Investigation of severe accident scenario of PWR response to LOCA along with SBO

Hu, Liang; Zhang, Yapei; Li, Longze; Su, G.H.; Tian, Wenxi; Qiu, Suizheng

doi:10.1016/j.pnucene.2015.03.014

Cited by 19 publications

(9 citation statements)

References 15 publications

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“…Xi'an Jiaotong University developed Modular In-vessel Degradation Analysis Code (MIDAC) to simulate the process of in-vessel severe accidents (Wang et al, 2014b,c;Hu et al, 2015). MIDAC includes five modules for calculations: early-behavior, core degradation, debris bed, molten-materials-in-vessel retention (IVR), and connection modules.…”

Section: Code Development Review and Relevant Applicationsmentioning

confidence: 99%

See 1 more Smart Citation

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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Section: Code Development Review and Relevant Applicationsmentioning

confidence: 99%

“…Results provide a clarified explanation of the process and such events as coolant release, ECCS operation, core exposure, etc. Dr. Liang Hu has also investigated the severe accident scenario of PWR reaction to LOCA along with SBO (Hu et al, 2015).…”

Section: Severe Accident Review At Xjtumentioning

confidence: 99%

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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“…After the puff phase, coolant leakage decreases and reaches 50 kg/s [22,37]. Furthermore, the puff release of radioactive material is limited to a number of fission products presented in the coolant [22].…”

Section: In-containment Fission Product Modelmentioning

confidence: 99%

Numerical Simulation of Decontamination of Airborne Fission Products during In-Vessel Release Phase by Containment Spray

Mehboob

2018

Science and Technology of Nuclear Installations

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The containment spray system (CSS) has a significant role in limiting the risk of radioactive exposure to the environment. In this work, the optimal droplet size and pH value of spray water to prevent the fission product release have been evaluated to improve the performance of the spray system during in-vessel release phase. A semikinetic model has been developed and implemented in MATLAB. The sensitivity and removal rate of airborne isotopes with the spray system have been simulated versus the spray activation and failure time, droplet size, and pH value. The alkaline (Na 2 S 2 O 3 ) spray solution and spray water with pH 9.5 have similar scrubbing properties for iodine. However, the removal rate from the CSS has been found to be an approximately inverse square of droplet diameter (1/ 2 ) for Na 2 S 2 O 3 and higher pH of spray water. The numerical results showed that 450 m-850 m droplet with 9.5 pH and higher or the alkaline (Na 2 S 2 O 3 ) solution with 0.2 m 3 /s-0.35 m 3 /s flow rate is optimal for effective scrubbing of in-containment fission products. The proposed model has been validated with TOSQAN experimental data.

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“…These studies can be useful for understanding the effects of passive system and PRZ valve stuck on a core severe accident. Hu have studied the influence of different break sizes in the SBO condition for Chinese three-loop PWR using the MIDAC code (Hu et al, 2015). Important parameters, such as RCS pressure, core melting time, and RPV rupture time are analyzed.…”

Section: Introductionmentioning

confidence: 99%

The accumulator effects on in-vessel severe accident progression of a three loop PWR nuclear power plant in a SBLOCA without safety injection system

Salehi

Shayesteh

2017

Annals of Nuclear Energy

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Investigation of severe accident scenario of PWR response to LOCA along with SBO

Cited by 19 publications

References 15 publications

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Numerical Simulation of Decontamination of Airborne Fission Products during In-Vessel Release Phase by Containment Spray

The accumulator effects on in-vessel severe accident progression of a three loop PWR nuclear power plant in a SBLOCA without safety injection system

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