Recovery and Resilience After a Nuclear Power Plant Disaster: A Medical Decision Model for Managing an Effective, Timely, and Balanced Response

2013 ◽  
Vol 7 (2) ◽  
pp. 136-145 ◽  
Author(s):  
C. Norman Coleman ◽  
Daniel J. Blumenthal ◽  
Charles A. Casto ◽  
Michael Alfant ◽  
Steven L. Simon ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Decision Model ◽  
Large Scale ◽  
Medical Decision ◽  
Incident Management ◽  
Additional Information ◽  
Medical Issues ◽  
High Level

AbstractResilience after a nuclear power plant or other radiation emergency requires response and recovery activities that are appropriately safe, timely, effective, and well organized. Timely informed decisions must be made, and the logic behind them communicated during the evolution of the incident before the final outcome is known. Based on our experiences in Tokyo responding to the Fukushima Daiichi nuclear power plant crisis, we propose a real-time, medical decision model by which to make key health-related decisions that are central drivers to the overall incident management. Using this approach, on-site decision makers empowered to make interim decisions can act without undue delay using readily available and high-level scientific, medical, communication, and policy expertise. Ongoing assessment, consultation, and adaption to the changing conditions and additional information are additional key features. Given the central role of health and medical issues in all disasters, we propose that this medical decision model, which is compatible with the existing US National Response Framework structure, be considered for effective management of complex, large-scale, and large-consequence incidents. (Disaster Med Public Health Preparedness. 2012;0:1-10)

A High Effective Parallel Method for the Coupling Between Neutronics and Thermal-Hydraulic

2016 ◽  
Author(s):  
Xiaomeng Dong ◽  
Zhijian Zhang ◽  
Zhaofei Tian ◽  
Lei Li ◽  
Guangliang Chen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Decisive Role ◽  
Reactor Power ◽  
Coupling Method ◽  
Outlet Temperature

Multi-physics coupling analysis is one of the most important fields among the analysis of nuclear power plant. The basis of multi-physics coupling is the coupling between neutronics and thermal-hydraulic because it plays a decisive role in the computation of reactor power, outlet temperature of the reactor core and pressure of vessel, which determines the economy and security of the nuclear power plant. This paper develops a coupling method which uses OPENFOAM and the REMARK code. OPENFOAM is a 3-dimension CFD open-source code for thermal-hydraulic, and the REMARK code (produced by GSE Systems) is a real-time simulation multi-group core model for neutronics while it solves diffusion equations. Additionally, a coupled computation using these two codes is new and has not been done. The method is tested and verified using data of the QINSHAN Phase II typical nuclear reactor which will have 16 × 121 elements. The coupled code has been modified to adapt unlimited CPUs after parallelization. With the further development and additional testing, this coupling method has the potential to extend to a more large-scale and accurate computation.

Design Concept of Composite Module for Nuclear Power Plant Construction

2004 ◽  
Author(s):  
Taihei Yotsuya ◽  
Kouichi Murayama ◽  
Jun Miura ◽  
Akira Nakajima ◽  
Junichi Kawahata
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Construction Method ◽  
Nuclear Plant ◽  
Small Scale ◽  
Modular Construction ◽  
Plant Construction ◽  
Composite Module

A composite module construction method is to be examined reflecting one of the elements of construction rationalization of a future nuclear plant planned by Hitachi. This concept is based on accomplishments and many successes achieved by Hitachi through application of the modular construction method to nuclear power plant construction over 20 years. The feature of the composite module typically includes a planned civil structure, such as a wall, a floor, and a post, representing modular components. In this way, an increased level of rationalization is expected in the conventional large-scale nuclear plants. Furthermore, the concept aiming at the modularization of all the building parts comprising medium- or small-scale reactors is also to be examined. Additional aims include improved reductions in the construction duration and rationalization through use of the composite module. On the other hand, present circumstances in nuclear plant construction are very pressing because of economic pressures. With this in mind, Hitachi is pursuing additional research into the introduction of drastic construction rationalization, such as the composite module. This concept is one of the keys to successful future plant construction, faced with such a severe situation.

Steam Line Integrity Analyses for LTO: Enhancing Credibility With Comprehensive Measurement

2012 ◽  
Author(s):  
Horst Rothenhöfer ◽  
Andreas Manke
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Simulation Models ◽  
Proper Function ◽  
Blow Down ◽  
Term Operation ◽  
High Level ◽  
Comprehensive Measurement

The safety relevant components of nuclear power plant Neckarwestheim 1 — in service since 1976 — have been reviewed and updated for long-term operation (LTO). The actions included hardware retrofits as well as updates of analysis according to the latest state of the scientific and technical knowledge. For large piping such as the steam lines, the established pipes have been retained while the supports have been optimized. All shock absorbers (snubbers) including corresponding inertia have been eliminated resulting in a defined guidance and statically defined displacements. The integrity analyses for the optimized steam lines, including break preclusion, have been validated successfully with comprehensive measurements. The verification has delivered an extra high level of credibility, exceeding the “standard” requirements to achieve fitness for service in long-term operation. Measurement and validation, which are the main focus of this paper, range from monitoring of service loads to the static and dynamic measurements of pressure, local temperatures and displacements during initial start-up after implementation of the design modifications. The proper function of supports has been proved and the quality of the simulation models has been confirmed. Some expected and some unexpected dynamic events have been detected during blow-down tests. It was demonstrated that the amplitudes of all dynamic loads stay within limits. The validation of analyses with comprehensive measurement has been an important proof of quality and delivered the redundancy required for the integrity of a nuclear power plant in service, enhancing the high level of safety even more.

Incorporation of Risk Insights in the Regulatory Treatment of Nuclear Power Plant Structures, Systems, and Components

2002 ◽  
Author(s):  
Eugene Imbro ◽  
Thomas G. Scarbrough
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Regulatory Commission ◽  
The United States ◽  
Special Treatment ◽  
Regulatory Commission ◽  
High Level

The U.S. Nuclear Regulatory Commission (NRC) has established an initiative to risk-inform the requirements in Title 10 of the Code of Federal Regulations (10 CFR) for the regulatory treatment of structures, systems, and components (SSCs) used in commercial nuclear power plants. As discussed in several Commission papers (e.g., SECY-99-256 and SECY-00-0194), Option 2 of this initiative involves categorizing plant SSCs based on their safety significance, and specifying treatment that would provide an appropriate level of confidence in the capability of those SSCs to perform their design functions in accordance with their risk categorization. The NRC has initiated a rulemaking effort to allow licensees of nuclear power plants in the United States to implement the Option 2 approach in lieu of the “special treatment requirements” of the NRC regulations. In a proof-of-concept effort, the NRC recently granted exemptions from the special treatment requirements for safety-related SSCs categorized as having low risk significance by the licensee of the South Texas Project (STP) Units 1 and 2 nuclear power plant, based on a review of the licensee’s high-level objectives of the planned treatment for safety-related and high-risk nonsafety-related SSCs. This paper discusses the NRC staff’s views regarding the treatment of SSCs at STP described by the licensee in its updated Final Safety Analysis Report (FSAR) in support of the exemption request, and provides the status of rulemaking that would incorporate risk insights into the treatment of SSCs at nuclear power plants.

Grid-Connected Nuclear Power Plant Key Issues Summary

2014 ◽  
Vol 521 ◽  
pp. 530-535
Author(s):  
Meng Wang ◽  
Jian Ding ◽  
Tian Tang ◽  
Zhang Sui Lin ◽  
Zhen Da Hu ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Large Scale ◽  
Power Modeling ◽  
Modeling Simulation ◽  
Load Following ◽  
Key Issues ◽  
The Impact

The current situation of nuclear power plants at home and abroad is described, and the impact of large-scale nuclear power accessing to the grid is analyzed, specifically in the aspects of nuclear power modeling, simulation, load following, reliability, fault diagnosis, etc. Nuclear power accessing to the grid will bring a series of problems, the causes of each problem, the main solutions and future development directions are summarized.

scholarly journals A Dialogic Perspective on Managing Knowledge Differences: Problem-Solving while Building a Nuclear Power Plant Safety System

2021 ◽  
pp. 017084062110618
Author(s):  
Chia-Yu Kou ◽  
Sarah Harvey
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Knowledge Integration ◽  
Safety System ◽  
Problem Situation ◽  
Plant Safety ◽  
Nuclear Power Plant Safety ◽  
Large Scale Project

To manage knowledge differences, existing research has documented two sets of practices: traversing and transcending knowledge boundaries. What research has yet to explore, however, is the dynamics through which traversing or transcending practices emerge in response to a particular problem situation. Using a qualitative, inductive study of the problem episodes encountered by groups of experts working on a large-scale project to build the safety system for a nuclear power plant, we observed that the emergence of traversing or transcending depended on how experts interpreted problems and initiated dialogues around specific problems. Our work provides insight into the condition through which knowledge integration trajectories may emerge.

scholarly journals PERHITUNGAN BIAYA OPERASI DAN PERAWATAN PLTN SKALA BESAR DAN KECIL

2015 ◽  
Vol 17 (2) ◽  
pp. 87
Author(s):  
Mochamad Nasrullah ◽  
Wiku Lulus Widodo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Secondary Data ◽  
Capacity Factor ◽  
Maintenance Cost ◽  
Small Scale ◽  
Operation And Maintenance ◽  
Operation And Maintenance Cost

ABSTRAK PERHITUNGAN BIAYA OPERASI DAN PERAWATAN PLTN SKALA BESAR DAN KECIL. Biaya pembangkit PLTN terdiri dari tiga komponen, yaitu biaya investasi, bahan bakar dan operasi perawatan (O & M). Besarnya biaya O&M pada PLTN besar dan kecil tidaklah sama. Studi ini bertujuan untuk menghitung biaya O&M PLTN skala besar dan kecil dengan mempertimbangkan parameter teknis dan ekonomis yang diambil dari berbagai data sekunder dan sumber lainnya. Studi dilakukan menggunakan data dari PLTN jenis PWR dengan daya 1343 MWe untuk PLTN ukuran besar dan daya 90 MWe untuk PLTN ukuran kecil. Asumsi digunakan tingkat eskalasi sebesar 5%, faktor kapasitas 90%. Metodologi yang digunakan adalah menghitung dengan spreadsheet yang meliputi skala masing-masing komponen O&M. Hasil perhitungan menunjukkan biaya O & M jika dihitung dengan satuan juta US$/tahun, maka biaya O&M PLTN 1343 MWe sebesar 99,21 juta US$/tahun lebih mahal dari PLTN 90 MWe sebesar 45,13 juta US $/tahun. Namun jika biaya O & M PLTN 1343 MWe dihitung dengan satuan mills $/kWh, maka hasilnya  sebesar 9,37 lebih murah dibandingkan dengan PLTN 90 MWe yaitu sebesar 63,70 mills $/kWh. Hal ini berarti semakin kecil ukuran kapasitas dayanya maka biaya operasi dan perawatannya semakin mahal. Penyebab perbedaan biaya operasi dan perawatan antara PLTN skala besar dan kecil, adalah kapasitas daya, faktor kapasitas, jumlah personal yang bekerja pada biaya administrasi umum pegawai dan manajemen, operasi pembangkit tahunan, biaya tenaga kerja offsite. Kata kunci : Biaya operasi dan perawatan, PLTN, LEGECOST ABSTRACT CALCULATION OF OPERATION AND MAINTENANCE COST FOR LARGE AND SMALL SCALE NPP. The generation cost of nuclear power plant consists of three components:  investment costs, fuel cost operation and maintenance (O&M) cost. O&M costs in the large scale of NPP is different from small scale NPP. The objective of this study are to calculate the O&M cost of large NPP and small NPP by considering technical and economic parameters from secondary data and  other references. This study uses 1343 MWe PWR data for large NPP and 90 MWe PWR for small NPP. The assumptions are 5% escalation level and 90% capacity factor. The methodology for calculation using spreadsheet with scaling methods for each O&M components. The results shows that the O &M cost if calculated in units of million US$/year, the O&M cost of NPP 1343 MWe is US$million 99.21/ year which is more expensive than the O&M cost of NPP 90 Mwe which is only US$million 45.13/ year.  But if the cost of O&M 1343 MWe nuclear power plant unit is calculated in units of mills $/kWh, the result shows that the O&M cost is 9.37 mills $/kWh which is less than the 90 MWe NPP which reaches $ 63.70 mills/kWh. The conclusion is  lower NPP capacity  has higher O&M cost. Different O&M cost is caused by power capacity, capacity factor, the amount of worker on site staff, the annual net generation and the offsite technical support. Keywords: Operation and maintenance cost, NPP, LEGECOST 

Advanced Construction Technologies for the Ohma Nuclear Power Plant Reactor Building of Electric Power Development Co., Ltd.

2010 ◽  
Author(s):  
Tatsuya Obata ◽  
Akihito Urashima ◽  
Kiyokatsu Watanabe ◽  
Tsumoru Miyahara
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Electric Power ◽  
Nuclear Power ◽  
Large Scale ◽  
Construction Method ◽  
Strong Wind ◽  
Power Development ◽  
Reactor Building ◽  
Aomori Prefecture

Electric Power Development Co., Ltd has been constructing Ohma Nuclear Power Plant aiming to start commercial operation in Nov. 2014. Ohma Nuclear Power Plant is located in Ohma-town, Aomori Prefecture and is a landmark power plant in which Mixed Oxide fuels can be loaded in the full core of the reactor. Hitachi-GE Nuclear Energy Ltd. and Kajima JV, both have extensive experience of nuclear power plant construction, are the main contractors of this project and supply the entire engineering, manufacturing of all major components, and execute the construction and commissioning for the reactor building. Ohma-town is located at the northernmost part of Aomori Prefecture bordering Tsugaru strait, where is exposed to severe cold and constant strong wind in winter. Such severe weather conditions make the construction very hard, however, Hitachi and KAJIMA tries to complete the project on schedule and on budget applying highly reliable advanced construction technologies, such as open-top and parallel construction method, all whether construction method, and large scale modularization technology. The groundbreaking (acquisition of the first construction permission) was already completed in May 2008. Its civil work steadily progressed, and the rock inspection was completed in Oct. 2009. Base mat will be completed in July 2010, and both building work and mechanical work go into full swing after installation of RCCV lower liner module.

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