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Journal Articles

Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool; Confirmation of fuel temperature calculation function with oxidation reaction in the SAMPSON code

Suzuki, Hiroaki*; Morita, Yoshihiro*; Naito, Masanori*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

Mechanical Engineering Journal (Internet), 7(3), p.19-00450_1 - 19-00450_17, 2020/06

In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Air oxidation models based on oxidation data obtained on the Zircaroy-4 cladding (ANL model) and the Zircaroy-2 cladding (JAEA model) were included in the modified SAMPSON code. Experiments done by Sandia National Laboratory using simulated fuel assemblies equivalent to those of an actual BWR plant were analyzed by the modified SAMPSON code to confirm the functions for analysis of the severe SFP accidents. The rapid fuel rod temperature rise due to the Zr air oxidation reaction could be reasonably evaluated by the SAMPSON analysis. The SFP accident analyses were conducted with different initial water levels which were no water, water level at bottom of active fuel, and water level at half of active fuel. The present analysis showed that the earliest temperature rise of the fuel rod surface occurred when there was no water in the SFP and natural circulation of air became possible.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 5; Loss of coolant accident analysis by SAMPSON code

Morita, Yoshihiro*; Suzuki, Hiroaki*; Naito, Masanori*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki

no journal, , 

We conducted the preliminary analysis for the phenomenon of loss of coolant in Spent Fuel Pool by MAAP code and reported the analytical results for temperature and relocation behavior of spent fuel channels.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 12; Loss of coolant accident analysis by improved SAMPSON code

Morita, Yoshihiro*; Suzuki, Hiroaki*; Naito, Masanori*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

no journal, , 

A new model including the spent fuel pool (SFP) or Zr oxidation behavior which is necessary to evaluate the SFP accident caused by cooling function loss was developed and implanted in the severe accident code SAMPSON in this work. Results of the evaluation using the improved code will be presented.

Oral presentation

Evaluation of short and long-term behavior of radioactive nuclides distributed in Fukushima Daiichi NPP, 3; Phenomenologically estimation of dose rate in a building based on an accident scenario investigation (Unit-1)

Kino, Chiaki*; Karasawa, Hidetoshi*; Uchida, Shunsuke*; Naito, Masanori*; Osaka, Masahiko

no journal, , 

FP distribution in 1F was phenomenologically evaluated in views of accident scenario. Possible retention of chemisorbed Cs in the separator etc. was implied.

Oral presentation

Estimation of Cs distribution and characteristics in the reactor under severe accident, 5; Summary

Miwa, Shuhei; Karasawa, Hidetoshi; Kino, Chiaki*; Nakajima, Kunihisa; Suzuki, Eriko; Imoto, Jumpei

no journal, , 

We investigated the Cs distribution and characteristics in the upper structure of the reactor pressure vessel in TEPCO Fukushima Daiichi Nuclear Power Station (1F) based on the data on the amount of Cs chemisorbed compound onto stainless steel in the upper structure calculated by severe accident analysis code SAMPSON with improved Cs chemisorption model, the chemical form and water solubility of Cs chemisorbed compounds obtained by experiments which are prerequisite for the evaluation of long-term behaviors. The results indicate that the amount of insoluble Cs chemisorbed compounds can be lower than that estimated by using existing Cs chemisorption model.

Oral presentation

Estimation of Cs distribution and characteristics in the reactor under severe accident, 1; Evaluation of amount of chemisorbed Cs in the reactor

Karasawa, Hidetoshi; Miwa, Shuhei; Kino, Chiaki*

no journal, , 

Amount of CsOH chemisorbed on surfaces of structural materials such as separators and dryers in unit1, unit2, unit3 were evaluated by the SAMPSON code under the Fukushima Daiichi Nuclear Power Plant severe accident conditions. Concentrations of CsOH vapors are decreased due to reaction with Mo vapors and to produce aerosols under decreasing gas temperature. As an existing chemisorption model is independent on CsOH concentrations, an ECUME has developed a new chemisorption model with a function of CsOH concentrations and gas temperature. Cs absorbed amounts were changed unit by unit due to different CsOH concentrations and gas temperature. Evaluation of CsOH chemisorption in a SA analysis needs the new chemisorption model with dependency of CsOH concentrations.

Oral presentation

Evaluation of chemisorption experiments by the SA analysis code SAMPSON

Karasawa, Hidetoshi; Miwa, Shuhei; Suzuki, Eriko; Nakajima, Kunihisa; Kino, Chiaki*

no journal, , 

Temperature effects of chemisorption of CsOH vapor generated at about 1000K on SUS were examined using TeRRa test apparatus with temperature gradient tube from 1273K to 473K. The chemisorption amounts were measured using IPS after dissolving test coupons. These results were calculated using the SA code, SAMPSON. For the test analysis, the thermal hydraulic analysis (THA) module and the FP transport analysis (FPTA) module were used. The FPTA could calculated the chemisorption amount within the experimental error range using the gas temperature calculated by the THA module. So the temperature dependency of the chemisorption model used in the calculation was validated.

Oral presentation

Development of analysis method based on SAMPSON for ATF with Cr coated Zr alloy cladding

Tezuka, Kennichi*; Kino, Chiaki*; Yamashita, Susumu; Mohamad, A. B.; Nemoto, Yoshiyuki

no journal, , 

no abstracts in English

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