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The Feasibility of Developing a Computer Based Expert System to Mitigate Nuclear Power Plant Accidents

机译:开发基于计算机的专家系统来缓解核电站事故的可行性

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摘要

This study investigated the feasibility of developing a rule-based expert system to support nuclear plant operators in the mitigation of accidents. Human error in the use of Emergency Operating Procedures (EOPs) was the problem to be addressed. The goal was to determine if the Nuclear Plant Information System (NPIS) at one specific power plant would support development of an EOP operator aid to reduce the number of human errors.A review of the literature confirmed that human error is a recurring problem. This is particularly evident during high stress situations, such as accidents. A rule-based operator aid can reduce human performance errors. This made the research significant enough to justify its undertaking. Previous studies have developed rule-based operator aids for new plant design, but ignored nuclear plants constructed before the availability of computers.The data required for performance of each Emergency Operating Procedure step was identified. Individual step data requirements were compared to data presently available from the Nuclear Plant Information System. For needed data not directly available, alternative parameters were selected where possible. The alternative parameters provide the same plant information to the operator as that described in the Emergency Operating Procedure step. Parameters that cannot be monitored directly or by an alternative method are identified. This was documented in an EOP data matrix. Using the EOPs, a set of rules was developed for a 10, 000-gpm large break loss of coolant accident (LBLOCA). A plant specific simulator scenario for a LBLOCA was conducted. Data collection was performed during this scenario. A comparison of the collected data to the EOP rules determined all required information is not available. This was documented in an EOP rules matrix. A separate matrix compiled all parameters not directly on NPIS and without an acceptable alternative. The effect of each missing parameter on the mitigation strategy is documented.An EOP expert performed an independent verification of the rules matrix. This verifies correctness of the rules and the required data. A NPIS database expert performed an additional independent verification of unavailable NPIS data. This verified that the matrix data identified as unavailable from NPIS was correct. The study resulted in a set of recommendations for improving plant process computers, EOP procedures, and EOP development techniques. This approach may be used in other nuclear plants. Additional research avenues were identified.
机译:这项研究调查了开发基于规则的专家系统以支持核电站运营商缓解事故的可行性。使用紧急操作程序(EOP)的人为错误是要解决的问题。目的是确定一个特定电厂的核电站信息系统(NPIS)是否将支持开发EOP操作员辅助设备以减少人为错误的数量。文献回顾证实,人为错误是一个经常发生的问题。这在高压力情况下(例如事故)尤其明显。基于规则的操作员协助可以减少人为操作错误。这使得研究意义重大,足以证明其合理性。以前的研究已经为新工厂的设计开发了基于规则的操作员辅助设备,但忽略了在计算机可用之前建造的核电站。确定了每个“紧急操作程序”步骤的执行所需的数据。将各个步骤的数据要求与目前可从核电厂信息系统获得的数据进行了比较。对于无法直接获得所需数据的情况,尽可能选择其他参数。备用参数为操作员提供了与“紧急操作程序”步骤中所述的相同的工厂信息。确定无法直接监视或通过其他方法监视的参数。在EOP数据矩阵中对此进行了记录。使用EOP,制定了一套规则,以解决10,000 gpm的冷却液意外大断裂损失(LBLOCA)。进行了针对LBLOCA的工厂特定模拟器场景。在这种情况下执行了数据收集。将收集到的数据与EOP规则进行比较,确定所有必需信息均不可用。这已记录在EOP规则矩阵中。一个单独的矩阵不直接在NPIS上编译所有参数,也没有可接受的替代方法。记录每个缺失参数对缓解策略的影响。EOP专家对规则矩阵进行了独立验证。这验证了规则和所需数据的正确性。 NPIS数据库专家对不可用的NPIS数据进行了另外的独立验证。这证明了从NPIS不能识别的矩阵数据是正确的。该研究提出了一系列建议,用于改进工厂过程计算机,EOP程序和EOP开发技术。该方法可用于其他核电厂。确定了其他研究途径。

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    Smith Jesse E.;

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  • 年度 2000
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