• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.9 no.1
• /
• pp.56-61
• /
• 2013

This paper presents the results of integrity assessment for the cracks happened in reactor vessel upper head penetration nozzles. The crack morphology for a boat sample from crack area was analyzed through microscope. The stress condition including weld residual stress around crack was analyzed using finite element analysis. From the results of crack morphology and stress condition, the crack was concluded as primary water stress corrosion cracking. The integrity of the cracked nozzle was assessed by the methodology provided in ASME Section XI. According to the assessment results, the remaining life of the cracked nozzle was 1.43 yrs. and the plant decided to repair it.

• Journal of Korean Critical Care Nursing
• /
• v.12 no.1
• /
• pp.46-56
• /
• 2019

Purpose : The purpose of this study was to identify minimum data sets for oral mucous integrity-related documentation and to analyze nursing records for oral care. Methods: To identify minimum data sets for oral status, the authors reviewed 26 assessment tools and a practical guideline for oral care. The content validity of the minimum data sets was assessed by three nurse specialists. To map the minimum data sets to nursing records, the authors examined 107 nursing records derived from 44 patients who received chemotherapy or hematopoietic stem cell transplantation in one tertiary hospital. Results: The minimum data sets were 10 elements such as location, mucositis grade, pain, hygiene, dysphagia, exudate, inflammation, difficulty speaking, and moisture. Inflammation contained two value sets: type and color. Mucositis grade, pain, dysphagia and inflammation were recorded well, accounting for a complete mapping rate of 100%. Hygiene (100%) was incompletely mapped, and there were no records for exudate (83.2%), difficulty speaking (99.1%), or moisture (88.8%). Conclusion: This study found that nursing records on oral mucous integrity were not sufficient and could be improved by adopting minimum data sets as identified in this study.

• Nuclear Engineering and Technology
• /
• v.35 no.6
• /
• pp.556-565
• /
• 2003

A quality assurance safety assessment database, called QUARK (QUality Assurance Program for Radioactive Waste Management in Korea), has been developed to manage both analysis information and parameter database for safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility in Korea. QUARK is such a tool that serves QA purposes for managing safety assessment information properly and securely. In QUARK, the information is organized and linked to maximize the integrity of information and traceability. QUARK provides guidance to conduct safety assessment analysis, from scenario generation to result analysis, and provides a window to inspect and trace previous safety assessment analysis and parameter values. QUARK also provides default database for safety assessment staff who construct input data files using SAGE(Safety Assessment Groundwater Evaluation), a safety assessment computer code.

• 유체기계공업학회:학술대회논문집
• /
• 2002.12a
• /
• pp.459-464
• /
• 2002

In this paper, the recent trends of conformity assessment activity which is carrying out at ISO is summarized. It is an increasing requirement of quality assurance systems that a company's engineers and technicians are able to demonstrate that they have the required level of knowledge and skill. This is particularly so since maintenance and Inspection activities are very operator dependent and those in authority have to place great reliance on the skill, experience, Judgement and integrity of the personnel involved.

• Proceedings of the KSME Conference
• /
• 2007.05b
• /
• pp.3497-3500
• /
• 2007

The internal structure is subjected to dynamic analysis due to the structural integrity. The internal structure shall be installed in the vertical hole call IR1 of reactor core. In order to verify the deflection of the internal structure, the mode and response spectrum analysis of the internal structure was performed. The natural frequency of the internal structure is 11.6 Hz(mode 1 and 2) and deflections of the internal structure are less than values of allowable design (3.2 mm).

• Transactions of the Korean Society for Noise and Vibration Engineering
• /
• v.21 no.12
• /
• pp.1098-1103
• /
• 2011

The structural integrity of APR1400 reactor vessel internals has been being assessed referring the US Nuclear Regulatory Commission regulatory guide 1.20, comprehensive vibration assessment program. The program is composed of a vibration and stress analysis, a vibration and stress measurement, and an inspection. This paper covers the vibration and stress analysis on the reactor vessel internals by the pulsation of reactor coolant pump. 3-dimensional models to calculate the hydraulic loads and structural responses were built and the pressure distributions and the structural responses were predicted using ANSYS. This paper presents that APR1400 reactor vessel internals have enough structural integrity against the pulsation of reactor coolant pump as the peak stress of the reactor vessel internals is much lower than the acceptance limit.

• IE interfaces
• /
• v.25 no.4
• /
• pp.376-381
• /
• 2012

As the number, complexity and interaction of electrical, electronic and programmable electronic (E/E/PE) systems increase, a growing emphasis has been placed on the concept of functional safety during product development. IEC 61508 provides guidelines and standardized procedures in the development of reliable and dependable E/E/PE systems to assure functional safety. Determining risk classes (i.e., safety integrity levels, SILs) associated to a specific E/E/PE item may be recognized as one of the most crucial activities in the product development per IEC 61508 since SILs are used to specify necessary safety requirements for achieving an acceptable residual risk. This article presents a case study on the assessment of SILs applying failure modes, effects and diagnostic analysis (FMEDA) from which failure rates may be derived for each important failure category by combining a standard FMEA with online diagnostic techniques.

• Proceedings of the Korean Institute of Industrial Safety Conference
• /
• 2000.06a
• /
• pp.25-30
• /
• 2000

The object of this work is to develop an assessment system for pipeline integrity The system consists of four module applications for internal algorithm; the effect of corrosion in pipeline, crack, stress corrosion crack (SCC) and fatigue modules. Presently, the module of the external corrosion has been developed and the internal algorithm for the effect of corrosion in pipeline and the database of the system are described in this paper, The database of the system is separated to mainly four parts; geometry of pipeline, material properties, boundary conditions and general Properties. Each components of the system are designed by user-friendly concept. This system may give a guideline for maintenance and modifications for the pipeline at the industrial sight. Furthermore, a procedure to evaluate an inspection interval is also provided.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
• /
• 2012.04a
• /
• pp.907-910
• /
• 2012

Since the inner barrel assembly of the Advanced Power Reactor 1400 reactor vessel is a new design feature introduced instead of CEA(control element assembly) shroud assembly, the inner barrel assembly can be a significant object of structural integrity assessment. This paper covers the structural responses of top plate, which is a component of the inner barrel assembly, against the deterministic hydraulic load induced by pump pulsation and the random hydraulic load induced by turbulence of coolant. The top plate responds to the deterministic hydraulic load more than to the random hydraulic load and shows enough structural integrity. The results of this paper will be important basis for the selection of instruments and measurement location.

• International Journal of Precision Engineering and Manufacturing
• /
• v.1 no.2
• /
• pp.48-54
• /
• 2000

This paper presents the effect of shape of external corrosion in pipeline on failure prediction by using a numerical simulation. The numerical study for the pipeline failure analysis is based on the FEM(Finite Element Method)with an elastic-plstic and large-deformation analysis. Corrosion pits and narrow corrosion grooves in pressurized pipeline were analysed. A failure criterion, based on the local stress state at the corrosion and a plastic collapse failure mechanism, is proposed. The predicted failure stress assessed for the simulated corrosion defects having different corroded shapes along the pipeline axis compared with those by methods specified in ANSI/ASME B31G code and a modified B31G code. It is concluded the corrosion geometry significantly affects the failure behavior of corroded pipeline and categorisation of pipeline corrosion should be considered in the development of new guidance for integrity assessment.