scholarly journals The buckling strength of a steel containment vessel with discontinuous stiffening rings of a nuclear power plant

2020 ◽  
Vol 86 (890) ◽  
pp. 20-00245-20-00245
Author(s):  
Kazuhiro MIURA ◽  
Takashi OKAFUJI ◽  
Mitsuhiro NAKAMURA ◽  
Tatsuyuki HARADA ◽  
Noriyuki HAKODA ◽  
...  
2020 ◽  
Vol 86 (892) ◽  
pp. 20-00248-20-00248
Author(s):  
Takashi OKAFUJI ◽  
Kazuhiro MIURA ◽  
Mitsuhiro NAKAMURA ◽  
Tatsuyuki HARADA ◽  
Noriyuki HAKODA ◽  
...  

Author(s):  
Mitsuru Imamura ◽  
Kotaro Sato ◽  
Tadashi Narabayashi ◽  
Yoichiro Shimazu ◽  
Masashi Tsuji

We have studied nuclear power plant for district heating. Already some towns and villages in Hokkaido have requested small reactor for district heating. Using existing technology allows us to shorten development period and to keep a lid on development cost. We decided to develop new reactor based on “MUTSU” reactor technology because “MUTSU” had already proved its safety. And this reactor was boron free reactor. It allows plant system to reduce the chemical control system. And moderator temperature coefficient is deeply negative. It means to improve its operability and leads to dependability enhancement. We calculated burn-up calculation of erbium addition fuel. In the result, the core life became about 10 years. And we adapt the cassette type refueling during outage in order to maintain nonproliferation. In the district heating system, a double heat exchanger system enables to response to load change in season. To obtain the acceptance of public, this system has a leak prevention system of radioactive materials to public. And road heating system of low grade heat utilization from turbine condenser leads to improve the heat utilization efficiency. We carried out performance evaluation test of district heating pipeline. Then the heat loss of pipeline is estimated at about 0.440 °C/km. This result meets general condition, which is about 1 °C/km. This small plant has passive safety system. It is natural cooling of containment vessel. In case of loss of coolant accident, decay heat can remove by natural convection air cooling after 6 hours. Decay heat within 6 hours can remove by evaporative heat transfer of pool on containment vessel.


2020 ◽  
Vol 44 (4) ◽  
pp. 291-300 ◽  
Author(s):  
Junseok Yoon ◽  
Yunheung Kim ◽  
Keun-Tae Park ◽  
Wang-Myung Kang ◽  
Beom-Soo Kang

Author(s):  
Mitsuyuki Nakano ◽  
Haruko Sasaki ◽  
Tomokazu Watanabe ◽  
Ayumi Maezawa

At Fukushima Dai-ichi nuclear power plant zircaloy that was used for cladding tube was exposed to high temperature steam and Hydrogen was produced by rapid oxidation. Essentially produced oxygen had to be sealed in containment vessel and released to the air by venting. However Hydrogen released from containment vessel were stored in reactor building and exploded at the NPP. From the experience engineers recognized that countermeasure to prevent Hydrogen leak from containment vessel was required. Unfortunately there are few studies relevant to Hydrogen permeability at high temperature and demanded Hydrogen permeability coefficient of sealing material in the case of high temperature exposure. In this study tests were conducted to predict Hydrogen permeability through rubber gasket at ACCIDENT. Experimental conditions were 1) deteriorated by heat, 2) deteriorated by heat and steam, 3) at high temperature. Tests were conducted for Silicone rubber, EPDM, NBR and Fluoro-rubber and we found that there was no significant difference between the rubbers Hydrogen permeability coefficient under conditions from 1) to 3) without the case of losing its elasticity. Currently we can present basic data to predict Hydrogen leak volume from containment vessel to reactor building at ACCIDENT. Based on the data we calculated Hydrogen leak volume from containment vessel through top flange of Fukushima Dai-ichi nuclear power plant in the case that zircaloy was melted completely as example.


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