bluuebunny/crossref_metadata_2025_split huggingface dataset:
Konsep Akad Al-Ju’alah Di Dalam Perusahaan Multi-Level Marketing (MLM) Patuh Syariah
Authors: Tunggak Buerah , Tamjis Mohd Fairuz 
Published: October 2016

Sales of products through the concept of Multi-Level Marketing (MLM) is a new form of business that is growing rapidly in Malaysia now. The business of the Malaysian population drastic response, including the Muslims. Nevertheless there are some aspects that often cause confusion and doubt in the business, especially in terms of adherence to Sharia. Among the aspects that need to be emphasized to ensure MLM companies operate on a Shariah platform is to examine the type of contract used. Each contract is recognized in Islamic Muamalat contains the pillars and the conditions that must be complied with. Violation of rules and conditions that have been set will cause the business carried invalid or void thereby making the non-compliant businesses. Between the concepts of contracts in the MLM business that need attention is the relationship between MLM companies and distributors (members), distributors (members) and the buyer, pegedar old (upline) and distributors (downline), salaries, bonuses and setting membership fees. In general, the application includes several types of MLM business like a business contract of al-Bai‘ (sale), al-Wakalah (business representative), al-Ijarah (leasing) and al-Ju‘alah (promise of wages). Writing is only focusing on the concept of al-Ju‘alah contract that is embedded in the MLM business. This article will detail the pillars and conditions that must be adhered to by all parties involved in the contract of al-Ju‘alah. This article will also try to identify common violations committed by MLM companies on the pillars and conditions of the contract. Finally, this paper suggests the parties involved in an MLM company in the country to implement the concept of MLM business through the application of Shariah tenets and conditions of the contract which will be explained later. All parties need to be involved to ensure that business is conducted so that the provision of Shariah-compliant obtained lawful and blessed. Keywords: Multi-Level Marketing (MLM), Transactions, Akad al-Ju‘alah, Shariah-compliant.
ANALISIS LITERATUR ISU PELANTIKAN HAKIM SYARIE WANITA DI MALAYSIA
Authors: Nasohah Zaini , Majemi Fatimah , Mohd Kusrin Zuliza , Muhammad Husni Ahmad , Samuri Mohd Al-Adib 
Published: October 2016

Qadi or judge is a significant post in a state. Islam has enumerated certain detailed and strict conditions for a person to be appointed as a judge. Among the conditions is appointing a male judge for the post. Discussion on this issue in Malaysia is still ongoing as there are states that have not giving opportunity for women to have the post. This article aims to analyze literature review on the issue in Malaysia. A comparative content analysis approach was applied in analyzing the data gathered. The analysis discovers that there are lot of writings in fiqh references that disagree with the appointment of female judges. However, contemporary writings show that a lot of writing that supported and agreed with the appointment of female judges in certain area of judgements.Keywords: Shariah Judges, Women, Justification, Appointment, Acceptance
Examining Learning and Peer Efficacy Among Secondary School Students In District of Ledang
Authors: Md. Sawari Siti Salwa , Ghazali Mohd Al'Ikhsan , Trayek Fuad A. A. , Awang Mat Muhamad Zahiri 
Published: October 2016

Efficacy functions to enhance the desire of learning through mediations of motivations and confidence. The present study is designed to achieve two main objectives. First, to identify the level of learning efficacy of public and religious secondary school students. Second, to examine the significant difference level of learning efficacy between public and religious school students. This study involved 242 students sampled from four schools in district Ledang. The sampled participated in the survey, employing a twelfth item questionnaire measuring Learning Self-efficacy (LSE) and Peer Self-efficacy (PSE). The data are analysed quantitatively using descriptive statistics and independent-samples t-tests. The result showed that the majority of students experience a moderate level of learning efficacy. Generally, for the selected public school students the mean is 2.75 and religious school students the mean is 2.97. Regarding the comparison level of learning efficacy between the two types of students, the findings of the current study show that there is no significant differences (p=.47), while peers self-efficacy revealed that there are significant differences (p=0.001).
Passive System Reliability Modeling of the Combination of Failure Modes
Authors: Burgazzi Luciano 
Published: October 2016

Innovative probabilistic models to extend the reliability analysis of passive systems under different modes of failure are proposed.
The prevailing failure mode on the system can be predicted through the failure probability assessment on each specific mode. A realistic case is presented to analyze a passive system with two kinds of major failure modes — natural circulation stoppage due to e.g., isolation valve closure (a catastrophic failure) and heat transfer process degradation due to e.g., deposit thickness on component surfaces (a degradation failure). Modeling of each individual failure mode together with system reliability analysis is presented and results are discussed.
Comparison of Fukushima Response in the United States and Europe
Authors: Lutz Robert J. , Prior Robert P. 
Published: October 2016

The accident at the three reactor units at Fukushima Daiichi showed weaknesses in the plant coping capability for beyond design basis accidents caused by extreme external events. The weaknesses included plant design features, accident management procedures and guidance, and offsite emergency response. As a result, significant changes to plant coping capability have been made to light water reactors worldwide to enhance the coping capabilities for beyond design basis accidents. However, the response in the United States has been significantly different from that in Europe in a number of ways. In the United States, the regulator and the industry convened separate expert panels to review the Fukushima accident and make recommendations for enhancements. On the regulatory side, a series of three Orders were issued and that required the implementation of certain enhancements (Mitigation strategies, hardened vents for certain BWRs, spent fuel pool level indication) to ensure adequate protection for the health and safety of the public. Other enhancements were subject to the “Backfit Rule” which requires that changes to regulatory requirements be shown to be cost beneficial using accepted methodologies. Simultaneously, the industry took independent steps to develop a diverse and flexible coping strategies (known as FLEX) and other enhancements. The focus in the United States was clearly on enhancements to guarantee continued core, containment and spent fuel pool cooling in the event of beyond design basis accidents, particularly those resulting from extreme external events.
In Europe, the regulatory agencies ordered the development and completion of “Stress Tests” for each reactor site. These Stress Tests were focused on identifying the capability of the plant and its staff to respond to increasingly severe external events. The Stress Tests not only examined the ability to maintain core, containment and spent fuel pool cooling but also the ability to mitigate the consequences of accidents that progress to core damage (i.e., a severe accident). Regulatory requirements were then issued by the national regulators that addressed the weaknesses identified from the Stress Tests. While many of the enhancements to the plant coping capability were similar to those in the United States, significant hardware enhancements were also required to reduce the consequences of core damage accidents including hydrogen control and containment filtered venting.
Finally, most European regulators also include severe accident management guidance (SAMG) as a regulatory requirement. In the United States, SAMG will be maintained as a voluntary industry commitment that is subject to regulatory oversight review.
Instrument Health Monitoring for Extending Calibration Intervals of Safety Related Instruments
Authors: Black R. Steven , Hussey Aaron J. , Bickford Randall L. 
Published: October 2016

The ability to extend calibration intervals for nuclear plant instrumentation has multiple benefits for improving productivity and reducing operating costs at nuclear plants. Benefits include fewer calibrations inside containment during an outage and associated reduced critical path time and ALARA exposure, reduced risk of calibration error or instrument damage during removal and replacement, and reduced operations and maintenance cost for instrument removal, calibration and replacement.
A good instrument calibration program ensures instruments are checked frequently enough to provide a high level of confidence that they are performing within acceptable limits, but no more frequently. Over-testing of plant instruments and equipment should be avoided for two reasons: valuable resources are expended on maintenance that might not measurably improve plant safety, reliability, or efficiency; and the potential exists for adjustment errors or equipment damage each time an instrument is removed from service for testing. Over-testing increases the risk of errors or damage being introduced without a justifiable improvement in reliability.
This paper discusses the regulatory framework for extending calibration intervals of safety related instruments for U.S. based nuclear power plants. Necessary changes to licensing, plant processes and procedures, training, and configuration management are summarized. An example application of pattern recognition modeling is provided to highlight the analytical support for the processes provided by active monitoring to confirm on-going instrument heath. The paper concludes with a listing of recommended steps to implement a practical program for extending calibration intervals of safety related instruments within the U.S. nuclear regulatory environment.
Results of the Loss of Offsite Power Events Analysis
Authors: Volkanovski Andrija , Ballesteros Avila Antonio , Peinador Veira Miguel 
Published: October 2016

This paper presents the results of statistical and engineering analysis of Loss of Offsite Power (LOOP) events registered in four reviewed databases. The paper includes events registered in IRSN (Institut de Radioprotection et de Sûreté Nucléaire) SAPIDE and GRS (Gesellschaft für Anlagen- und Reaktorsicherheit mbH) VERA database in time period 1992 to 2011. The Nuclear Regulatory Commission (NRC) Licensee Event Reports (LERs) database and the IAEA International Reporting System (IRS) database are screened for the relevant events registered in period 1990 to 2013.
In total, 228 relevant events were identified in the IRSN database, 190 in GRS, 120 in LER and 52 in IRS. The data include events registered both during the critical (at power) and shutdown operation of the plants. The identified events were classified considering nine different categories.
In the three databases (SAPIDE, VERA, IAEA-IRS) the largest numbers of events are registered for the plant centered category. The largest number of the events in the NRC-LER database is found for switchyard centered events. According to the mode of operation, most events were reported during critical power operation, in all four databases. The “Partial loss of external power” events are the most frequent type of event found in the IRSN and NRC databases while the “Physical loss of electrical busbars” is the main type in the GRS and IAEA databases. The largest number of events in all databases is identified for the switchyard failures followed by the interconnections failures (both lines and transformers). Mainly LOOP event are identified by the fault report in the control room. Electrical deficiency is detected as the main direct cause of events. Environment is registered as the main contributor for the electrical grid deficiency in the French and NRC databases. Electrical failures are dominant contributor to the electrical grid deficiency in the German and IAEA databases. The principal root cause for the LOOP events are human failures with the human errors during test, inspection and maintenance as the largest sub-group. The largest number of the LOOP events resulted in reactor trip followed by the Emergency Diesel Generator (EDG) start. The majority of the reported LOOP events lasted for more than 2 minutes.
Main lessons learned from the analysed events and potential actions for decrease of the number of LOOP events are presented.
Reliability of PCCS in AP1000 Based on Accident Development
Authors: Yu Yu , Wang Shengfei , Niu Fenglei 
Published: October 2016

Passive containment cooling system (PCCS) is an important safety-related system in AP1000 nuclear power plant, by which heat produced in reactor is transferred to the heat sink – atmosphere – based on natural circulation, independent of human response or the operation of outside equipments, so the reactor capacity of resisting external hazards (earthquake, flood, etc.) is improved. However since the system operation based on natural circulation, many uncertainty factors such as temperatures of cold and heat sources will affect the system reliability, and physical process failure becomes one of the important contributors to system failure, which is not considered in the active system reliability analysis. That is, the system will lose its function since the natural circulation cannot be established or kept even when the equipments in the system can work well.
The function of PCCS in AP1000 is to transfer the heat produced in the containment to the environment and to keep the pressure in the containment below its threshold. After accidents the steam is injected to the containment and can be cooled and condensed when it arrives at the containment wall, then the heat is transferred to the atmosphere through the steel vessel. So the peak value of the pressure is influenced by the steam situation which is injected into the containment and the heat transfer and condensate processes under the accidents. In this paper the dynamic thermal-hydraulic (T-H) model simulating the fluid performance in the containment is established, based on which the system reliability model is built. Here the total pressure in the containment is used as the success criteria. Apparently the system physical process failure may be related to the system working state, the outside conditions, the system structure parameters and so on, and it’s a heavy work to analyze the influences of all the factors, so only the effects of important ones are included in the model. Monte Carlo (MC) simulation is used to evaluate the system reliability, in which the input parameters such as air temperature are sampled based on their probabilistic density distributions. The pressure curves along with the accident development are gained and the system reliabilities under different accidents are gotten as well as the main contributors. The results illustrate that the system physical process failure probabilities are varied under different climate conditions, which result in the system reliability and the main contributors to system failure changing, so the different methods can be taken to improve the system reliability according to the local condition of the nuclear power plant.
Corrosion of Hot-Dip Galvanized Containment Installations: A Potential Cause for Thermal-Hydraulic Effects After LOCA in PWR?
Authors: Kryk Holger , Harm Ulrich , Hampel Uwe 
Published: October 2016

Generic investigations regarding the influence of corrosion processes of hot-dip galvanized PWR containment installations on strainer clogging as well as on the coolant chemistry and possible resulting in-core effects are carried out within joint research projects of the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), TU Dresden (TUD) and Zittau-Görlitz University of Applied Sciences (HSZG). Lab-scale experiments at HZDR and TUD are focused on elucidation of physico-chemical corrosion and precipitation processes as well as resulting clogging effects.
Results of generic experiments in a lab-scale corrosion test facility suggest that there is a multi-stage corrosion process. The first stage comprises dissolution of the zinc layer in the coolant forming zinc ions and in turn affecting the coolant chemistry. During the second stage, the base material (steel) corrodes forming insoluble corrosion particles, which can subsequently lead to accelerated clogging of fiber-laden strainers within a few hours. The main influences on corrosion were identified as impact of the coolant jet onto the corroding surface, water chemistry and zinc surface / coolant volume ratio.
Furthermore, retrograde solubility of zinc corrosion products in boric acid containing coolants with increasing temperature was observed. Thus, formation and deposition of solid corrosion products cannot be ruled out if zinc containing coolant is heated up during its recirculation into hot downstream components (e.g. hot-spots in core). Corrosion experiments, which included formation of corrosion products at a heated cladding tube, proved that zinc, dissolved in the coolant at low sump temperatures, turns into solid deposits of zinc borates when contacting heated zircaloy surfaces. Due to alternating heating and cooling of the coolant during sump recirculation operation, a cycle of zinc corrosion and zinc borate precipitation may be initiated, which may eventually influence the thermal hydraulics in downstream components during the post-LOCA stage. The results obtained at lab-scale were confirmed by corresponding experiments in semi-technical test facilities of the project partner HSZG.
Based on the experimental results, water chemical measures were tested to reduce corrosion and/or zinc borate precipitation effects.
Benchmark Accelerated Aging of Harvested Hypalon/EPR and CSPE/XLPE Power and I&C Cable in Nuclear Power Plants
Authors: Duckworth Robert C. , Frame Emily , Fifield Leonard S. , Glass Samuel W. 
Published: October 2016

As part of the Light Water Reactor and Sustainability (LWRS) program in the U.S. Department of Energy (DOE) Office of Nuclear Energy, material aging and degradation research is currently geared to support the long-term operation of existing nuclear power plants (NPPs) as they move beyond their initial 40 year licenses. The goal of this research is to provide information so that NPPs can develop aging management programs (AMPs) to address replacement and monitoring needs as they look to operate for 20 years, and in some cases 40 years, beyond their initial, licensed operating lifetimes. For cable insulation and jacket materials that support instrument, control, and safety systems, accelerated aging data are needed to determine priorities in cable aging management programs.
Before accelerated thermal and radiation aging of harvested, representative cable insulation and jacket materials, the benchmark performance of a new test capability at Oak Ridge National Laboratory (ORNL) was evaluated for temperatures between 70 and 135°C, dose rates between 100 and 500 Gy/h, and accumulated doses up to 200 kGy. Samples that were characterized and are representative of current materials in use were harvested from the Callaway NPP near Fulton, Missouri, and the San Onofre NPP north of San Diego, California. From the Callaway NPP, a multiconductor control rod cable manufactured by Boston Insulated Wire (BIW), with a Hypalon/ chlorosulfonated polyethylene (CSPE) jacket and ethylene-propylene rubber (EPR) insulation, was harvested from the auxiliary space during a planned outage in 2013. This cable was placed into service when the plant was started in 1984. From the San Onofre NPP, a Rockbestos Firewall III (FRIII) cable with a Hypalon/ CSPE jacket with cross-linked polyethylene (XLPE) insulation was harvested from an on-site, climate-controlled storage area. This conductor, which was never placed into service, was procured around 2007 in anticipation of future operation that did not occur.
Benchmark aging for both jacket and insulation material was carried out in air at a temperature of 125°C or in a uniform 140 Gy/h gamma field over a period of 60 days. Their mechanical properties over the course of their exposures were compared with reference data from comparable cable jacket/insulation compositions and aging conditions. For both accelerated thermal and radiation aging, it was observed that the mechanical properties for the Callaway BIW control rod cable were consistent with those previously measured. However, for the San Onofre Rockbestos FRIII, there was an observable functional difference for accelerated thermal aging at 125°C. Details on possible sources for this difference and plans for resolving each source are given in this paper.
FMEDA-Based NPP I&C Systems Safety Assessment: Toward to Minimization of Experts’ Decisions Uncertainty
Authors: Yasko Alexander , Babeshko Eugene , Kharchenko Vyacheslav 
Published: October 2016

There are many techniques for the Nuclear Power Plants Instrumentation and Control (NPP I&C) systems safety assessment. Each of them is suitable for specific types of I&C systems and life cycle stages. Though general procedures of techniques application are specified by standards and described by guides, there is no universal solution that could be unambiguously applied to any NPP I&C system.
The Failure Modes, Effects and Diagnostics/Criticality Analysis (FME(D/C)A) is the one that is most often used. Using this technique, the process of assessment is not trivial because of dimensionality problem that is especially critical for modern NPP I&C systems that contain many complex electronic components. Another challenge is the need of compliance to varying requirements of standards. Furthermore, modern I&C systems are based on different platforms (FPGA, microcontrollers).
Most of safety and reliability assessment techniques, including mentioned FME(D/C)A, are based on expertise and thereby results are dependent on experts’ decisions very much. This could be a serious challenge, because it is very difficult to find universal experts that have sufficient experience to be equally qualified in different electronic components (FPGA, microcontrollers etc.) used in modern I&C systems.
The goal of this paper is to analyze the ways of automation of FMEDA-based NPP I&C systems safety assessment and minimization of uncertainty degree of experts’ decisions.
Possible experts’ errors and the uncertainty degree of their decisions are analyzed. We propose integration of all existing FMEA-based techniques into XME(D/C)A that includes Functional FMEA, Design FMEA, Software FMEA, Hardware FMEA etc. Such approach allows performing more comprehensive analysis. Developed tool AXMEA (Automated XMEA) represents an integrated solution that provides the automation of stages of FMEDA technique applied to NPP I&C.
The case study is the application of proposed technique and tool during SIL3 certification of the modular RadICS™ platform.