The SAM Software System for Modeling Severe Accidents at Nuclear Power Plants Equipped with WER Reactors on Full-Scale and Analytic Training Simulators

D. Yu. Osadchaya; R. L. Fuks

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The SAM Software System for Modeling Severe Accidents at Nuclear Power Plants Equipped with WER Reactors on Full-Scale and Analytic Training Simulators

机译：配备有WER反应堆的核电厂严重事故建模的SAM软件系统，具有完整的规模和分析培训模拟器

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The architecture of the SAM software package intended for modeling beyond-design-basis accidents at nuclear power plants equipped with WER reactors evolving into a severe stage with core melting and failure of the reactor pressure vessel is presented. By using the SAM software package it is possible to perform comprehensive modeling of the entire emergency process from the failure initiating event to the stage of severe accident involving meltdown of nuclear fuel, failure of the reactor pressure vessel, and escape of corium onto the concrete basement or into the corium catcher with retention of molten products in it.

机译：提出了用于对装备有WER反应堆的核电站中超出设计基准的事故进行建模的SAM软件包的体系结构，该事故演变为具有堆芯熔化和反应堆压力容器故障的严重阶段。通过使用SAM软件包，可以对从故障启动事件到严重事故阶段的整个紧急过程进行全面建模，该过程涉及核燃料的熔化，反应堆压力容器的故障以及真皮上的钙泄漏。或进入其中保留有熔融产品的捕集器。

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来源
《Thermal engineering》 |2014年第4期|303-308|共6页
作者
D. Yu. Osadchaya; R. L. Fuks;
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作者单位

General Energy Technologies, Ryazanskii pr. 22, korp. 2, Moscow, 109428 Russia;

General Energy Technologies, Ryazanskii pr. 22, korp. 2, Moscow, 109428 Russia;

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原文格式 PDF
正文语种 eng
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关键词
NPP; training simulator; severe accident; corium catcher;

机译：核电厂训练模拟器;严重事故皮质捕手;

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专利

1. Design Analysis of the Molten Core Confinement within the Reactor Vessel in the Case of Severe Accidents at Nuclear Power Plants Equipped with a Reactor of the VVER Type [J] . Yu. A. Zvonaryov, M. A. Budaev, A. M. Volchek, Physics of atomic nuclei . 2013,第14期

机译：在装有VVER型反应堆的核电厂发生严重事故的情况下，反应堆容器内熔核限制区的设计分析
2. Experimental Investigations of Thermal—Hydraulic Processes Arising during Operation of the Passive Safety Systems Used in New Projects of Nuclear Power Plants Equipped with WER Reactors [J] . A. V. Morozov, O. V. Remizov, D. S. Kalyakin Thermal engineering . 2014,第5期

机译：装有WER反应堆的核电站新项目中使用的被动安全系统运行期间发生的热力-液压过程的实验研究
3. Using the STAR CCM+ Software System for Modeling the Thermal State and Natural Convection in the Melt Metal Layer during Severe Accidents in WER Reactors [J] . N. A. Kochetov, V. D. Loktionov, A. S. Sidorov Thermal engineering . 2015,第9期

机译：使用STAR CCM +软件系统对WER反应堆中严重事故期间熔融金属层的热状态和自然对流建模
4. Design of a Software Training System for Severe Accident Mitigation of Korean Standard Nuclear Power Plants [C] . Ko-Ryu Kim, Soo-Yong Park, Yong-Man Song ICAPP 2008;International conference on advances in nuclear power plants . 2008

机译：韩国标准核电站严重事故缓解软件培训系统的设计
5. A model for the release, dispersion and environmental impact of a postulated reactor accident from a submerged commercial nuclear power plant. [D] . Bertch, Timothy Creston. 1998

机译：淹没式商业核电站发生的假定反应堆事故的释放，扩散和环境影响的模型。
6. Spatiotemporal association of low birth weight with Cs-137 deposition at the prefecture level in Japan after the Fukushima nuclear power plant accidents: an analytical-ecologic epidemiological study [O] . Hagen Scherb, Keiji Hayashi 2020

机译：在福岛核电站事故后日本县级CS-137沉积的时尚血为低出生体重：分析 - 生态流行病学研究
7. Severe reactor accidents and the modeling of severe reactor accidents with MELCOR-version 2.1 for power plant units Olkiluoto 1 and Olkiluoto 2 [O] . Koivunen Petri 2016

机译：严重的反应堆事故和发电厂单元Olkiluoto 1和Olkiluoto 2的MELCOR版本2.1的严重反应堆事故建模
8. Reactor Safety Study:An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix VII. Release of Radioactivity in Reactor Accidents. Appendix VIII. Physical Processes in Reactor Meltdown Accidents. Appendix IX. Safety Design Rationale for Nuclear Power Plants. Appendix X. Design Adequacy. [R] . 1976

机译：反应堆安全研究：美国商业核电厂事故风险评估。附录七。反应堆事故中放射性的释放。附录八。反应堆熔毁事故中的物理过程。附录九。核电厂安全设计理念。附录X.设计充分性。

The SAM Software System for Modeling Severe Accidents at Nuclear Power Plants Equipped with WER Reactors on Full-Scale and Analytic Training Simulators

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