20 orbital regions of 10 volunteers were measured by direct anthropometry using a digital caliper and by indirect anthropometry (computerized photogrammetry) using standardized digital photographs. Lines, points, and distances were defined based on the position of the anthropometric landmarks endocanthion and exocanthion and then used to calculate the brow position index (BPI). Statistical analysis was performed using Student's t test with a significance level of 5 %. The BPI values obtained by computerized photogrammetric measurements did not differ significantly from those obtained by direct anthropometric measurements (p > 0.05). The mean BPI was 84.89 ± 10.30 for the computerized photogrammetric measurements and 85.27 ± 10.67 for the direct anthropometric measurements. The BPI defined in this study and obtained by computerized photogrammetry is a reproducible and efficient method for measuring the eyebrow position. This journal requires that authors assign a level of evidence to each article.

  14. Computerized videodefecography versus defecography: do we need radiographs?

    Directory of Open Access Journals (Sweden)

    Carlos Walter Sobrado

    Full Text Available CONTEXT AND OBJECTIVE: Defecography has been recognized as a valuable method for evaluating patients with evacuation disorders. It consists of the use of static radiography and fluoroscopy to record different situations within anorectal dynamics. Conventionally, rectal parameters are measured using radiograms. It is rare for fluoroscopy alone to be used. Computer software has been developed with the specific aim of calculating these measurements from digitized videotaped images obtained during fluoroscopy, without the need for radiographic film, thereby developing a computerized videodefecography method. The objective was thus to compare measurements obtained via computerized videodefecography with conventional measurements and to discuss the advantages of the new method. DESIGN AND SETTING: Prospective study at the radiology service of Hospital das Clínicas, Universidade de São Paulo. METHOD: Ten consecutive normal subjects underwent videodefecography. The anorectal angle, anorectal junction, puborectalis muscle length, anal canal length and degree of anal relaxation were obtained via the conventional method (using radiography film and via computerized videodefecography using the ANGDIST software. Measurement and analysis of these parameters was performed by two independent physicians. RESULTS: Statistical analysis confirmed that the measurements obtained through direct radiography film assessment and using digital image analysis (computerized videodefecography were equivalent. CONCLUSIONS: Computerized videodefecography is equivalent to the traditional defecography examination. It has the advantage of offering reduced radiation exposure through saving on the use of radiography.

  15. A formal design verification and validation on the human factors of a computerized information system in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Park, Jae Chang; Cheon, Se Woo; Jung, Kwang Tae; Baek, Seung Min; Han, Seung; Park, Hee Suk; Son, Ki Chang; Kim, Jung Man; Jung Yung Woo

    1999-11-01

    This report describe a technical transfer under the title of ''A formal design verification and validation on the human factors of a computerized information system in nuclear power plants''. Human factors requirements for the information system designs are extracted from various regulatory and industrial standards and guidelines, and interpreted into a more specific procedures and checklists for verifying the satisfaction of those requirements. A formalized implementation plan is established for human factors verification and validation of a computerized information system in nuclear power plants. Additionally, a Computer support system, named as DIMS-web (design Issue Management System), is developed based upon web internet environment so as to enhance the implementation of the human factors activities. DIMS-Web has three maine functions: supporting requirements review, tracking design issues, and management if issues screening evaluation. DIMS-Web shows its benefits in practice through a trial application to the design review of CFMS for YGN nuclear unit 5 and 6. (author)

  16. Imagery Scripts and a Computerized Subtraction Stress Task Both Induce Stress in Methamphetamine Users: A Controlled Laboratory Study

    Directory of Open Access Journals (Sweden)

    Kathleen J. Garrison

    2010-01-01

    Full Text Available Patients treated for methamphetamine (MA dependence have a high rate of relapse, and stress is thought to play a key role. We sought to develop a computerized procedure for experimentally inducing stress in MA users. In a within-subjects design, we compared a computerized subtraction stress task (SST to personalized stress-imagery scripts and a control condition (neutral imagery in 9 former MA users, recruited in San Francisco in 2006–2007. We assessed blood hormone levels, anxiety and craving for MA on visual analog scales, and the Positive and Negative Affect Schedule and made linear mixed-effects models to analyze the results. Both the SST and stress scripts were effective in inducing self-report markers of stress in MA users. Because the SST is easily reproducible and requires less time of staff and participants, it may be a useful alternative for measuring stress reactivity in drug users.

  17. Quality criteria in computerized tomography of the chest

    International Nuclear Information System (INIS)

    Doehring, W.

    1985-01-01

    The quality of thoracical computerized tomography (CT) - like any other CT examination - depends from the quality of the equipment used, from the skill of the examinor and the properties of the patient. Concerning computerized chest tomograms, rapid scan equipment should be used only and slow translation - rotation systems should not be used any more. Whereas the quality of computerized tomograms may be influenced by the patient in the scanning process only, the examining physician will decisively influence the possible informative value of the examination also in the reconstruction of the CT value matrix, in single demonstration of CT values and, possibly, in additional measurement value processing as well as in the interpretation of findings. Use of equipment should always consider the technical potential provided by the equipment to be oriented to the clinical issue, and the conditions preset by the patient. (orig.) [de

  18. Computerized access to materials data. A progress report

    International Nuclear Information System (INIS)

    Rumble, J. Jr.

    1985-01-01

    As the effort to build a comprehensive computerized materials data system grows, it becomes more obvious that the benefits will be far-reaching. During this workshop, the enthusiasm of the participants grew steadily until the questions became not''What,'' but ''When?''. The engineering community within the United States has banded together many times to advance progress in engineering capability. The computerized materials data system requires such an effort, and the rewards will be substantial. Chapter 3 identifies changes in the use of materials data in the Nuclear Power Industry. Chapter 4 describes the EPRI experience in building computerized materials databases. In Chapter 5, the National Materials Property Data Network is discussed. The next four chapters present summaries of the workshop discussions and its conclusions. Chapter 6 discusses the content of the proposed system, Chapter 7 its size and the data sources, and Chapter 8 the user interfaces and system capabilities. In Chapter 9, ways of making further progress are outlined

  19. Quantization Procedures

    International Nuclear Information System (INIS)

    Cabrera, J. A.; Martin, R.

    1976-01-01

    We present in this work a review of the conventional quantization procedure, the proposed by I.E. Segal and a new quantization procedure similar to this one for use in non linear problems. We apply this quantization procedures to different potentials and we obtain the appropriate equations of motion. It is shown that for the linear case the three procedures exposed are equivalent but for the non linear cases we obtain different equations of motion and different energy spectra. (Author) 16 refs

  20. Development of computerized supporting system for emergency response in nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Jae Il

    1992-02-01

    In emergency situation of nuclear power plants, effective use of emergency operating procedures (EOPs) is a crucial part of the emergency response process. However, there are several problems in the emergency operating procedures because of the form of the written procedures. They are voluminous and complicate for effective references under high stress situation. Inevitably, it takes time that could be better spent employing measures to control and stabilize to select the correct procedures and apply the decision logic. In this study, a computerized supporting system has been developed to reduce the operator error possibility under emergency situations of nuclear power plant. Using on-line input parameters, the system can determine the status of the critical safety functions and can find appropriate procedures and necessary operator actions automatically. Moreover, the system can help the operator decision making in the core melt accident situation. By tracking the EOP in an on-line mode, most steps concerning checking or verifying plant state are processed automatically without operator participations. Therefore, the interactions between the system and the operator are simplified significantly and the possibility of human error is reduced

  1. Impact of Multidetector Computerized Tomography (MDCT) On The General Population

    Energy Technology Data Exchange (ETDEWEB)

    Leite, B.B.; Ribeiro, N.C. [Servico de Radiologia, Hospital de Curry Cabral, Rua da Beneficencia, 8, 1069-166 Lisboa (Portugal)

    2009-05-15

    Multidetector computerized tomography (MDCT) appeared in the early 1990s, as a technological evolution of computerized tomography. As one would expect, the evolution continues and, each year, more powerful equipments appear, with new medical applications. However, the general use of this technique has lead to the dramatic increase on the general population irradiation. Special concern is required regarding the most vulnerable groups, like the pediatric population, the pregnant and the young female. Due to a larger awareness of this irradiation risks, some initiatives have been developed, coming from different areas, aiming to maximize the benefit to risk ratio of MDCT. (author)

  2. Recurrent lymph node metastases after craniocervical tumours: Computerized tomography

    International Nuclear Information System (INIS)

    Helmberger, H.; Lenz, M.; Kersting-Sommerhoff, B.; Bautz, W.; Kretz, S.

    1992-01-01

    A total of 544 CT examinations of the craniocervical region carried out in 231 patients were analyzed on a retrospective basis in order to assess the clinical value of contrast-enhanced computerized tomography, being carried out either for comparison with or in combination with clinical control examinations, in the post-therapeutic surveillance of patients treated for craniocervical tumours. The diagnostic accuracy attained with computerized tomography in the detection of recurrent lymph node metastases was 95% and thus superior to that determined for clinical control examinations (80%). (orig./GDG) [de

  3. Computerized integrated data base production system (COMPINDAS)

    Energy Technology Data Exchange (ETDEWEB)

    Marek, D; Buerk, K [Fachinformationszentrum Karlsruhe, Gesellschaft fuer Wissenschaftlich-Technische Information mbH, Eggenstein-Leopoldshafen (Germany)

    1990-05-01

    Based on many years of experience, and with the main objective in mind to guarantee long-term database quality and efficiency of input processes, Fachinformationszentrum Karlsruhe is developing an integrated interactive data management systems for bibliographic and factual databases. Its concept includes the following range of applications: Subject analysis with computer-assisted classification, indexing and translation; technical procedures with online acquisition and management of literature and factual data, recording by means of optical scanning, computer-assisted bibliographic description, control and update procedures; support of the whole process by continuous surveillance of document flow. All these procedures will be performed in an integrated manner. They system is to meet high standards for flexibility, data integrity and effectiveness of system functions. Independent of the type of data, the appropriate database or the subject field to be handled, all data will be stored in one large pool. One main goal is to avoid duplication of work and redundancy of data storage. The system will work online, interactive and conversational. COMPINDAS is being established on the basis of the ADABAS as database management system for storage and retrieval. The applications are being generated by means of aDis of ASTEC in Munich. aDis is used for the definition of the data structures, checking routines, coupling processes, and the design of dialogue and batch routines including masks. (author). 7 figs.

  4. Computerized integrated data base production system (COMPINDAS)

    International Nuclear Information System (INIS)

    Marek, D.; Buerk, K.

    1990-05-01

    Based on many years of experience, and with the main objective in mind to guarantee long-term database quality and efficiency of input processes, Fachinformationszentrum Karlsruhe is developing an integrated interactive data management systems for bibliographic and factual databases. Its concept includes the following range of applications: Subject analysis with computer-assisted classification, indexing and translation; technical procedures with online acquisition and management of literature and factual data, recording by means of optical scanning, computer-assisted bibliographic description, control and update procedures; support of the whole process by continuous surveillance of document flow. All these procedures will be performed in an integrated manner. They system is to meet high standards for flexibility, data integrity and effectiveness of system functions. Independent of the type of data, the appropriate database or the subject field to be handled, all data will be stored in one large pool. One main goal is to avoid duplication of work and redundancy of data storage. The system will work online, interactive and conversational. COMPINDAS is being established on the basis of the ADABAS as database management system for storage and retrieval. The applications are being generated by means of aDis of ASTEC in Munich. aDis is used for the definition of the data structures, checking routines, coupling processes, and the design of dialogue and batch routines including masks. (author). 7 figs

  5. Computerized tabletop games as a form of a video game training for old-old.

    Science.gov (United States)

    Cujzek, Marina; Vranic, Andrea

    2017-11-01

    This research aimed at investigating the utility of a computerized version of a cognitively stimulating activity as a video game intervention for elderly. The study focused on the effect of a 6-week extensive practice intervention on aspects of cognitive functioning (vigilance, working memory (WM), inhibition, reasoning) of old-old participants (N = 29), randomly assigned to trained or active control group. The difference between groups was in the content of the extended video game practice - cognitively complex card game for trained and computerized version of a simple dice-game of chance for control participants. A pretest, posttest and a 4-month follow-up measurement was conducted. Results revealed improvements in both groups, except for improved reasoning found only in trained participants. These results suggest that: (1) improvements are dependent on the complexity of the program, (2) cognitively stimulating activity are a valid training procedure for old-old, (3) novelty of computer use is an important factor in determining training efficacy.

  6. A computerized stroop test for the evaluation of psychotropic drugs in healthy participants.

    Science.gov (United States)

    Pilli, Raveendranadh; Naidu, Mur; Pingali, Usha Rani; Shobha, J C; Reddy, A Praveen

    2013-04-01

    The Stroop paradigm evaluates susceptibility to interference and is sensitive to dysfunction in frontal lobes and drug effects. The aim of the present study was to establish a simple and reliable computerized version of Stroop color-word test, which can be used for screening of various psychotropic drugs. The standardized method was followed in all cases, by recording the reaction time (RT) in msec in 24 healthy participants using computerized version of Stroop color-word test. Reproducibility of the test procedure was evaluated by recording the RTs by a single experimenter on two sessions (interday reproducibility). Validity of the model was further tested by evaluating the psychotropic effect of Zolpidem 5 mg, Caffeine 500 mg, or Placebo on 24 healthy subjects in a randomized, double blind three-way crossover design. The method was found to produce low variability with coefficient of variation less than 10%. Interday reproducibility was very good as shown by Bland-Altman plot with most of the values within ±2SD. There was a significant increase in RTs in Stroop performance with Zolpidem at 1 hr and 2 hrs; in contrast, caffeine significantly decreased RTs in Stroop performance at 1 hr only compared to placebo. The Stroop color-word recording and analysis system is simple, sensitive to centrally acting drug effects, and has potential for future experimental psychomotor assessment studies.

  7. The importance of proper administration and interpretation of neuropsychological baseline and postconcussion computerized testing.

    Science.gov (United States)

    Moser, Rosemarie Scolaro; Schatz, Philip; Lichtenstein, Jonathan D

    2015-01-01

    Media coverage, litigation, and new legislation have resulted in a heightened awareness of the prevalence of sports concussion in both adult and youth athletes. Baseline and postconcussion testing is now commonly used for the assessment and management of sports-related concussion in schools and in youth sports leagues. With increased use of computerized neurocognitive sports concussion testing, there is a need for standards for proper administration and interpretation. To date, there has been a lack of standardized procedures by which assessments are administered. More specifically, individuals who are not properly trained often interpret test results, and their methods of interpretation vary considerably. The purpose of this article is to outline factors affecting the validity of test results, to provide examples of misuse and misinterpretation of test results, and to communicate the need to administer testing in the most effective and useful manner. An increase in the quality of test administration and application may serve to decrease the prevalence of invalid test results and increase the accuracy and utility of baseline test results if an athlete sustains a concussion. Standards for test use should model the American Psychological Association and Centers for Disease Control and Prevention guidelines, as well as the recent findings of the joint position paper on computerized neuropsychological assessment devices.

  8. Método computadorizado para medida da acuidade visual A computerized method for visual acuity assessment

    Directory of Open Access Journals (Sweden)

    Patrícia Katayama Kjaer Arippol

    2006-12-01

    assessment with optotypes arranged as those of printed logarithmic charts used in ophthalmic clinic. Ninety seven-year-old students, 8 normal adult volunteers and 10 patients from the Strabismus sector of the Federal University of São Paulo were evaluated by the same examiner and submitted to the visual acuity test through printed visual acuity logarithmic tumble "E" chart and the new computerized test at the same time. Written consent was obtained after clarification about the research project. RESULTS: Statistical analysis showed excellent correlation between the two methods (r>0.75 besides the slight trend of the computerized test to overestimate visual acuity when compared with the gold standard. Sensitivity of the computerized test was 100% (correctly identified 6 eyes with poor visual acuity and specificity was 94%. CONCLUSION: The computerized test can be used as a new clinical tool for visual acuity screening of school-age children and it is fast, easy to perform and inexpensive, besides being more attractive for children. The method releases the examiner from the interpretation of the subject's answers and ensures the procedure's standardization even when more than one examiner performs the test. To better understand the effectiveness of this method for visual screening, one option would be to introduce it in elementary schools, after training the teachers to perform this test.

  9. Procedures simulation in Nuclear Power Plants (SIMPROC); Codigo para la simulacion de procedimientos humanos en centrales nucleares: SIMPROC

    Energy Technology Data Exchange (ETDEWEB)

    Izquierdo, J. M.; Hortal, J.; Sanchez, M.; Melendez, E.; Queral, C.; Ibanez, L.; Gil, J.; Fernandez, I.; Murcia, S.; Gomez, J.

    2010-07-01

    SIMPROC, a procedure simulator support in rules, is an Indizen product whose procedure computerization is based in XML. It's a compliment for the traditional methods of procedures evaluation and it's connected to SCAIS (Code System for an Integrate Security Analysis).

  10. Coupling two iteratives algorithms for density measurements by computerized tomography

    International Nuclear Information System (INIS)

    Silva, L.E.M.C.; Santos, C.A.C.; Borges, J.C.; Frenkel, A.D.B.; Rocha, G.M.

    1986-01-01

    This work develops a study for coupling two iteratives algotithms for density measurements by computerized tomography. Tomographies have been obtained with an automatized prototype, controled by a microcomputer, projected and assembled in the Nuclear Instrumentation Laboratory, at COPPE/UFRJ. Results show a good performance of the tomographic system, and demonstrate the validity of the method of calculus adopted. (Author) [pt

  11. Multidimensional Computerized Adaptive Testing for Indonesia Junior High School Biology

    Science.gov (United States)

    Kuo, Bor-Chen; Daud, Muslem; Yang, Chih-Wei

    2015-01-01

    This paper describes a curriculum-based multidimensional computerized adaptive test that was developed for Indonesia junior high school Biology. In adherence to the Indonesian curriculum of different Biology dimensions, 300 items was constructed, and then tested to 2238 students. A multidimensional random coefficients multinomial logit model was…

  12. Evaluation of the absorbed dose in odontological computerized tomography

    International Nuclear Information System (INIS)

    Legnani, Adriano; Schelin, Hugo R.; Rocha, Anna Silvia P.S. da; Khoury, Helen J.

    2011-01-01

    This paper evaluated the absorbed dose at the surface entry known as 'cone beam computed tomography' (CBCT) in odontological computerized tomography. Examination were simulated with CBCT for measurements of dose. A phantom were filled with water, becoming scatter object of radiation. Thermoluminescent dosemeters were positioned on points correspondent to eyes and salivary glands

  13. Wilderness Management... A Computerized System for Summarizing Permit Information

    Science.gov (United States)

    Gary H. Elsner

    1972-01-01

    Permits were first needed for visits to wilderness areas in California during summer 1971. A computerized system for analyzing these permits and summarizing information from them has been developed. It produces four types of summary tables: point-of-origin of visitors; daily variation in total number of persons present; variations in group size; and variations in...

  14. The computerized patient record: Where do we stand?

    NARCIS (Netherlands)

    Jaspers, M. W. M.; Knaup, P.; Schmidt, D.

    2006-01-01

    OBJECTIVES: To provide an overview of trends in research, developments and implementations of the computerized patient record (CPR) of the last two years. METHODS: We surveyed the medical informatics literature, spanning the years 2004-2005, focusing on publications on CPRs. RESULTS: The main trends

  15. Computerized tomography in the examination of the orbit

    International Nuclear Information System (INIS)

    Ammerich, H.; Wackenheim, A.; Golabek, R.

    1980-01-01

    The importance of computerized tomography in the ophtalmological diagnosis is discussed. A great value of the information obtained by this not cumbersome method is stressed. The findings achieved this method in the most frequent diseases of the eyeball, orbit and neighbouring anatomical structures are described. (author)

  16. Contribution of computerized tomography to orbit fracture diagnosis

    International Nuclear Information System (INIS)

    Nemeth, T.; Sobota, J.

    1984-01-01

    Suitability and specificity of examinations using computerized tomography are discussed for diagnoses fractures of the orbit including accurate anatomical localization of traumatic changes. The possibility of accurate assessment of the drop of the floor of the orbit which is essential for determination of the thickness of the bone or cartilaginous graft under the eyeball is also important

  17. Development and validation of the computerized family relations

    NARCIS (Netherlands)

    Skoczen, I.; Cieciuch, J.; Oud, J.H.L.; Welzen, K.F.

    2015-01-01

    The aim of the present study was to develop and investigate the psychometric properties of the Computerized Family Relations Test (CFRT) for children. This test assesses the quality of family relationships with the mother and father from a child's perspective. The CFRT consists of six scales

  18. Serial assessment of doxorubicin cardiomyopathy with the computerized scintillation probe

    International Nuclear Information System (INIS)

    Strashun, A.; Goldsmith, S.J.; Horowitz, S.F.

    1982-01-01

    Cardiac function was serially monitored in 55 patients receiving adriamycin chemotherapy over 18 months with quantitative radionuclide assessment by both a nonimaging computerized scintillation probe and gamma camera-computer imaging. Interval ejection fraction change was comparable with both techniques and predicted incipient cardiotoxicity. Probe data revealed ejection fraction decline was antedated by decline left ventricular emptying and filling rates

  19. Emission computerized-tomography and determination of local brain function

    International Nuclear Information System (INIS)

    Kuhl, D.E.; Alavi, A.; Reivich, M.; Edwards, R.Q.; Fenton, C.A.; Zimmerman, R.A.

    1975-01-01

    Methods for the three dimensional reconstruction of /sup 99m/Tc brain scans are described. The diagnostic advantages of computerized tomography in the localization of brain tumors and in measurements of local cerebral blood flow are discussed. (U.S.)

  20. Cranial Computerized Tomography In The Evaluation Of Stroke ...

    African Journals Online (AJOL)

    206 patients clinically diagnosed as stroke / cerebrovascular accidents (CVA) were investigated using computerized tomography (CT) scan. 19 patients (9%) had normal scan. While 20(9.7%) had other lesions including atrophy and tumours. Of the 167 (18. %) patients proven to have suffered a cerebro- vascular accident ...

  1. The Pattern of Significant Lesions Found in Computerized ...

    African Journals Online (AJOL)

    Introduction: Seizures are common reasons for neurologic consultations and investigations. In the absence of magnetic resonance imaging, computerized tomography scanning of the brain is a reliable and cheaper alternative. Little is known about the pattern of brain lesions in patients with recurrent seizures in Nigeria.

  2. Computerized tomographic findings in children with head trauma in ...

    African Journals Online (AJOL)

    Objective: To describe the computerized tomographic findings in children with head trauma who presented at the University of Benin Teaching Hospital, Benin City, Nigeria. Methods: It is a retrospective review of patients aged 0 – 15 years with suspected intracranial injury (ICI) following head trauma, who presented for CT ...

  3. Significance of computerized tomography and nasal cytology in the ...

    African Journals Online (AJOL)

    Ehab

    assessment of sinus disease in asthmatic children. Rhinosinusitis is a common asthma comorbidity. Nasal eosinophil or neutrophil score >0.5 provides a better predictive value for rhinosinusitis compared to total serum IgE. Keywords: computerized tomography, nasal sinus, asthma, sinusitis, allergic rhinitis, children.

  4. The Pattern of Significant Lesions Found in Computerized ...

    African Journals Online (AJOL)

    2017-12-05

    Dec 5, 2017 ... Introduction: Seizures are common reasons for neurologic consultations and investigations. In the absence of magnetic resonance imaging, computerized tomography scanning of the brain is a reliable and cheaper alternative. Little is known about the pattern of brain lesions in patients with recurrent ...

  5. Towards Computerized Adaptive Assessment Based on Structured Tasks

    NARCIS (Netherlands)

    Tvarožek, Jozef; Kravcik, Milos; Bieliková, Mária

    2008-01-01

    Tvarožek, J., Kravčík, M., & Bieliková, M. (2008). Towards Computerized Adaptive Assessment Based on Structured Tasks. In W. Nejdl et al. (Eds.), Adaptive Hypermedia and Adaptive Web-Based Systems (pp. 224-234). Springer Berlin / Heidelberg.

  6. Robinson's computerized model of eye muscle mechanics revised.

    NARCIS (Netherlands)

    H.J. Simonsz (Huib)

    1994-01-01

    textabstractThe computerized model of static eye-muscle mechanics developed by Robinson was revised extensively and improved. An extensive literature study yielded additional information on the average diameter of the eye as related to age, on the average location of the insertions and origins of

  7. Radiation exposure of the gonads in infant brain computerized tomography

    International Nuclear Information System (INIS)

    Berndt, L.; Rosenkranz, G.; Tellkamp, H.

    1988-01-01

    In 61 babies and infants the gonadal dose due to brain computerized tomography was determined over the symphysis by thermoluminescent dosimetry. The average radiation dose was 43 mGy corresponding with data reported. Shielding of the testes in infants is an additional burden and worth discussing because of the low absolute gonadal dose

  8. Quality control of online calibration in computerized assessment

    NARCIS (Netherlands)

    Glas, Cornelis A.W.

    In computerized adaptive testing, updating item parameter estimates using adaptive testing data is often called online calibration. This study investigated how to evaluate whether the adaptive testing data used for online calibration sufficiently fit the item response model used. Three approaches

  9. Computerized x-ray radiographic system for fuel pellet measurements

    International Nuclear Information System (INIS)

    Green, D.R.; Karnesky, R.A.; Bromley, C.

    1977-01-01

    The development and operation of a computerized system for determination of fuel pellet diameters from x-ray radiography is described. Actual fuel pellet diameter measurements made with the system are compared to micrometer measurements on the same pellets, and statistically evaluated. The advantages and limitations of the system are discussed, and recommendations are made for further development

  10. A Computerized Clinical Support System and Psychological Laboratory.

    Science.gov (United States)

    Cassel, Russell N.

    1978-01-01

    Advocating "holistic" medicine, this article details the benefits to be derived from using a computerized clinical support system in a psychological laboratory focusing on internal healing where the client/patient becomes a committed partner utilizing biofeedback equipment, gaming, and simulation to achieve self-understanding and…

  11. Use of computerized tomography and magnetic resonance imaging

    International Nuclear Information System (INIS)

    Tjoerstad, K.

    1992-01-01

    This is a neurologist's opinion on how computerized tomography and magnetic resonance imaging have improved the doctor's diagnostic possibilities, changed patient/doctor relationship and increased the patients' expectations from diagnostic tests. How should the often conflicting interests of patients, society and doctors be handled? 15 refs., 1 fig., 1 tab

  12. Radio astronomical interferometry and x-ray's computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, L F [Universidad Nacional Autonoma de Mexico, Mexico City. Inst. de Astronomia

    1982-01-01

    Radio astronomical interferometry and computerized tomography are techniques of great importance for astronomy and medicine, respectively. In this paper we emphasize that both techniques are based on the same mathematical principles, and present them as an example of interaction between basic and applied science.

  13. Quality control of on-line calibration in computerized assessment

    NARCIS (Netherlands)

    Glas, Cornelis A.W.

    1998-01-01

    In computerized adaptive testing, updating parameter estimates using adaptive testing data is often called online calibration. In this paper, how to evaluate whether the adaptive testing model used for online calibration fits the item response model used sufficiently is studied. Three approaches are

  14. Multiple Maximum Exposure Rates in Computerized Adaptive Testing

    Science.gov (United States)

    Ramon Barrada, Juan; Veldkamp, Bernard P.; Olea, Julio

    2009-01-01

    Computerized adaptive testing is subject to security problems, as the item bank content remains operative over long periods and administration time is flexible for examinees. Spreading the content of a part of the item bank could lead to an overestimation of the examinees' trait level. The most common way of reducing this risk is to impose a…

  15. Monkeys Exhibit Prospective Memory in a Computerized Task

    Science.gov (United States)

    Evans, Theodore A.; Beran, Michael J.

    2012-01-01

    Prospective memory (PM) involves forming intentions, retaining those intentions, and later executing those intended responses at the appropriate time. Few studies have investigated this capacity in animals. Monkeys performed a computerized task that assessed their ability to remember to make a particular response if they observed a PM cue embedded…

  16. Sequential Computerized Mastery Tests--Three Simulation Studies

    Science.gov (United States)

    Wiberg, Marie

    2006-01-01

    A simulation study of a sequential computerized mastery test is carried out with items modeled with the 3 parameter logistic item response theory model. The examinees' responses are either identically distributed, not identically distributed, or not identically distributed together with estimation errors in the item characteristics. The…

  17. Computerized spirography and roentgenopneumopolygraphy in diagnosis of tracheobroncheal dyskinesia

    International Nuclear Information System (INIS)

    Gladkij, A.V.; Gul'ko, S.I.; Vyalyj, N.P.; Salivon, A.P.; Orlovskaya, I.I.

    1991-01-01

    The results of comprehensive examination of respiratory organs in 103 patients with hypotonic dyskinesia syndrome of trachea and large bronchi were presented. The comprehensive examination included computerized spirography and roentgenopneumopolygraphy with additional tests: exercise and drug. It was shown that the conducted comprehensive examination helped to receive an information about breathh physiology, to diagnose tracheobroncheal dyskinesia and to evaluate the degree of ventilation disorders

  18. Benefits of a relational database for computerized management

    International Nuclear Information System (INIS)

    Shepherd, W.W.

    1991-01-01

    This paper reports on a computerized relational database which is the basis for a hazardous materials information management system which is comprehensive, effective, flexible and efficient. The system includes product information for Material Safety Data Sheets (MSDSs), labels, shipping, and the environment and is used in Dowell Schlumberger (DS) operations worldwide for a number of programs including planning, training, emergency response and regulatory compliance

  19. Antipsychotic treatment in schizophrenia: the role of computerized neuropsychological assessment.

    Science.gov (United States)

    Kertzman, Semion; Reznik, Ilya; Grinspan, Haim; Weizman, Abraham; Kotler, Moshe

    2008-01-01

    The present study analyzes the role of neurocognitive assessment instruments in the detection of the contribution of antipsychotic treatment to cognitive functioning. Recently, a panel of experts suggested six main domains (working memory; attention/vigilance; verbal/visual learning and memory; reasoning and problem solving; speed of processing) implicated in schizophrenia-related cognitive deficits, which serve as a theoretical base for creation of real-time computerized neurocognitive batteries. The high sensitivity of computerized neuropsychological testing is based on their ability to adopt the reaction time (RT) paradigm for the assessment of brain function in a real-time regime. This testing is highly relevant for the monitoring of the cognitive effects of antipsychotics. Computerized assessment assists in the identification of state- and trait-related cognitive impairments. The optimal real-time computerized neurocognitive battery should composite balance between broad and narrow coverage of cognitive domains relevant to the beneficial effects of antipsychotics and will enable better planning of treatment and rehabilitation programs.

  20. 45 CFR 307.25 - Review and certification of computerized support enforcement systems.

    Science.gov (United States)

    2010-10-01

    ..., DEPARTMENT OF HEALTH AND HUMAN SERVICES COMPUTERIZED SUPPORT ENFORCEMENT SYSTEMS § 307.25 Review and certification of computerized support enforcement systems. The Office will review, assess and inspect the... 45 Public Welfare 2 2010-10-01 2010-10-01 false Review and certification of computerized support...

  1. Morphological analysis of the vestibular aqueduct by computerized tomography images

    International Nuclear Information System (INIS)

    Marques, Sergio Ricardo; Smith, Ricardo Luiz; Isotani, Sadao; Alonso, Luis Garcia; Anadao, Carlos Augusto; Prates, Jose Carlos; Lederman, Henrique Manoel

    2007-01-01

    Objective: In the last two decades, advances in the computerized tomography (CT) field revise the internal and medium ear evaluation. Therefore, the aim of this study is to analyze the morphology and morphometric aspects of the vestibular aqueduct on the basis of computerized tomography images (CTI). Material and method: Computerized tomography images of vestibular aqueducts were acquired from patients (n = 110) with an age range of 1-92 years. Thereafter, from the vestibular aqueducts images a morphometric analysis was performed. Through a computerized image processing system, the vestibular aqueduct measurements comprised of its area, external opening, length and the distance from the vestibular aqueduct to the internal acoustic meatus. Results: The morphology of the vestibular aqueduct may be funnel-shaped, filiform or tubular and the respective proportions were found to be at 44%, 33% and 22% in children and 21.7%, 53.3% and 25% in adults. The morphometric data showed to be of 4.86 mm 2 of area, 2.24 mm of the external opening, 4.73 mm of length and 11.88 mm of the distance from the vestibular aqueduct to the internal acoustic meatus, in children, and in adults it was of 4.93 mm 2 , 2.09 mm, 4.44 mm, and 11.35 mm, respectively. Conclusions: Computerized tomography showed that the vestibular aqueduct presents high morphological variability. The morphometric analysis showed that the differences found between groups of children and adults or between groups of both genders were not statistically significant

  2. Proposal for dose measurement in the crystalline lens and thyroid in computerized tomography of paranasal sinuses

    International Nuclear Information System (INIS)

    Mello, Ana Caroline; Machado Neto, Vicente

    2014-01-01

    With the evolution of diagnostic imaging equipment, a computerized tomography (CT) has become one of the most used tests to assess pathologies affecting the paranasal sinuses. This work aims at presenting a method of obtaining measurements of dose in the eye lenses and thyroid, from the execution of CT of the paranasal sinuses protocol. Experimental procedure will be used in an object simulator (phantom) head and neck made with accessible materials and thermoluminescent dosimeters (TLDs) of LiF: Mg,Ti for the absorbed dose in the regions of interest, when exposed to radiation in a CT scanner 16 channels. After the dosimetric evaluation with phantom use, this methodology will be applied in vivo, or in patients with medical request for the examination and approval by the Ethics Committee. Thus, at the end of this survey protocols and actions aimed at reducing the absorbed dose in the eye lenses and thyroid without impairing the diagnostic image quality can be proposed. (author)

  3. Statistical evaluation of the dose-distribution charts of the National Computerized Irradiation Planning Network

    International Nuclear Information System (INIS)

    Varjas, Geza; Jozsef, Gabor; Gyenes, Gyoergy; Petranyi, Julia; Bozoky, Laszlo; Pataki, Gezane

    1985-01-01

    The establishment of the National Computerized Irradiation Planning Network allowed to perform the statistical evaluation presented in this report. During the first 5 years 13389 dose-distribution charts were calculated for the treatment of 5320 patients, i.e. in average, 2,5 dose-distribution chart-variants per patient. This number practically did not change in the last 4 years. The irradiation plan of certain tumour localizations was performed on the basis of the calculation of, in average, 1.6-3.0 dose-distribution charts. Recently, radiation procedures assuring optimal dose-distribution, such as the use of moving fields, and two- or three-irradiation fields, are gaining grounds. (author)

  4. Development of a computerized data base for low-level waste leaching data

    International Nuclear Information System (INIS)

    Dougherty, D.R.; Colombo, P.

    1987-01-01

    A computerized data base (db) of low-level waste (LLW) leaching data is being compiled by Brookhaven National Laboratory under contract to the DOE Low-Level Waste Management Program. Although this db is being compiled as part of an effort to develop accelerated leach test procedures for LLW forms, other involved in LLW management may find it useful. The db is implemented on an IBM PC XT and is self-contained in that its data manipulation and analysis programs are not proprietary (i.e., need not be purchased). The db includes data from the Accelerated Leach Test(s) Program plus selected literature data, which have been selected based on criteria that include completeness of the experimental description and elucidation of leaching mechanisms. 6 references, 5 figures, 3 tables

  5. Nuclear computerized library for assessing reactor reliability (NUCLARR): Part 2, Guide to operations: User's guide

    International Nuclear Information System (INIS)

    Gilmore, W.E.; Gentillon, C.D.; Gertman, D.I.; Beers, G.H.; Galyean, W.J.; Gilbert, B.G.

    1988-06-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal micro-computer. NUCLARR can be used by the end user to furnish data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. Volume IV of this series is the User's Guide for operating the NUCLARR software and is presented in three parts. This volume, Part 2: Guide to Operations, contains the instructions and basic procedures for using the NUCLARR software. Part 2 provides guidance and information for getting started, performing the desired functions, and making the most efficient use of the system's features

  6. The use of inverse systems in computerized operator support systems for load-following control

    International Nuclear Information System (INIS)

    Klebau, J.; Hentschel, B.; Ziegenbein, D.

    1987-01-01

    The basic problem in load-following control of nuclear power reactors consists in calculation of control rod movement to realize desired local power density distribution in the reactor. Well-known solutions are based on optimal control theory. The paper describes the concept of systems inverses which makes it possible to solve the load-following control problem not in an optimal but in an 'ideal' way, vanishing the optimization criterion of the classical approaches. The advantages of inverse systems are simple calculation procedures, low on-line-storage capacity and low on-line computational amount. This makes it attractive to use inverse systems in computerized operator support systems. 19 refs. (author)

  7. A Method of Retrospective Computerized System Validation for Drug Manufacturing Software Considering Modifications

    Science.gov (United States)

    Takahashi, Masakazu; Fukue, Yoshinori

    This paper proposes a Retrospective Computerized System Validation (RCSV) method for Drug Manufacturing Software (DMSW) that relates to drug production considering software modification. Because DMSW that is used for quality management and facility control affects big impact to quality of drugs, regulatory agency required proofs of adequacy for DMSW's functions and performance based on developed documents and test results. Especially, the work that explains adequacy for previously developed DMSW based on existing documents and operational records is called RCSV. When modifying RCSV conducted DMSW, it was difficult to secure consistency between developed documents and test results for modified DMSW parts and existing documents and operational records for non-modified DMSW parts. This made conducting RCSV difficult. In this paper, we proposed (a) definition of documents architecture, (b) definition of descriptive items and levels in the documents, (c) management of design information using database, (d) exhaustive testing, and (e) integrated RCSV procedure. As a result, we could conduct adequate RCSV securing consistency.

  8. Computerized tomography and staging of bladder tumors

    International Nuclear Information System (INIS)

    Wozniak, A.; Luongo, A.; Nogueira, A.

    1982-01-01

    Computed Tomography (CT) has been employed in 13 patients with bladder tumors; 8 of them subsequently underwent surgery. Concordance between CT and pathological staging ranged in 90% of accurate results. Our data are discussed and compared to those of other authors in the literature. Staging was carried out according to the International Union Against Cancer. CT proved to be very accurate in the assessment of local and regional spread of tumor, limphatic progression and early detection of ureteral obstruction, as well as diagnosis of distant metastasis in selected patients. In poor candidates for surgery CT provided invaluable data to be used for localizing fields of radiation therapy. CT is a very well tolerated procedure, it is therefore suitable in subsequent treatment control. (Author) [pt

  9. Computerized tests to evaluate recovery of cognitive function after deep sedation with propofol and remifentanil for colonoscopy.

    Science.gov (United States)

    Borrat, Xavier; Ubre, Marta; Risco, Raquel; Gambús, Pedro L; Pedroso, Angela; Iglesias, Aina; Fernandez-Esparrach, Gloria; Ginés, Àngels; Balust, Jaume; Martínez-Palli, Graciela

    2018-03-27

    The use of sedation for diagnostic procedures including gastrointestinal endoscopy is rapidly growing. Recovery of cognitive function after sedation is important because it would be important for most patients to resume safe, normal life soon after the procedure. Computerized tests have shown being accurate descriptors of cognitive function. The purpose of the present study was to evaluate the time course of cognitive function recovery after sedation with propofol and remifentanil. A prospective observational double blind clinical study conducted in 34 young healthy adults undergoing elective outpatient colonoscopy under sedation with the combination of propofol and remifentanil using a target controlled infusion system. Cognitive function was measured using a validated battery of computerized cognitive tests (Cogstate™, Melbourne, Australia) at different predefined times: prior to starting sedation (Tbaseline), and then 10 min (T10), 40 min (T40) and 120 min (T120) after the end of colonoscopy. Tests included the assessment of psychomotor function, attention, visual memory and working memory. All colonoscopies were completed (median time: 26 min) without significant adverse events. Patients received a median total dose of propofol and remifentanil of 149 mg and 98 µg, respectively. Psychomotor function and attention declined at T10 but were back to baseline values at T40 for all patients. The magnitude of psychomotor task reduction was large (d = 0.81) however 100% of patients were recovered at T40. Memory related tasks were not affected 10 min after ending sedation. Cognitive impairment in attention and psychomotor function after propofol and remifentanil sedation was significant and large and could be easily detected by computerized cognitive tests. Even though, patients were fully recovered 40 min after ending the procedure. From a cognitive recovery point of view, larger studies should be undertaken to propose adequate criteria for discharge

  10. How to Train an Injured Brain? A Pilot Feasibility Study of Home-Based Computerized Cognitive Training.

    Science.gov (United States)

    Verhelst, Helena; Vander Linden, Catharine; Vingerhoets, Guy; Caeyenberghs, Karen

    2017-02-01

    Computerized cognitive training programs have previously shown to be effective in improving cognitive abilities in patients suffering from traumatic brain injury (TBI). These studies often focused on a single cognitive function or required expensive hardware, making it difficult to be used in a home-based environment. This pilot feasibility study aimed to evaluate the feasibility of a newly developed, home-based, computerized cognitive training program for adolescents who suffered from TBI. Additionally, feasibility of study design, procedures, and measurements were examined. Case series, longitudinal, pilot, feasibility intervention study with one baseline and two follow-up assessments. Nine feasibility outcome measures and criteria for success were defined, including accessibility, training motivation/user experience, technical smoothness, training compliance, participation willingness, participation rates, loss to follow-up, assessment timescale, and assessment procedures. Five adolescent patients (four boys, mean age = 16 years 7 months, standard deviation = 9 months) with moderate to severe TBI in the chronic stage were recruited and received 8 weeks of cognitive training with BrainGames. Effect sizes (Cohen's d) were calculated to determine possible training-related effects. The new cognitive training intervention, BrainGames, and study design and procedures proved to be feasible; all nine feasibility outcome criteria were met during this pilot feasibility study. Estimates of effect sizes showed small to very large effects on cognitive measures and questionnaires, which were retained after 6 months. Our pilot study shows that a longitudinal intervention study comprising our novel, computerized cognitive training program and two follow-up assessments is feasible in adolescents suffering from TBI in the chronic stage. Future studies with larger sample sizes will evaluate training-related effects on cognitive functions and underlying brain structures.

  11. A minimax sequential procedure in the context of computerized adaptive mastery testing

    NARCIS (Netherlands)

    Vos, Hendrik J.

    1997-01-01

    The purpose of this paper is to derive optimal rules for variable-length mastery tests in case three mastery classification decisions (nonmastery, partial mastery, and mastery) are distinguished. In a variable-length or adaptive mastery test, the decision is to classify a subject as a master, a

  12. Developments of methods for computerized configuration control

    International Nuclear Information System (INIS)

    Kafka, P.

    1997-01-01

    It is known that Probabilistic Safety Assessment (PSA) is nowadays the appropriate technology and tool that can be used to optimize, during the design phase, a considered installation taking into account reliability and safety aspects, and also to evaluate and quantify the base-line risk level for the optimized installation. This base-line risk level is normally expressed by an average frequency per plant-year assigned to a scenario of interest (e.g. core damage, in case of a NPP). A considerable number of changes in components and system design can occur during the construction phase and another during the subsequent operation phase due to a continuous change in the plant configurations and their operating procedures, when compared to the configuration considered for the base-line risk quantification. These changes can be originated by planned activities like tests, maintenance and repair or by unplanned actions, mainly random events (failures) on components and systems. This results in a fluctuation of the risk level over operating time and is denominated as the ''risk profile'' (RP) of the installation. Living PSA and risk monitoring programs can assess the RP. An adequate management tool, calculating the ''risk profile'', can be used to control and optimize the operation of the installation with respect to a minimal risk level over the operating time. As a result we obtained a so called fault tolerant operation. 30 refs, 1 tab, figs

  13. Study of computerized tomography using neutron beam

    International Nuclear Information System (INIS)

    Pereira, W.W.

    1991-05-01

    This paper aims to demonstrate the advantages, shortcomings and complementaries of a tomography development using neutrons over the one employing gamma rays in the context of their applications to non destructive essays. A simulated experimental study was performed in order to compare the two aforementioned tomographic procedures as applied to some materials. These materials were chosen for their clear advantages and complementaries as, for instance, aluminium, iron, plastic and aluminium hydroxide. In this work two tomographic systems, are employed both with parallel beams. The first with a gamma radiation source (Caesium-137), with an energy of 662 KeV and an activity of 3,9 x 10 9 Bq (100 mCi) and the second one employing a neutron source, the Argonaut Reactor of the Instituto de Engenharia Nuclear, IEN/CNEN, from where the thermal neutron beam of about 10 5 n/(cm.s) was obtained. It is possible to conclude from the simulated and experimental results, by means of image analysis and distortion measurements, that for a given material the adequate radiation and its energy may be chosen so as to better characterize it. (author)

  14. Strategies of reconstruction algorithms for computerized tomography

    International Nuclear Information System (INIS)

    Garderet, P.

    1984-10-01

    Image reconstruction from projections has progressively spread out over all fields of medical imaging. As the mathematical aspects of the problem become more and more comprehensively explored a great variety of numerical solutions have been developed best suited to such-and-such imaging medical application and taking into account the physical phenomena related to data collection (a priori properties for signal and noise). The purpose of that survey is to present the general mathematical frame and the fundamental assumptions of various strategies; Fourier methods approximate explicit deterministic inversion formula for the Radon transform. Algebraic reconstruction techniques set up an a priori discrete model through a series expansion approach of the solution. The numerical system to be solved is huge when a fine grid of pixels is to be reconstructed; iterative solutions may then be found. Recently some least square procedures have been shown to be tractable which avoid the use of iterative methods. Finally maximum like hood approach incorporates accurately the Poisson nature of photon noise and are well adapted to emission computed tomography. The various strategies will be analysed from both aspects of theoretical assumptions needed for suitable use and of computing facilities, actual performance and cost. In the end we take a glimpse of the extension of the algorithms from two dimensional imaging to fully three dimensional volume analysis in preparation of the future medical imaging technologies

  15. Validation of the computerized annunciation message list system (CAMLS)

    Energy Technology Data Exchange (ETDEWEB)

    Feher, M P; Davey, E C; Lupton, L R [AECL, Chalk River Labs., Chalk River, ON (Canada)

    1997-09-01

    The Computerized Annunciation Message List System is a computerized annunciation system for the control rooms of nuclear generating stations. CAMLS will alert operators to changes in plant conditions that may impact on safety and production and help staff to effectively respond. CAMLS is designed to: provide a clear and concise overview of the current problems or faults in the plant; provide an overview of the current state of the plant in terms of automatic process and equipment actions; provide support for specific operational tasks, through either pre-configured or operator-configured annunciation displays, including: rapid and efficient upset response, plant stabilization, problem diagnosis, recovery action planning and implementation, and rapid recovery from trip and return to power operation. To achieve this, several information processing, presentation,a nd interaction concepts were developed. 2 refs, 6 figs, 7 tabs.

  16. Computerized tomography in diffuse diseases of the liver. Pt. 2

    International Nuclear Information System (INIS)

    Helmberger, H.; Vogel, U.; Bautz, W.

    1993-01-01

    Computerized tomography is a first-line method of imaging to confirm diffuse disorders of the liver suggested by preliminary clinical and biochemical findings. If the disease is caused by an obstructed vessel, this is reliably detected. For most types of thesaurismosis as well as hepatic steatosis and cirrhosis of the liver approaches to quantitative determinations of the spread of disease have been described in theory but so far failed to show great merits in practice. The transition from hepatic fibrosis to cirrhosis as the final developmental stage common to all those disorders has typical features on computerized tomography. This explains why the use of this method in diffuse hepatic disease offers particular advantages as regards the detection of complications occurring at an advanced stage ot the diagnosis of changes developing into malignancies. (orig.) [de

  17. Computerized axial tomography : the tool in osseointegrated dental implants

    International Nuclear Information System (INIS)

    Fernandez-Lopez, Otton

    2002-01-01

    Failure rates in rehabilitations with osseointegrated implants are handled through appropriate radiographic preoperative planning. The appropriate length of the implant without running the risk of a perforation of vital structures, has been determined by a radiographic diagnosis. Computerized and conventional axial tomography have proved to be invaluable elements for pre-surgical evaluation. A radiologic guidance is elaborated to perform a computerized axial tomography (CT) of maxillary bones in totally edentulous patients. Surgical guides are constructed from a wax-up emanated from the information of the CT. The CT has proven to be an radiographic indispensable element to achieve the surgical-prosthetic success in osseointegrated dental implants. The CT has allowed the realization of a precise wax-up for making of surgical guide and a precise temporary prostheses in positioning of osseointegrated implants, with the consequent saving time and money for the rehabilitator and patient [es

  18. Computerized reactor monitor and control for nuclear reactors

    International Nuclear Information System (INIS)

    Buerger, L.

    1982-01-01

    The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

  19. Transformations and algorithms in a computerized brain atlas

    International Nuclear Information System (INIS)

    Thurfjell, L.; Bohm, C.; Eriksson, L.; Karolinska Institute/Hospital, Stockholm

    1993-01-01

    The computerized brain atlas constructed at the Karolinska Hospital, Stockholm, Sweden, has been further developed. This atlas was designed to be employed in different fields of neuro imaging such as positron emission tomography (PET), single photon emission tomography (SPECT), computerized tomography (CT) and magnetic resonance imaging (MR). The main objectives with the atlas is to aid the interpretation of functional images by introducing anatomical information, to serve as a tool in the merging of data from different imaging modalities and to facilitate the comparisons of data from different individuals by allowing for anatomical standardization of individual data. The purpose of this paper is to describe the algorithms and transformations used in the implementation of the atlas software

  20. Computerized Tests. New practical and ethical challenges for Psychological Assessment

    Directory of Open Access Journals (Sweden)

    Gabriela Susana Lozzia

    2013-08-01

    Full Text Available The purpose of this study is to bring the readers in our field of knowledge closer to the new problems and solutions resulting from the application of computer systems to Psychological Assessment. Therefore, this work puts forward a suitable implementation of Computer-based and Internet-delivered Testing, includes a description of the new technologies that can be applied to Psychological Assessment: administration of traditional paper-and-pencil tests through computers, elaboration of automated reports, computerized adaptive tests, automated test construction and automatic generation of items, as well as the specific guidelines and regulations governing the development of each of these areas. This study provides an outline of the current issues connected with the appropriate use of Computerized Tests by way of conclusion and finally encourages psychologists to keep debating and reflecting on these topics.