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Murakami Lab
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A lab that works on safety management of nuclear power plants and on research into nuclear materials.
AboutAbout the lab
Toward trustworthy nuclear energy systems
The Murakami Lab studies safety management of nuclear power plants and nuclear materials.
The safety of a nuclear power plant can be improved even after construction is complete, throughout the entire period in which the plant remains in use.
The lab studies how to manage this, from the perspectives of using risk information, maintenance, and aging management.
In its materials research, the lab uses experiments and analysis to clarify complex phenomena that arise from the interaction between radiation and matter, with the aim of providing highly reliable nuclear materials.
Key terms
- Aging management
- Measures for nuclear power plants that have been operating for a long time, in which equipment degradation is evaluated so that the plants can continue to be used safely
- Amorphization
- A change in which atoms that were neatly arranged in a crystal lose that order and fall into a disordered state
- Dose rate effect
- A phenomenon in which, even when the total amount of radiation received is the same, the degree of material degradation differs depending on the rate (dose rate) at which it is received
NewsLab news
Analysis of the improper case involving Chubu Electric Power's determination of design basis ground motion published in the Japanese-language Transactions of the Atomic Energy Society of Japan
A student received the Presentation Award at the Japan Society of Maintenology academic conference
Results of joint research with employees of an electric power company published as a paper
Research results on aging management of concrete published
A master's student received the Encouragement Award at the Japan Society of Maintenology academic conference
ResearchResearch themes
Toward trustworthy nuclear energy systems, the lab works on safety management and on nuclear materials research. Its research projects, supported by external funding and other sources, include the search for new alloys and the evaluation of degradation in reactor materials and concrete.
*Illustrative imageSearching for Lightweight Alloys That Resist Irradiation Damage
Among high-entropy alloys, which mix several elements in roughly equal proportions, the lab is searching for alloys that are lighter than iron and whose dimensions change little even under irradiation at high temperatures.
*Illustrative imageNeutron-Induced Swelling of Concrete Aggregate
In concrete near a nuclear reactor, many of the minerals in the aggregate become amorphous and swell when they are hit by neutrons. Together with collaborators, the lab investigated the relationship between irradiation dose and the resulting swelling.
*Illustrative imageMaterial Degradation That Depends on the Rate of Irradiation
To clarify the dose rate effect, which is a problem in the degradation of reactor materials, the lab uses ion irradiation and is developing experimental methods such as transmission electron microscopy combined with an accelerator.
*Illustrative imageEvaluating Crack Growth Probabilistically
The lab is verifying PASCAL, an analysis code developed by the Japan Atomic Energy Agency that evaluates crack growth probabilistically, in cooperation with other universities and companies, and is also considering new evaluation research.
MembersFaculty
The members of the Murakami Lab are faculty members, project researchers, and collaborators.As of 2026
- Associate ProfessorKenta MurakamiPublications ↗
- Project Associate ProfessorJinya Katsuyama
- Project Assistant ProfessorTaro YaoyamaPublications ↗
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Report an errorAbout the images
The top and research theme images are illustrative and were not taken at the lab. They are cropped from Wikimedia Commons images. Cropped CC BY-SA images are provided under the same CC BY-SA license as the original (version shown on each line).
- Top image: “Chooz Nuclear Power Plant-9362” Raimond Spekking / CC BY-SA 4.0 (cropped)
- Searching for Lightweight Alloys That Resist Irradiation Damage: “Microstructure of High-Entropy Alloy AlCoCrFeNi₂.₁” OndrejAmbroz / CC BY 4.0 (cropped)
- Neutron-Induced Swelling of Concrete Aggregate: “Alkalic granite (GeoDIL number - 1524)” Darla Sondrol / CC0 (cropped)
- Material Degradation That Depends on the Rate of Irradiation: “TEM micrograph dislocations precipitate stainless steel 1” Wikityke at English Wikipedia / CC BY-SA 3.0 (cropped)
- Evaluating Crack Growth Probabilistically: “Reactor Vessel head” NRC / Public domain (cropped)
- Related lab (Abe Lab): “Tokamak WEST” Christophe Roux / IRFM / CC BY 4.0 (cropped)
- Related lab (Miwa Lab (Visualization Laboratory)): “Buoyant jet” Left.tom / CC BY-SA 4.0 (cropped)
- Related lab (Takata Lab): “Sequoyah Nuclear Power Plant cooling towers” Eric Evenson, USGS / Public domain (cropped)
- Related lab (Demachi Lab): “Cooling towers of a nuclear power plant” Vsatinet / CC BY-SA 4.0 (cropped)
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