Development of rapid atmospheric source term estimation system for AP1000 nuclear power plant

Zhao, Yunfei; Zhang, Liguo; Tong, Jiejuan

doi:10.1016/j.pnucene.2015.02.008

Cited by 26 publications

(10 citation statements)

References 11 publications

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“…The simulation constraints used in this work are listed in Tables 3 and 4. The inventory of 1000 MWe PWR is evaluated by ORI-GEN2.2 code and compared with the core inventory listed in the USNRC (1975) ( Figure 7) and with AP-1000 core inventory [42]. A good comparison has been seen with inventories listed in literature (Figure 7) but the coolant inventory of AP-1000 has been found to be slightly higher than our selected plant ( Table 5).…”

Section: Discussionmentioning

confidence: 64%

“…The comparison of core and coolant inventory with AP-1000 and KORI-1 is listed in Table 5. The core and coolant inventory have been found to be comparable with AP-1000 PWR [42]. Since our plant and AP-1000 have similar core power whereas KORI-1 is 1600 MWth PWR, the core and coolant inventories for selected isotopes for KORI-1 have been found to be less in quantity as compared to our plant and AP-1000.…”

Section: Volumetric Mass Inventorymentioning

confidence: 57%

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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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Section: Discussionmentioning

confidence: 64%

Section: Volumetric Mass Inventorymentioning

confidence: 57%

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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“…dengan menjumlahkan konsekuensi dari semua perwakilan probabilitas kelompok, konsekuensi rata-rata tahunan dapat diperoleh. Perhitungan dispersi di atmosfer menggunakan persamaan Gaussian yang sudah tersegmentasi yang dimodifikasi dari persamaan Gifford [1, [8][9].…”

Section: Pc-cosyma (Code System Of Methods For Assessing Radiologicalunclassified

“…Source term dipostulasikan kondisi severe accident dengan tujuan analisis statistika lebih terlihat pada sumber sebaran yang lebih besar. Source term yang digunakan pada penelitian ini menggunakan source term yang sudah dihitung pada PWR 1000-MWe [3,8,11].…”

Section: Metodologiunclassified

PENGARUH KONDISI ATMOSFERIK TERHADAP PERHITUNGAN PROBABILISTIK DAMPAK RADIOLOGI KECELAKAAN PWR 1000-MWe

Udiyani

Kuntjoro

2015

Tri Dasa Mega

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ABSTRAK PENGARUH KONDISI ATMOSFERIK TERHADAP PERHITUNGAN PROBABILISTIK DAMPAK RADIOLOGI KECELAKAAN PWR 1000-MWe. Perhitungan dampak kecelakaan radiologi terhadap lepasan produk fisi akibat kecelakaan potensial yang mungkin terjadi di Pressurized Water Reactor (PWR) diperlukan secara probabilistik. Mengingat kondisi atmosfer sangat berperan terhadap dispersi radionuklida di lingkungan, dalam penelitian ini akan dianalisis pengaruh kondisi atmosferik terhadap perhitungan probabilistik dari konsekuensi kecelakaan reaktor. Tujuan penelitian adalah melakukan analisis terhadap pengaruh kondisi atmosfer berdasarkan model data input meteorologi terhadap dampak radiologi kecelakaan PWR 1000-MWe yang disimulasikan pada tapak yang mempunyai kondisi meteorologi yang berbeda. Simulasi menggunakan program PC-Cosyma dengan moda perhitungan probabilistik, dengan data input meteorologi yang dieksekusi secara cyclic dan stratified, dan disimulasikan di Tapak Semenanjung Muria dan Pesisir Serang. Data meteorologi diambil setiap jam untuk jangka waktu satu tahun. Hasil perhitungan menunjukkan bahwa frekuensi kumulatif untuk model input yang sama untuk Tapak pesisir Serang lebih tinggi dibandingkan dengan Semenanjung Muria. Untuk tapak yang sama, frekuensi kumulatif model input cyclic lebih tinggi dibandingkan model stratified. Model cyclic memberikan keleluasan dalam menentukan tingkat ketelitian perhitungan dan tidak membutuhkan data acuan dibandingkan dengan model stratified. Penggunaan model cyclic dan stratified melibatkan jumlah data yang besar dan pengulangan perhitungan akan meningkatkan ketelitian nilai-nilai statistika perhitungan. Kata kunci: dampak kecelakaan, PWR 1000-MWe, probabilistik, atmosferik, PC-Cosyma ABSTRACT THE INFLUENCE OF ATMOSPHERIC CONDITIONS TO PROBABILISTIC CALCULATION OF IMPACT OF RADIOLOGY ACCIDENT ON PWR-1000MWe. The calculation of the radiological impact of the fission products releases due to potential accidents that may occur in the PWR (Pressurized Water Reactor) is required in a probabilistic. The atmospheric conditions greatly contribute to the dispersion of radionuclides in the environment, so that in this study will be analyzed the influence of atmospheric conditions on probabilistic calculation of the reactor accidents consequences. The objective of this study is to conduct an analysis of the influence of atmospheric conditions based on meteorological input data models on the radiological consequences of PWR-1000MWe accidents. Simulations using PC-Cosyma code with probabilistic calculations mode, the meteorological data input executed cyclic and stratified, the meteorological input data are executed in the cyclic and stratified, and simulated in Muria Peninsula and Serang Coastal. Meteorological data were taken every hour for the duration of the year. The result showed that the cumulative frequency for the same input models for Serang coastal is higher than the Muria Peninsula. For the same site, cumulative frequency on cyclic input models is higher than stratified models. The cyclic models provide flexibility in determining the level of accuracy of calculations and do not require reference data compared to stratified models. The use of cyclic and stratified models involving large amounts of data and calculation repetition will improve the accuracy of statistical calculation values. Keywords: accident impact, PWR 1000 MWe, probabilistic, atmospheric, PC-Cosyma

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“…This source term can provide a necessary input for the consecutive simulation of atmospheric dispersion and radiological dose assessment to the public. Based on the dose assessment, corresponding emergency response actions could be recommended such as whether people should be guided by evacuation or shelter-inplace protective actions (Zhao et al, 2015). Radiological source term estimation, atmospheric dispersion analysis and radiation dose assessment have been considered as the most important safety concerns in the area of emergency response after a nuclear accident.…”

Section: Introductionmentioning

confidence: 99%

Nuclear Emergency Management using Accident Consequence Analysis Code

Uddin¹,

Kim

2019

J. Korean Soc. Hazard Mitig

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Shin Kori Unit 3 is a new pressurized water reactor in Advanced Power Reactor 1400, which was developed by Korea Hydro and Nuclear Power Co. and commenced commercial operation in December 2016. We calculated the radionuclide concentrations and related radiation doses at the early stage of accidents under the assumption of hypothetical severe nuclear accidents in Shin Kori Unit 3. In this study, the radiological source terms of the accident scenarios were evaluated using the radiological assessment system for consequence analysis code, which has been used as a regulatory software tool for emergency response applications developed by the United States Nuclear Regulatory Commission. In general, the atmospheric transport, dispersion, and deposition processes of radioactive materials can be simulated by the Gaussian model using a straight-line trajectory Gaussian plume model for short distances and a Lagrangian Gaussian puff model for long distances. The most dangerous scenarios were observed during winter when we considered two accident scenarios, namely, long-term station blackout (LTSBO) and loss-of-coolant accident (LOCA), based on the reactor conditions and seasonal effects. The total effective dose equivalent values for LTSBO and LOCA were estimated to be 14 and 0.08 mSv, respectively, in the precautionary action zone of 5 km in two days after the accident. According to Korean regulations on urgent public protective actions, the criteria are 10 mSv in two days for indoor sheltering and 50 mSv in one week for public evacuation. In the LTSBO case, we found that immediate public protective measures were required. Appropriate decisions must be made by the off-site emergency management center under the Nuclear Safety and Security Commission in Korea.

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Development of rapid atmospheric source term estimation system for AP1000 nuclear power plant

Cited by 26 publications

References 11 publications

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

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

PENGARUH KONDISI ATMOSFERIK TERHADAP PERHITUNGAN PROBABILISTIK DAMPAK RADIOLOGI KECELAKAAN PWR 1000-MWe

Nuclear Emergency Management using Accident Consequence Analysis Code

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