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Welding of main circulation pipeline completed for Unit 2 of Turkey's Akkuyu NPP

On August 27, welding of the main circulation pipeline was completed for Unit 2 of Turkey's Akkuyu Nuclear Power Plant. The pipeline connects the reactor, steam generators, and main circulation pumps, and is one of the key components forming the primary circuit system of the reactor facility. The welding work lasted 73 days and involved welding 32 pipe joints. Engineering technicians, welders, fitters, pipe cutters, non-destructive testing personnel, heat treatment personnel, and quality inspection personnel participated in the relevant operations. During construction, each process step proceeded according to the established technological workflow, and welded joints had to pass inspection before moving to the next stage. According to reports, all welded joints underwent high-temperature heat treatment to relieve internal stress in the metal and ensure compliance with design performance requirements.

2026-08-28

Egyptian Minister of Electricity Inspects Small Modular Reactor Technology in Russia

On August 27, 2026, Egyptian Minister of Electricity and Renewable Energy Mahmoud Esmat visited a small nuclear reactor manufacturing and assembly plant operated by Rosatom during an official visit to Russia. The inspection focused on the latest advancements in small modular reactor-related technologies, industrial application status, and potential cooperation opportunities between the two sides. The Egyptian side stated that such visits align with the country's direction of diversifying energy sources and enhancing the security and sustainability of electricity supply. During the visit, Esmat was briefed on the manufacturing and assembly processes of small reactor components, as well as related safety systems...

2026-08-28

Hole of about 3 meters confirmed at bottom of reactor pressure vessel of Unit 3 at Fukushima Daiichi Nuclear Power Station

Tokyo Electric Power Company (TEPCO) announced on August 27 that a hole approximately 3 meters in diameter has been confirmed at the bottom of the reactor pressure vessel of Unit 3 at the Fukushima Daiichi Nuclear Power Station. The pressure vessel is a steel container that held nuclear fuel before the accident, with a cylindrical shape and a diameter of about 5.5 meters. This is the first time since the core meltdown accident at Units 1 to 3 of the Fukushima Daiichi Nuclear Power Station in 2011 that the specific size and shape of such a hole have been confirmed on the pressure vessel. The hole is believed to be related to the falling of melted nuclear fuel during the 2011 accident. After the accident, the containment vessel of Unit 3 has maintained a relatively high water level for an extended period, and access routes into the containment vessel are limited. TEPCO previously used a micro drone measuring approximately 12 centimeters per side...

2026-08-28

Japan Extends Deadline for Anti-Terrorism Facility Construction at Onagawa Nuclear Power Plant Unit 2

The Nuclear Regulation Authority (NRA) of Japan has officially decided to revise relevant regulations to extend the deadline for installing anti-terrorism facilities, specifically "facilities for responding to specified severe accidents," at nuclear power plants. Under the new rules, the deadline will be adjusted from "within five years after the construction plan is approved" to "within five years after the start of commercial operation." The revised regulations are expected to take effect in September. This change will affect Tohoku Electric Power's Onagawa Nuclear Power Plant Unit 2. The unit, which had faced the possibility of shutdown by December 2026 due to difficulties in completing the required facilities by then, will now be able to continue operating beyond that date. Tohoku Electric Power...

2026-08-28

3D Systems Collaborates with Savannah River National Laboratory to Advance 3D Printing in Nuclear Energy Systems

3D Systems Corporation of the United States announced on August 27 that it has signed a Cooperative Research and Development Agreement (CRADA) with Savannah River National Laboratory (SRNL), under which the two parties will conduct joint research and development on additive manufacturing technology to advance its application in advanced energy production, nuclear energy systems, energy infrastructure resilience, and related mission scenarios. Under the agreement, the two parties will leverage SRNL's Advanced Manufacturing Collaborative (AMC) to advance work in advanced materials development, equipment upgrades, AI and machine learning-assisted process optimization, manufacturing systems, cybersecurity, and workforce development. Collaboration goals include developing next-generation additive manufacturing materials, real-time process optimization tools, and scalable production solutions...

2026-08-28

South Korean research team evaluates pipe rupture risk in nuclear power plants using probabilistic analysis

Researchers from Seoul National University of Science and Technology in South Korea have recently proposed a sensitivity analysis method based on probabilistic fracture mechanics to evaluate the rupture frequency of main coolant piping systems in nuclear power plants. This method can analyze the impact of uncertainties and modeling assumptions on prediction results, helping engineers distinguish extremely low-probability events from relatively more likely failure scenarios. In nuclear power plants, the main coolant piping system plays a critical role in maintaining structural integrity under normal reactor operating conditions. A pipe rupture could trigger a loss-of-coolant accident, and therefore this system has long been included in the key scope of nuclear power plant safety design and assessment.

2026-08-28

South Korean Lawmaker Proposes Special Act on Nuclear-Powered Submarines

Yoo Yong-won, a lawmaker from South Korea's People Power Party (PPP), proposed a draft of the Special Act on the Nuclear-Powered Submarine Project on August 27, aiming to establish a dedicated legal basis for introducing nuclear-powered submarines to South Korea. The South Korean government is currently advancing the nuclear-powered submarine project as a national strategic initiative. At a press conference held at the National Assembly that day, Yoo stated that the existing Defense Acquisition Program Act and Nuclear Safety Act have limitations in fully reflecting the unique characteristics of military nuclear propulsion systems, making it necessary to enact a special law. The draft proposes establishing a Nuclear-Powered Submarine Strategic Committee under the president's leadership to deliberate on major related matters...

2026-08-28

Qinshan Nuclear Power Membrane Deoxygenation Retrofit Project Put into Operation

Recently, the membrane deoxygenation retrofit project at Qinshan Nuclear Power completed commissioning and was put into operation. The project applies membrane deoxygenation technology to the auxiliary feedwater system (ASG) and reactor boron and water makeup system (REA) of Units 1 and 2 at Qinshan Nuclear Power Plant Phase II, optimizing and upgrading the original deoxygenation process. Units 1 and 2 of Qinshan Phase II originally adopted thermal deoxygenation. During long-term operation, this method presented issues such as insufficient redundancy in single-train equipment operation, high temperature and humidity on site, and potential exceedance of auxiliary feedwater tank temperature limits during summer peak temperature periods. To enhance system operational reliability, Qinshan Nuclear Power initiated relevant technical retrofits, introducing membrane separation packaged units to form a parallel standby configuration with the original thermal deoxygenation system, allowing flexible switching...

2026-08-28

Zhangzhou Nuclear Power Unit 4 Completes Hoisting of Four Internal Structure Modules

From August 18 to 27, CNNC 24 completed the hoisting of four concrete modules for the internal structure of Zhangzhou Nuclear Power Unit 4 within 10 consecutive days, covering the evaporator compartments of Loops 3, 2, and 1 as well as the pressurizer compartment, creating conditions for subsequent loop installation and commissioning work. The evaporator and pressurizer are key equipment in the nuclear island loops. The corresponding compartment concrete modules serve both load-bearing fixation and protection functions, representing an important embodiment of the "Hualong One" defense-in-depth safety philosophy at the civil construction stage. The four modules hoisted this time are all irregularly shaped structures, all adopting the "off-site prefabrication + integral modular hoisting" process, with a total hoisting weight of approximately 2,400 tons. Compared with Unit 3, Unit 4 achieved 3...

2026-08-28

Lufeng Nuclear Power Unit 1 Nuclear Island Installation and High-Quality Cold Test Sand Table Exercise Successfully Concluded

From August 18 to August 21, 2026, the China Nuclear Energy Association (hereinafter referred to as the Association) organized relevant experts to successfully carry out the sand table exercise for the nuclear island installation and high-quality cold test of Lufeng Nuclear Power Unit 1. The sand table exercise was led by Hu Guofeng, former Director of Shanghai Nuclear Engineering Research and Design Institute Co., Ltd. and Deputy Director of the Science, Technology and Development Expert Committee, with Li Jingxi, former Director of the South China Nuclear and Radiation Safety Supervision Station of the Ministry of Ecology and Environment, Li Qibin, former Chairman of China Nuclear Industry 23 Construction Co., Ltd., Zeng Hao, former Chairman of CNNC Maintenance Co., Ltd., and Wang Mingliang, former Deputy General Manager of China Nuclear Industry Fifth Construction Co., Ltd., serving as advisors. A total of 24 external experts participated...

2026-08-28

Fangchenggang Nuclear Power Station Unit 2 Completes First Ten-Year Overhaul

On the morning of August 25, Unit 2 of CGNPC Fangchenggang Nuclear Power Station successfully synchronized to the grid on its first attempt following the 7th overhaul, marking the completion of the F207 overhaul undertaken by CGNPC Service Maintenance Company. This overhaul was the first ten-year overhaul since Unit 2 was put into commercial operation. The maintenance process achieved the goal of "no indicator events in safety, quality, and schedule," and made breakthroughs in charging pump maintenance and nuclear-grade socket welding operations. During this overhaul, the nuclear-grade socket welding project was implemented on-site for the first time. To ensure work quality, the maintenance team completed preparatory work in advance, including welding procedure qualification certification, skill qualification process card review and submission, test piece welding, and non-destructive testing, all of which passed acceptance.

2026-08-28

Safety-level DCS Response Time Testing for Unit 3 of Xudabao Nuclear Power Plant Successfully Completed

Recently, with the final test data confirmed to be accurate, the safety-level DCS (Digital Control System) response time testing for Unit 3 of Xudabao Nuclear Power Plant was successfully completed. All test results met the requirements, with no abnormal equipment actions throughout the entire process, providing reliable instrumentation and control assurance for the subsequent fuel loading and stable operation of the unit. The test lasted 14 days and covered 182 test cases, encompassing more than 1,500 functional tests for reactor trip and engineered safety features systems. As a critical step before fuel loading, the safety-level DCS response time test holds significant reference value for verifying the response performance of the unit's safety systems. To ensure the successful completion of the test, the instrumentation and control team adhered to the work philosophy of "comprehensive preparation, strong collaboration, experience feedback, and pragmatic execution," advancing all tasks in an orderly manner.

2026-08-27

Argonne National Laboratory Measures Dust Resuspension Behavior in Radioactive Contamination Scenarios

Researchers at the U.S. Department of Energy's Argonne National Laboratory recently conducted field experiments to simulate the movement of dust particles on concrete surfaces under radioactive contamination scenarios, measuring the effects of pedestrian activity and vehicle traffic on dust dispersion. The study was published in the journal Health Physics and received support from the U.S. Department of Homeland Security Science and Technology Directorate and the Radiological/Nuclear Emergency Response and Recovery Research and Development Program. To control humidity and temperature and prevent dust generation, pedestrian tests were conducted inside a tent. In the image, researchers can be seen entering the tent on the left. Particle counters are placed on a white table, with their hoses extending into the tent to collect air samples. (Image courtesy of Ar...

2026-08-27

NNSA Administrator Brandon Williams Visits Kairos Power to Review SMR Technology

Kairos Power, a U.S. small modular reactor developer, recently announced that Brandon Williams, Administrator of the National Nuclear Security Administration (NNSA), has visited the company's Manufacturing Development Campus in Albuquerque, New Mexico, to review its readiness for advanced reactor deployment. According to Kairos Power, Williams and his delegation toured the campus's advanced manufacturing, fuel development, molten salt production, modular systems, and large-scale hardware verification facilities. The campus serves as a key base for the company's advancement of fluoride salt-cooled high-temperature reactor technology and also supports the engineering validation and manufacturing capability development required for future reactor deployment.

2026-08-27

Ikata Nuclear Power Station Unit 3 in Japan briefly deviated from operational limits due to abnormal signals in protection system instrumentation

Shikoku Electric Power Co. reported on August 27 that abnormal signals from safety protection system instrumentation appeared in the central control room of Ikata Nuclear Power Station Unit 3, which was in normal operation, indicating that one channel of the overtemperature ΔT related instrumentation was unreliable. The operator determined at 22:10 on August 26 that the unit had deviated from the operational limits stipulated in the Reactor Facility Security Regulations. On-site confirmation showed that the unreliable signal originated from 1 of the 4 channels of the overtemperature ΔT protection function. Overtemperature ΔT is one of the reactor automatic trip elements, used to protect in-core fuel; its limit value is calculated based on parameters such as reactor power, pressurizer pressure, and...

2026-08-27