scholarly journals Spesifikasi, Kode dan Standar Baja Nasional dan Potensinya untuk Mendukung Program PLTN Tipe LWR di Indonesia

2019 ◽  
Vol 20 (2) ◽  
pp. 111 ◽  
Author(s):  
Dharu Dewi ◽  
Sriyana Sriyana

SPESIFIKASI, KODE DAN STANDAR BAJA NASIONAL DAN POTENSINYA UNTUK MENDUKUNG PROGRAM PLTN TIPE LWR DI INDONESIA. Spesifikasi, kode dan standar baja nasional sangat penting diidentifkasi agar dapat dicocokkan atau dibandingkan  dengan spesifikasi, kode dan standar internasional untuk komponen PLTN sehingga industri baja diharapkan dapat berpartisipasi dalam pembangunan Pembangkit Listrik Tenaga Nuklir (PLTN). Spesifikasi kode dan standar  baja mengacu pada ASTM, ASME, AISC dan lain - lain. Tujuan studi ini adalah mengidentifikasi  spesifikasi, kode dan standar baja yang dimiliki industri nasional dan kemudian dicocokkan dengan spesifikasi, kode dan standar baja sesuai standar internasional untuk PLTN. Metodologi penelitian adalah kajian literatur, pengiriman kuesioner, survei dan kunjungan teknis ke industri baja. Disimpulkan bahwa baja struktur pada dasarnya memenuhi persyaratan untuk konstruksi PLTN.Kata kunci: spesifikasi, kode, standar, baja, industriSPECIFICATION, CODE AND STANDARD OF NATIONAL STEEL AND THE POTENCY TO SUPPORT THE NUCLEAR POWER PROGRAMME OF LWR TYPE IN INDONESIA. Specification, codes and standards are important to identify in order to be matched or compared to international specifications, codes and standards for NPP components so that the steel industry is expected to participate in the construction of Nuclear Power Plants (NPPs). The specifications, code and standards of steel refer to ASTM, ASME, AISC and others. The purpose of this study is to identify specifications, codes and steel standards owned by national industries and then compared it to international standards for nuclear power plants. The research methodology is literature review, questionnaire submission, surveys and technical visits to the steel industry. It was concluded that the structural steel basically meets the requirements for NPP construction.Keywords: specification, code, standard, steel, industry

2016 ◽  
Author(s):  
Michael Villaran ◽  
◽  
Meng Yue ◽  
Robert Lofaro ◽  
Athi Varuttamaseni ◽  
...  

Author(s):  
Sangmyeon Ahn ◽  
Jungjoon Lee ◽  
Chanwoo Jeong ◽  
Kyungwoo Choi

We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don’t have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA’s safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA’s Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA’s safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards.


Author(s):  
Aleksandr Orlov ◽  
◽  
Iurii Smirnov ◽  

The work is aimed at studying approaches and developing principal regulations when choosing the sites intended for constructing underground nuclear small power plants in geological formations. The research methodology provides for analysis and summarizing international and Russian experience in choosing the sites for the placement of radiation hazardous facilities. Results. The work gives the approaches when choosing the sites intended for radiation hazardous facilities proposed by IAEA in Russia and abroad. The formation of criteria complete, their specific weight and an integrated assessment of impacts of an energy object on the environment is of importance in the site choosing procedure. The several criteria characterising the site are different for the surface and underground placement of a nuclear plant. The underground placement of a nuclear plant is a determining factor in protecting against undesired external and internal impacts. The authors have proposed an algorithm of choosing the sites for underground small nuclear power plants based on a limited number of criteria. Conclusions. The approaches used for choosing the sites have similar algorithms. The site choosing procedure pays a lot of attention to formation of criteria and an integrated assessment of impacts of an energy object on the environment. The underground placement of energy objects improves their security that allows decreasing a number of observed criteria when choosing the sites.


2015 ◽  
Vol 59 (3) ◽  
pp. 91-98
Author(s):  
V. Šefl

Abstract In this literature review we identify and quantify the parameters influencing the low-cycle fatigue life of materials commonly used in nuclear power plants. The parameters are divided into several groups and individually described. The main groups are material properties, mode of cycling and environment parameters. The groups are further divided by the material type - some parameters influence only certain kind of material, e.g. sulfur content may decreases fatigue life of carbon steel, but is not relevant for austenitic stainless steel; austenitic stainless steel is more sensitive to concentration of dissolved oxygen in the environment compared to the carbon steel. The combination of parameters i.e. conjoint action of several detrimental parameters is discussed. It is also noted that for certain parameters to decrease fatigue life, it is necessary for other parameter to reach certain threshold value. Two different approaches have been suggested in literature to describe this complex problem - the Fen factor and development of new design fatigue curves. The threshold values and examples of commonly used relationships for calculation of fatigue lives are included. This work is valuable because it provides the reader with long-term literature review with focus on real effect of environmental parameters on fatigue life of nuclear power plant materials.


2016 ◽  
Vol 14 (3) ◽  
pp. 526-542 ◽  
Author(s):  
Ashok Kumar Upadhyay ◽  
Karuna Jain

Purpose Modularity in design and construction of nuclear power plants (NPPs) is widely used for reduction in project construction time and cost. This paper aims to improve understanding of existence, rationale, relevance, types and definitions of modularity in NPPs. Design/methodology/approach The paper approaches study of modularity in NPPs through review of existing literature. The objective of this paper is to answer the questions such as “what is the meaning of module in the context of NPPs?”, “what is the meaning of modularity in the context of NPPs?”, “why modularity is considered in the design and construction of NPPs?”, “what are the types of modules and modularity?” and “what are the emerging trends?” Findings Findings of the paper indicate towards widespread use of modularity to reduce construction time and cost, improve safety performance and enable smarter applications of NPPs. Large NPPs tend to use modularity to shorten the project gestation period, and thereby reduce capital cost. Small and medium size NPPs plan to use modularity for simpler and safer reactors that can be factory manufactured, transported, installed and scaled up as permitted by the economic environment. Research limitations/implications This being a review, it has the usual limitations associated with the literature review papers. Practical implications Findings of the paper may influence policy regarding option, type, size, design, engineering, procurement and construction of NPPs. Social implications Findings of the paper may influence the safety, cost, time and quality performance of future NPPs and facilitate cheaper and more reliable supply of electricity to consumers. Originality/value The systematic literature review presents issues and emerging trends in modularity of NPPs, enabling the future work to progress as modularity continues to develop and evolve. The paper also proposes a comprehensive classification and definitions of modules and modularity in NPPs that may facilitate understanding of these terms precisely and uniformly by researchers and practitioners alike.


Author(s):  
Hoonseok Byun ◽  
Seogchan Yoon ◽  
Jonghae Kim ◽  
Samchul Lee

Korea Electric Power Industry Code (KEPIC), a set of integrated standards applicable to the design, construction and operation of electric power facilities including nuclear power plants, has been developed on the basis of referring to the prevailing U.S. codes and standards which had been applied to the electric power facilities in Korea. Being the developing and managing organization of KEPIC, Korea Electric Association (KEA) published its first edition in 1995, the second in 2000 and the latest in 2005. KEPIC has been applied to the construction of nuclear power plants since 1997 in Korea. Along with the effectuation of the Agreement on Technical Barriers to Trade (TBT) in 1995, the international trend related to codes and standards is changing rapidly. KEA is, therefore, making its utmost efforts so as for KEPIC to keep abreast with the changing environment in international arena. KEA notified ISO/IEC Information Centre of its acceptance of the Code of Good Practice in the Agreement on TBT. Also the 2005 edition of KEPIC was published to be retrofitted according to the ISO/IEC Guide 21-Adoption of International Standards as regional or national standards. On the other hand, KEA is continuously performing to study on the improvement of KEPIC requirements. Such KEA’s efforts will help KEPIC correspond with international standards such as ISO/IEC standards, and internationally recognized standards such as ASME codes and standards. Furthermore KEA will expedite the publication of the bilingual edition of KEPIC at 2010 as per the globalization plan and KEA hopes that KEPIC can assist Korea Electric Power Corporation (KEPCO) and Korea Hydro & Nuclear Power Co., Ltd. (KHNP) in exportation of Korea Standard Nuclear Power Plant (KSNP) such as OPR-1000 and APR-1400 by the bilingual edition.


Sign in / Sign up

Export Citation Format

Share Document