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本文介绍了核电站运行期间核岛RX厂房内的仪用压缩空气SAR003BA贮气罐进口逆止阀SAR612VA密封不严出现内漏时,对机组安全运行及安全壳泄漏监测系统带来的影响。并针对这一现象在不影响机组正常运行的情况下,寻求其解决方案。 相似文献
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安全壳是压水堆核电机组的第三道安全屏障,其主要作用是防止放射性物质向外界环境扩散。定期检查机组安全壳在反应堆失水事故(LOCA)压力下的泄漏率,是核电机组安全运行的重要保障。论文基于泄漏率算法模型,搭建安全壳密封性试验系统,具体包括试验设备硬件选型、采集软件编程、试验数据处理方法。通过工程实践,实现了高精度试验数据采集和安全壳泄漏率分析计算。论文成果兼具创新及实用性,可广泛运用于核电站安全壳密封性试验。 相似文献
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为进一步探究核电厂安全壳内环境条件影响泄漏率测量的基本规律,自主研发了压降法安全壳泄漏率数据分析程序,并通过在大尺度安全壳模拟体上开展的泄漏率实验对测量结果进行验证。结合相应的实验数据研究了准稳态与非稳态环境条件下安全壳内温度和相对湿度变化对泄漏率测量值的影响。结果表明,在升温条件下,各温度传感器因所处热环境的差异而形成的不同升温速率会明显影响泄漏率的测量,测量值相比升温前的相对偏差可超过20%。此外,在壳内局部温湿度变化的非稳态环境下,压力与温度传感器的固有延迟效应还会导致泄漏率的测量出现异常。而当壳内温湿度维持恒定或各传感器的温湿度变化速率近似一致时,泄漏率测量值较稳定,可确定其为实际的泄漏率。该研究结论可为进一步认识安全壳泄漏率测量机理和方法优化提供参考。 相似文献
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本文简要介绍了压水堆核电站单层安全壳和双层安全壳及其有关系统的结构和功能,并论述了各种不同安全壳结构的差异和它们对周围环境的影响。对不同安全壳在各种不同运行工况下对周围环境的影响作了分析。对周围环境有影响的“源项”、安全壳的泄漏率及气体的释放方式也作了分析。重点分析了在失水事故(LOCA)时,不同安全壳对周围环境的影响。最后,对如何决定安全壳类型提出了初步看法。 相似文献
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《核标准计量与质量》2017,(3)
海阳核电1号机组为AP100核电厂在冬季实施安全壳结构完整性试验和安全壳整体泄漏率试验的首台机组,试验要求安全壳内大气及其金属温度保持在10℃~48.9℃之间,但海阳市冬季日平均气温低于10℃,给试验带来了极大的挑战。海阳核电1号机组在试验期间采用封堵屏蔽厂房、VCS/VYS联合运行、在屏蔽厂房增设暖风机等一系列温度控制措施,成功地保证了试验的顺利进行。 相似文献
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在发生核电厂严重事故时,为更加快速准确地估算释放至环境的气载放射性核素泄漏速率,提出了一种新的源项反演方法。该方法基于在安全壳附近主动布设的移动探测点所获取的γ能谱数据反演源项,研究了合适探测距离的选择、移动探测点的有效布设及准确反演单个核素泄漏速率的方法。根据研究结果,选择气载放射性核素中泄漏量及特征γ射线能量均相对高的88Kr作为特征核素进行能谱分析;确定合适的探测距离范围为距离安全壳100 m以内;建立γ能谱数据与特征核素泄漏速率的关系,在数值上准确反演放射性核素的泄漏速率。 相似文献
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Tension tests of concrete containment wall elements were conducted as part of a three-phase research program sponsored by the Electric Power Research Institute (EPRI). The objective of the EPRI experimental/analytical program is twofold. The first objective is to provide the utility industry with a test-verified analytical method for making realistic estimates of actual capacities of reinforced and prestressed concrete containments under internal over-pressurization from postulated degraded core accidents. The second objective is to determine qualitative and quantitative leak rate characteristics of typical containment cross-sections with and without penetrations. This paper covers the experimental portion the the EPRI program.The testing program for Phase 1 included eight large-scale specimens representing elements from the wall of a containment. Each specimen was 60-in (1525-mm) square, 24-in (610-mm) thick, and had full-size reinforcing bars. Six specimens were representative of prototypical reinforced concrete containment designs. The remaining two specimens represented prototypical prestressed containment designs.Various reinforcement configurations and loading arrangements resulted in data that permit comparisons of the effects of controlled variables on cracking and subsequent concrete/reinforcement/liner interaction in containment elements.Subtle differences, due to variations in reinforcement patterns and load applications among the eight specimens, are being used to benchmark the codes being developed in the analytical portion of the EPRI program.Phases 2 and 3 of the test program will examine leak rate characteristics and failure mechanisms at penetrations and structural discontinuities. 相似文献
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为解决传统的无线传感信号无法实现反应堆安全壳内外的信息传输问题,研究设计了通过超声波将无线信号传输到安全壳外的超声通信系统。超声通信系统的发射单元将信号加载于40 kHz的超声波上,超声通信单元将接收到的信号通过超声换能器穿过安全壳传输到接收单元,接收单元通过三级放大、检波、滤波、比较电路,最终实现信号由安全壳内到安全壳外的传输。系统在模拟安全壳工况下试验,试验结果表明:信号能够低功耗、稳定传输,且误码率低于10~(-6)。 相似文献
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The circuit design of a gamma radiation dosimeter is described which permits continuous monitoring of accumulated radiation dosage. An electro-chemical integrating and storage device permits continuous readout in Roentgens followed by a preset audible alarm with an exponential horn tuned for maximum audio output with minimum power input. Any radiation dose rate can be monitored by selecting a G-M detector that gives the desired range. The unit described has a readout range of 200 R and will operate in a radiation field up to 1000 R/hr with an accuracy to within ±5% in an operating temperature range from 0° to 60 °C. The unit weighs less than one pound and has the capability to be clipped to the user's belt, allowing freedom of activity during emergency rescue operations or other hazardous assignment. 相似文献
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双层安全壳核电机组的环廊密封性是核安全的重要保证,需在机组装料前完成测试。气体泄漏幂函数模型在计算民用建筑泄漏时比二次函数模型有更大的压力适用范围和更高的精度。本文以气体泄漏幂函数模型为基础,推导了环廊泄漏率的计算模型,以及带环廊负压修正的幂函数拟合方案,并采用某双层安全壳环廊密封性试验实测数据对该计算模型进行验证。结果表明,本文计算模型比带环廊负压修正的二次函数拟合方案和国外某公司使用的线性拟合方案有更高的精度,与双层安全壳实际泄漏情况更加吻合。 相似文献
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泄漏监测系统用于监测反应堆冷却剂系统压力边界(RCPB)完整性,也是破前漏(LBB)技术应用的先决条件。泄漏综合诊断是泄漏监测系统的核心功能。本文从系统可用性、数据可靠性、单仪表泄漏报警、泄漏综合诊断、报警响应策略、泄漏率定期试验自动计算6个方面构建泄漏综合诊断技术方案。泄漏监测系统的灵敏度和准确性是泄漏综合诊断技术的重要性能指标,也是监测RCPB完整性和LBB技术应用的关键要求。先确定触发单仪表报警的保守阈值范围,以保证检测的灵敏度,再经泄漏综合诊断技术方案复核并调整有效单仪表报警阈值,以保证报警的准确性。通过理论计算、数据分析、多信号的一致性判断,泄漏监测系统能及时准确地诊断出泄漏情况,充分应用智能化泄漏诊断技术,减少运行人员复核报警工作量。 相似文献
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M.D Pandey 《Nuclear Engineering and Design》1997,176(3):15
The main function of a nuclear containment structure is to prevent the leakage of radioactive materials from the reactor in the event of a serious failure in the process system. To maintain a high level of leak integrity, prestressed concrete is widely utilized in containment construction. In bonded prestressing systems, excessive prestressing losses caused by unexpected material deformations and degradation of tendons could result in the loss of leak integrity under an accident. To safeguard against this, the Canadian Standard, CSA N287.7 (1995), recommends periodic inspection and evaluation of prestressing systems of CANDU containments. As bonded tendons are not amenable to direct inspection, the evaluation is based on the testing of a set of beams with features identical to the containment. The paper presents a quantitative reliability-based approach to evaluate the containment integrity in terms of the condition of bonded prestressing systems. The proposed approach utilizes the results of lift-off, destructive, and flexural tests to update the probability distribution of prestressing force, and to revise the calculated reliability against through-wall cracking of containment elements. An acceptable criterion for the results of beam tests is established on the basis of maintaining adequate reliability throughout the service life of the containment. 相似文献