Analysis of severe accident progression and Cs behavior for SBO event during mid-loop operation of OPR1000 using MELCOR

Park, Yerim; Shin, Hoyoung; Kim, Seungwoo; Jin, Young Ho; Kim, Dong Ha; Jae, Moosung

doi:10.1016/j.net.2021.03.006

Cited by 4 publications

(1 citation statement)

References 2 publications

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“…The results indicated that the LOCA pathway affects the pathway of the safety injection system, resulting in different amounts of radionuclides released from the four LOCA pathways. Park 15 used MELCOR to study the release behavior of radionuclide Cs during a full‐plant blackout accident, considering operation of the middle loop as a case study, and comparing and analyzing the influence of middle loop operation and full‐power operation on the amount of Cs radionuclides released. The results indicated that Cs radionuclides released into the containment vessel were different due to chemisorption of the reactor coolant system.…”

Section: Introductionmentioning

confidence: 99%

Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident

Zhao

Zou²,

et al. 2022

Intl J of Energy Research

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Summary A simulation calculation model in the case of a severe accident such as a loss of coolant accident (LOCA) was established and calculated by MELCOR code in a marine pressurized water reactor. The effects of severe accidents on the hydrogen source term, release of the radionuclide source term, and the accident process were investigated, and the radiation consequences were analyzed. LOCA sensitivity analysis was conducted with different break sizes; the release and diffusion of source terms were analyzed. The results indicated that the hydrogen yield in the reactor core was dependent on the temperature, and on the residual water in the reactor core, which has no direct relationship with the break size. The break size directly affected the accident progression. However, when the break exceeded a certain size, it did not affect the LOCA process. The break size may not change to change the release amount and migration rule of radionuclides such as Xe and I, and the fission product CsI, as final containment is in dynamic equilibrium in LOCA conditions. The contents of fission products released into the containment vessel, major loop, cavity, and the environment are sensitive to the break size. However, no special correlation is observed between the amount released and the break size. Highlights The hydrogen yield in the reactor core was dependent on the temperature, and on the residual water in the reactor core, which has no direct relationship with the break size. The break size may not change to change the release amount and migration rule of radionuclides such as Xe, I, and CsI, as final containment is in dynamic equilibrium in LOCA conditions. No particular correlation is observed between the amount of radionuclide released and the break size.

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Section: Introductionmentioning

confidence: 99%