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RESULTS OF THE QUENCH-09 EXPERIMENT COMPARED TO QUENCH-07 WITH INCORPORATION OF B_4C ABSORBER

机译:包含B_4C吸收剂的QUENCH-09实验结果与QUENCH-07相比

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The purpose of the QUENCH experimental program at the Karlsruhe Research Center is to investigate the hydrogen source term that results from quenching an uncovered core, to examine the physicochemical behavior of overheated fuel elements under different flooding/ cooling conditions, and to create a database for model development and code improvement. The QUENCH-07 and -09 test bundles consisted of 21 rods, 20 of which were electrically heated over a length of 1.024 m. The Zircaloy-4 rod cladding and the grid spacers were identical to those used in Western-type light water reactors (LWRs), whereas the fuel was represented by ZrO_2 pellets. In both experiments the central rod was made of an absorber rod with B4C pellets and stainless steel cladding and of a Zircaloy-4 guide tube. Failure of the absorber rod cladding was detected at the same temperature in both experiments, i.e., at ~1555 to 1585 K. After a B_4C oxidation phase at ~1720 to 1780 K and a subsequent transient test phase to well above 2000 K, cooling of the test bundle was accomplished by injecting saturated steam at the bottom of the test section. The presence of the B_4C absorber material in the central rod triggers the formation of eutectic melts, i.e., melts that are formed far below the melting point of metallic Zir-caloy (~2030 K), and the oxidation of boron/carbon/ zirconium-containing melt can lead to increased amounts of hydrogen and to production of CO, CO_2, and CH_4 compared to a bundle without a control rod. The total amount of hydrogen released during the flooding, i.e., cooling, phase was, however, significantly larger in QUENCH-09 (~0.400 kg) than in QUENCH-07 (~0.120 kg). It is conjectured that it is mainly the period of steam starvation prior to the cooling phase of QUENCH-09 (steam flow reduction from 3.3 to 0.4 g/s for a duration of ~11 min) that caused the enhanced zirconium oxidation in the cooling phase of QUENCH-09. This is the revised and updated version of the paper that was presented at the 2004 International Meeting on LWR Fuel Performance in Orlando, Florida, on September 19-22, 2004, under the title "Results of the QUENCH-09 Experiment Compared to QUENCH-07 (LWR-Type Test Bundles with B_4C Absorber)."
机译:卡尔斯鲁厄研究中心的QUENCH实验程序的目的是研究淬灭未发现的岩心所产生的氢源项,以检查在不同的驱油/冷却条件下过热燃料元件的理化行为,并建立模型数据库开发和代码改进。 QUENCH-07和-09测试束由21根棒组成,其中20根棒被电加热到1.024 m的长度。 Zircaloy-4棒熔覆层和栅格隔板与西方轻型水反应堆(LWR)中使用的相同,而燃料以ZrO_2颗粒表示。在这两个实验中,中心杆均由带有B4C球团和不锈钢包层的吸收杆和Zircaloy-4导管制成。在两个实验中,在相同的温度下(即〜1555至1585 K),都检测到了吸收杆熔覆失败。在B_4C氧化阶段在〜1720至1780 K以及随后的瞬态测试阶段(远高于2000 K)之后,冷却了通过在测试部分的底部注入饱和蒸汽来完成测试束。中心棒中B_4C吸收剂材料的存在触发了共晶熔体的形成,即形成的熔体远低于金属锆合金的熔点(约2030 K),并且硼/碳/锆-锌的氧化与没有控制棒的管束相比,含有熔体的熔体会导致氢气量增加,并产生CO,CO_2和CH_4。但是,在淹水阶段(即冷却阶段)释放的氢气总量在QUENCH-09(约0.400千克)中明显大于QUENCH-07(约0.120千克)。据推测,主要是由于QUENCH-09冷却阶段之前的蒸汽饥饿期(蒸汽流量从3.3 g / s降低到0.4 g / s,持续约11分钟)导致了冷却阶段中锆的增强氧化作用。 QUENCH-09。这是该论文的修订和更新版本,该论文于2004年9月19日至22日在佛罗里达州奥兰多举行的2004年轻水堆燃料性能国际会议上发表,标题为“ QUENCH-09实验结果与QUENCH- 07(带有B_4C吸收器的LWR型测试套件)。”

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