This paper presents results from a series of integral tests performed at Framatome’s INKA test facility in Karlstein (Germany) which simulates a KERENA boiling water reactor (BWR). The scope of the test series was on the behaviour of and interaction between the different passive systems and components under the conditions of extended loss of alternating power (ELAP). These SBO-like conditions were aggravated in three out of four tests by parallel LOCA (Loss of Coolant Accident). The scenarios of all four tests fully correspond to Design Basic Conditions (DBC). They were: main steam line break, feed water line break, reactor pressure vessel (RPV) bottom leak and station blackout (SBO, non-LOCA).

In the tests, the passive systems integrated in KERENA and INKA, respectively, have fulfilled their design functions fully satisfactorily and as follows:

The Passive Pressure Pulse Transmitter (PPPT) triggered the RPV depressurization without delay. The Emergency Condenser (EC) system removed decay heat along with stored energy from the RPV to the containment. The Containment Cooling Condenser (CCC) system forwarded said power to a heat sink outside of the containment. The passive containment pressure suppression system kept the containment pressure within the design range, partially displacing surplus thermal energy from the drywell to the wetwell, in particular in the early phases after occurrence of LOCA. The passive core flooding system replenished the coolant inventory of the RPV thereby ensuring water levels in the RPV which are fully sufficient for core cooling.

Moreover, the systems have cooperated as anticipated by the designers, quietly and without perturbing each other.

Hence the test results, which are reported and discussed more in detail within this paper, soundly confirm the underlying design and its passive features.

Said tests were carried out as a part of the joint research project EASY (Evidence of Design Basis Accidents Mitigation solely with passive safety Systems), the overarching objective of which was the development and validation of the code system AC² of GRS (Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH).

本文介绍了在Framatome位于德国卡尔斯坦的INKA测试设施上进行的一系列整体测试的结果，该测试模拟了KERENA沸水反应堆（BWR）。测试系列的范围是在交流电扩展损耗（ELAP）的条件下，不同无源系统和组件的行为以及它们之间的相互作用。通过并行LOCA（冷却液事故损失），在四分之三的测试中使这些类似于SBO的条件恶化。所有这四个测试的方案都完全符合设计基本条件（DBC）。它们是：主蒸汽管线中断，给水管线中断，反应堆压力容器（RPV）底部泄漏和电站停电（SBO，非LOCA）。

在测试中，分别集成在KERENA和INKA中的无源系统已充分令人满意地履行了其设计功能，具体如下：

无源压力脉冲变送器（PPPT）立即触发了RPV降压。紧急冷凝器（EC）系统从RPV到安全壳去除了衰变热以及存储的能量。安全壳冷却冷凝器（CCC）系统将所述电源转发到安全壳外部的散热器。被动安全壳压力抑制系统将安全壳压力保持在设计范围内，部分将多余的热能从干井转移到湿井，特别是在LOCA发生后的早期阶段。被动堆芯注水系统补充了RPV的冷却剂存量，从而确保RPV中的水位足以用于堆芯冷却。

而且，这些系统已经按照设计人员的预期进行了协作，安静且互不干扰。

因此，在本文中进行了更详细的报道和讨论的测试结果，完全证实了基础设计及其被动特性。

说试验进行的联合研究项目EASY（的一部分Ë设计基础性证据，一个ccidents缓解单独与被动安全SY茎），其首要目标之一是代码系统的开发和验证AC ² GRS的（ GesellschaftfürAnlagen- and Reaktorsicherheit gGmbH）。