ISSUES WITH APPROACHES FOR SIMULATING AGING OF NUCLEAR POWER PLANT CABLE MATERIALS

2021 ◽  
Author(s):  
Kenneth T. Gillen ◽  
Mathew C. Celina
Keyword(s):  
Power Law ◽  
Nuclear Power ◽  
Power Plants ◽  
Time Dependent ◽  
International Electrotechnical Commission ◽  
Ambient Conditions ◽  
Energy Agency ◽  
Degradation Rates ◽  
Simplified Method ◽  
Aging Conditions

ABSTRACT Over the past 20 y, the International Electrotechnical Commission and the International Atomic Energy Agency have published several Technical Documents describing recommended methods for carrying out accelerated radiation plus temperature aging of cable materials in nuclear power plants. These methods include the power law method, the time-dependent model, the dose to equivalent damage approach, and the simplified method approach. Because of the expected and observed changes in chemistry that occur as aging conditions transition radiation–temperature space, we highlight issues with the time-dependent and simplified method approaches by showing that they do not simulate the chemistry occurring under ambient conditions. The DED approach and a recent modification, the Matched Accelerated Conditions approach, can handle the changes in chemistry for many important cable materials and therefore offer more confident accelerated simulations. Problems with the power law method are then briefly described. Also discussed are the significant issues that occur when trying to simulate the aging of semicrystalline cable materials that show inverse-temperature effects. For these materials, degradation rates under radiation can increase as the aging temperature drops below ∼60 °C, in temperature regions where typical ambient aging conditions occur. A possible approach for dealing with such materials is suggested.

scholarly journals Study on Probabilistic Safety Goals for Multimodule High-Temperature Gas-Cooled Reactor Based on Chinese Societal Risks

2021 ◽  
Vol 2021 ◽  
pp. 1-10
Author(s):  
Jinghan Zhang ◽  
Jun Zhao ◽  
Jiejuan Tong
Keyword(s):  
High Temperature ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Regulatory Commission ◽  
Nuclear Safety ◽  
Energy Agency ◽  
Water Reactor ◽  
Regulatory Commission ◽  
High Temperature Gas ◽  
Probabilistic Safety

Nuclear safety goal is the basic standard for limiting the operational risks of nuclear power plants. The statistics of societal risks are the basis for nuclear safety goals. Core damage frequency (CDF) and large early release frequency (LERF) are typical probabilistic safety goals that are used in the regulation of water-cooled reactors currently. In fact, Chinese current probabilistic safety goals refer to the Nuclear Regulatory Commission (NRC) and the International Atomic Energy Agency (IAEA), and they are not based on Chinese societal risks. And the CDF and LERF proposed for water reactor are not suitable for high-temperature gas-cooled reactors (HTGR), because the design of HTGR is very different from that of water reactor. And current nuclear safety goals are established for single reactor rather than unit or site. Therefore, in this paper, the development of the safety goal of NRC was investigated firstly; then, the societal risks in China were investigated in order to establish the correlation between the probabilistic safety goal of multimodule HTGR and Chinese societal risks. In the end, some other matters about multireactor site were discussed in detail.

Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP

2020 ◽  
Author(s):  
Akihiro Mano ◽  
Jinya Katsuyama ◽  
Yinsheng Li
Keyword(s):  
Fracture Mechanics ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Nuclear Power ◽  
Power Plants ◽  
Corrosion Cracking ◽  
Energy Agency ◽  
Pressurized Water ◽  
Water Reactor ◽  
Probabilistic Fracture Mechanics

Abstract A probabilistic fracture mechanics (PFM) analysis code, PASCAL-SP, has been developed by Japan Atomic Energy Agency (JAEA) to evaluate the failure probability of piping within nuclear power plants considering aged-related degradations such as stress corrosion cracking and fatigue for both pressurized water reactor and boiling water reactor environments. To strengthen the applicability of PASCAL-SP, a benchmarking study is being performed with a PFM analysis code, xLPR, which has been developed by U.S.NRC in collaboration with EPRI. In this benchmarking study, deterministic and probabilistic analyses are undertaken on primary water stress corrosion cracking using the common analysis conditions. A deterministic analysis on the weld residual stress distributions is also considered. These analyses are carried out by U.S.NRC and JAEA independently using their own codes. Currently, the deterministic analyses by both xLPR and PASCAL-SP codes have been finished and probabilistic analyses are underway. This paper presents the details of conditions and comparisons of the results between the two aforementioned codes for the deterministic analyses. Both codes were found to provide almost the same results including the values of stress intensity factor. The conditions and results of the probabilistic analysis obtained from PASCAL-SP are also discussed.

Belarusian Ostrovets nuclear power plant: the challenge of cross-border negotiations to balance economic development and environmental protection†

2020 ◽  
Vol 13 (2) ◽  
pp. 157-168
Author(s):  
Aslan Khuseinovich Abashidze ◽  
Vladimir Mikhailovich Filippov ◽  
Alexander Mikhailovich Solntsev
Keyword(s):  
Economic Development ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Environmental Protection ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
International Environmental Agreements ◽  
Environmental Agreements ◽  
Energy Agency

Abstract States have sovereign rights that allow them to construct nuclear power plants. Moreover, engaging with nuclear power generation makes possible the achievement of the Sustainable Development Goals (2016–30) in combatting climate change, paramount to the Paris Agreement’s initiatives. In the same vein, however, constructing and operating power plants pose strict dangers to both general safety of the public and to national security. Thus, plant operations should strictly abide by the International Atomic Energy Agency (IAEA) standards and international law. As a result, it is important to consider the potential transboundary impacts of nuclear power plants and to conduct an appropriate transboundary environmental impact assessment (EIA). The article examines the construction of the Ostrovets Nuclear Power Plant by Belarus, close to the border of the Republic of Lithuania. The question in focus, however, is as follows: what international procedure can be used to coordinate issues of potentially negative transboundary impacts? Lithuania, in order to avoid the operation of the nuclear power plant, thus sought peaceful settlement of the dispute making use of the dispute resolution mechanisms based on international environmental agreements. The authors of this study show that the treaty bodies, established on the basis of international environmental agreements, provide important assistance in this matter in coordination with the IAEA. The use of these quasi-judicial means of resolving interstate disputes proves effective in pursuing a compromise between economic development and environmental protection. In the absence of such mechanisms at a universal level, one should consider utilizing such mechanisms in other regions of the world.

scholarly journals Risk assessment of prospective investment projects for the construction of nuclear power plants abroad

2018 ◽  
Vol 7 (2.23) ◽  
pp. 251 ◽  
Author(s):  
Anna I. Guseva ◽  
Matvey V. Koptelov
Keyword(s):  
Risk Assessment ◽  
Construction Projects ◽  
Nuclear Power ◽  
Industrial Development ◽  
Power Plants ◽  
Energy Agency ◽  
Investment Projects ◽  
Development Organization ◽  
State Corporation

The article deals with the development of nuclear energy, classification of risks, approaches to risk assessment of investment projects of NPP construction abroad. Presented integrated methodology for assessing the risks of nuclear investment projects is based on the recommendations of the United Nations Industrial Development Organization (UNIDO), the International Atomic Energy Agency (IAEA), the sectoral methodological recommendations of the State corporation Rosatom. A way of accounting for risks in the calculation of economic efficiency is proposed. Calculations have been made for several real NPP construction projects (Rooppur NPP in Bangladesh, Astravets NPP in Belarus, Hanhikivi NPP in Finland). Analysis of the results of these projects shows that, taking into account all types of risks, its investment attractiveness has significantly decreased. 

Coordinated Research Projects at IAEA Concerning RPV and Structural Integrity

2006 ◽  
Author(s):  
William Server ◽  
Timothy Hardin ◽  
Milan Brumovsky´
Keyword(s):  
Ferritic Steel ◽  
Nuclear Power ◽  
Power Plants ◽  
Structural Integrity ◽  
Current Status ◽  
Research Projects ◽  
Energy Agency ◽  
Pressurized Water ◽  
Toughness Testing ◽  
Water Reactors

The International Atomic Energy Agency (IAEA) has had a series of reactor pressure vessel (RPV) structural integrity programs that started back in the 1970s. These Coordinated Research Projects most recently have focused on use of the Master Curve fracture toughness testing approach for RPV and other ferritic steel components and on the issue of pressurized thermal shock (PTS) in operating pressurized water reactors. This paper will provide the current status for these projects and discuss the implications for improved safety of key ferritic steel components in nuclear power plants (NPPs).

scholarly journals 14C in the Environment of Swiss Nuclear Installations

Radiocarbon ◽  
1989 ◽  
Vol 31 (03) ◽  
pp. 747-753 ◽  
Author(s):  
Heinz Hugo Loosli ◽  
Hans Oeschger
Keyword(s):  
Power Law ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Reference Station ◽  
Tree Leaves ◽  
Release Rates ◽  
Close Vicinity

The results of a 10-year survey of 14C content in tree leaves from the vicinity of Swiss nuclear installations are reported. The interpretation is based on the results from a reference station showing a systematic decrease from δ14C = +350 in 1977 to ca 4–190 in 1987. Excess activities of up to ca 100 are observed in the vicinity of nuclear power plants which are compatible with release rates and dilution calculations. A higher excess of up to 1400 is measured in the close vicinity of a small research plant which releases the activity on top of the roof. The determined decrease of the activity with distance can be described by a power law with ca −1.4 in the exponent. Additional doses of 14C to plants and population from excess 14C activities are estimated to be negligible compared to natural doses.

Design and Maintenance in an IAEA Technical Guidelines on Fluid-Structure Interaction

2014 ◽  
Author(s):  
Fumio Inada ◽  
Tomomichi Nakamura ◽  
Takashi Nishihara ◽  
Shigehiko Kaneko ◽  
Manwoong Kim ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Structural Integrity ◽  
General Description ◽  
Fluid Structure Interactions ◽  
Flow Induced Vibration ◽  
Energy Agency ◽  
Fluid Structure ◽  
Component Systems

In nuclear power plants, fluid structure interactions (FSI) occurring in component systems can cause excessive forces or stresses to the structures resulting in mechanical damages that may eventually threaten the structural integrity. FSI in the guidelines includes flow-induced vibration, water hammer, and pipewhip. It can also include movement, deformation, or fracture of equipments by tsunami etc. They can be issues of design and maintenance. Authors cannot find complete guidelines to correspond to the FSI phenomena which can be important in the design and maintenance of nuclear power plants. Based on the background, International Atomic Energy Agency (IAEA) has drafted guidelines on FSI. This paper summarizes general description of FSI as well as design and maintenance against FSI.

International Atomic Energy Agency

1965 ◽  
Vol 19 (4) ◽  
pp. 1043-1052
Keyword(s):  
International Atomic Energy Agency ◽  
Nuclear Power ◽  
Power Plants ◽  
Atomic Energy ◽  
Future Prospects ◽  
Energy Agency ◽  
New Members ◽  
Board Of Governors ◽  
Decisive Importance ◽  
Geneva Conference

The report of the Board of Governors of the International Atomic Energy Agency (IAEA) to the ninth General Conference of the Agency covered the period from July 1, 1964, to June 30, 1965. During the period under review, membership of the Agency increased from 87 to 92. The new members were Cameroun, Costa Rica, Cyprus, Kuwait, and Madagascar. The main event during the period had been the Third International Conference on the Peaceful Uses of Atomic Energy (Third Geneva Conference), which had provided a full evaluation of the experience gained since 1958 in designing, building, and operating nuclear power plants as well as of future prospects for nuclear power being introduced in an increasing number of countries. Ten specialized agencies, 75 states, and the Agency had been represented. The Conference focused its attention on nuclear power, the rapid rise of which as a major source of energy promised to be of decisive importance to the economic development of the world.

Progress With the International Pipe Failure Data Exchange Project

2007 ◽  
Author(s):  
Bengt Lydell ◽  
Alejandro Huerta ◽  
Karen Gott
Keyword(s):  
Nuclear Power ◽  
Data Exchange ◽  
Power Plants ◽  
Crack Depth ◽  
Pipe Failure ◽  
Energy Agency ◽  
Service Experience ◽  
Failure Data ◽  
Wall Thinning ◽  
Engineered Safeguards

Certain member countries of the Organisation for Economic Cooperation and Development (OECD) in 2002 established the OECD Pipe Failure Data Exchange Project (OPDE) to produce an international database on the piping service experience applicable to commercial nuclear power plants. OPDE is operated under the umbrella of the OECD Nuclear Energy Agency (NEA). The Project collects pipe failure data including service-induced wall thinning, part through-wall crack, pinhole leak, leak, and rupture/severance (i.e., events involving large leak rates up to and beyond the make-up capacity of engineered safeguards systems). The part through-wall events include degradation in excess of code allowable for pipe wall thinning or crack depth. OPDE also addresses such degradation that could have generic implications regarding the reliability of in-service inspection. At the end of 2006 the OPDE database included approximately 3,700 records on pipe failure affecting ASME Code Class 1 through 3 and non-Code piping. This paper summarizes the unique data quality considerations that are associated with the reporting and recording of piping component degradation and failure. The paper also summarizes the database content and puts it in perspective relative to past efforts to systematically collect and evaluate service experience data on piping performance.

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