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شبیهسازی پخش مواد پرتوزا حاصل از یک حادثه فرضی برای راکتور ABV با استفاده از کد RASCAL | ||
علوم و فناوریهای پدافند نوین | ||
مقاله 4، دوره 14، شماره 4 - شماره پیاپی 54، بهمن 1402، صفحه 253-263 | ||
نوع مقاله: مقاله پژوهشی | ||
نویسندگان | ||
محمد آزادی فر1؛ محسن شایسته* 2؛ جواد کریمی3 | ||
1دانشجوی کارشناسی ارشد، دانشگاه جامع امام حسین (ع)، تهران، ایران | ||
2دانشیار، دانشگاه جامع امام حسین (ع)، تهران، ایران | ||
3پژوهشگر، دانشگاه جامع امام حسین (ع) ، تهران ، ایران | ||
تاریخ دریافت: 13 مهر 1402، تاریخ بازنگری: 24 آذر 1402، تاریخ پذیرش: 04 دی 1402 | ||
چکیده | ||
ارزیابی دز ناشی از گسیل مواد پرتوزا یکی از مقولههای اصلی ایمنی رآکتورها و تأسیسات هستهای است. پخش مواد پرتوزا که ممکن است ناشی از یک حادثه در تأسیسات هستهای باشد، میتواند سبب خطرات پرتویی برای انسان و محیطزیست شود، در چنین شرایطی بایستی میزان دز ارزیابی شود و در صورت لزوم اقدامات کنترلی مناسب لحاظ گردد. در این مقاله فرض شده است، رآکتور ABV که یک رآکتور ماژولار کوچک است، بهمنظور تأمین انرژی تأسیسات صنعتی در اطراف شهرستان مبارکه واقع در استان اصفهان نصب شده است. هدف اصلی این پژوهش، بررسی پخش جوی سزیم-134 و سزیم-137 ناشی از یک حادثه فرضی ذوب قلب در این رآکتور است. مقدار رادیوایزوتوپهای سزیم-134 و 137 موجود در قلب رآکتور در زمان وقوع حادثه که در کارهای قبلی نویسندگان محاسبه شده است، بهعنوان چشمه تابشی فرض میشود. سپس، با استفاده از نرمافزار RASCAL و با فرض اینکه مدتزمان رهاسازی این دو رادیوایزوتوپ یک ساعت باشد، پخش جوی آنها در دو روز بعد از حادثه و تا شعاع 80 کیلومتری مورد بررسی قرار گرفته است. در این پژوهش کمیتهای دز مؤثر کل TEDE، دز تیروئید، CEDE استنشاقی، و همچنین آلودگی سطحی این دو ایزوتوپ محاسبه و الگوی پخش آنها تا فواصل 80 کیلومتری از محل وقوع حادثه ترسیم شده است. | ||
کلیدواژهها | ||
رآکتور ماژولار کوچک؛ حادثه هستهای؛ کد RASCAL؛ میزان دز؛ سزیم-134؛ سزیم-137 | ||
عنوان مقاله [English] | ||
Simulation of Radioactive Material Release Resulting from a Hypothetical Accident for ABV Reactor Using RASCAL Code | ||
نویسندگان [English] | ||
Mohammad Azadifar1؛ Mohsen Shayesteh2؛ Javad Karimi3 | ||
1Master's student, Imam Hossein University (AS), Tehran, Iran | ||
2Associate Professor, Imam Hossein University, Tehran, Iran | ||
3Researcher, Imam Hossein University . Tehran, Iran | ||
چکیده [English] | ||
Dose evaluation of radioactive materials is one of the main safety categories of reactors and nuclear facilities. The spread of radioactive materials, which may be caused by an accident in a nuclear facility, can cause radiation hazards to humans and the environment, in such a situation, the dose should be evaluated and, if necessary, appropriate control measures should be taken into account. In this article, it is assumed that the ABV reactor, which is a small modular reactor, has been installed in order to supply energy to industrial facilities around Mobarake city, located in Isfahan province. The main goal of this research is to investigate the atmospheric release of cesium-134 and cesium-137 caused by a hypothetical core meltdown incident in this reactor. The amount of cesium-134 and 137 radioisotopes present in the reactor core at the time of the accident, which was calculated in the previous works of the authors, is assumed as a radiation source. Then, using RASCAL software and assuming that the release time of these two radioisotopes is one hour, their atmospheric distribution has been investigated in two days after the accident and up to a radius of 80 km. In this research, total effective dose of TEDE, thyroid dose, inhaled CEDE, as well as the surface pollution of these two isotopes have been calculated and their distribution pattern up to 80 km distance from the accident site has been drawn. | ||
کلیدواژهها [English] | ||
Small Modular Reactor, Nuclear Accident, RASCAL Code, Dose Rate, Cs-134, Cs-137 | ||
مراجع | ||
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