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PRELIMINARY RESULTS OF THE HFR-EU1 FUEL IRRADIATION OF INET AND AVR PEBBLES IN THE HFR PETTEN

机译:HFR PET中Inet和AVR小卵石的HFR-EU1燃料辐照的初步结果

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The irradiation experiment HFR-EU1 in the HFR Petten is currently being conducted by the European Commission's Joint Research Centre - Institute for Energy (JRC-IE). The irradiation targets are 5 spherical High Temperature Reactor (HTR) fuel pebbles, 2 of INET production and 3 of former German production. Both types are made of TRISO coated particles and are tested for their potential for very high temperature performance and high burn-up. The irradiation started on 29 September 2006 and, by 24 February 2008, had accumulated 12 reactor cycles totaling 332.8 efpd and a calculated maximum burn-up of 8.9% FIMA (INET) and 11.2%FIMA(AVR).The objective of the HFR-EU1 test is to irradiate 5 HTR fuel pebbles at conditions beyond the characteristics of current HTR reactor designs with pebble bed cores, e.g. HTR-Modul, HTR-10 and PMBR. This should demonstrate that pebble bed HTRs are capable of enhanced performance in terms of sustainability (further increased power conversion efficiency, improved fuel use) and thus reduced waste production. The surface temperature of all pebbles was held constant during the irradiation, with the exception of HFR downtime and power transients.HFR-EU1 should demonstrate the feasibility of low coated particle failure fractions under normal operating conditions and more specifically:1. high fuel surface temperature of 900°C (INET) and 950°C (AVR).2. very high burn-up of 17% FIMA (INET) and 20% FIMA (AVR) which is significantly higher than the license limit of the HTR-Modul (approx. 8% FIMA); it will be explained in this paper why this objective had to be somewhat reduced due to excessive irradiation time requirements and technological difficulties;This paper provides the irradiation history of the experiment performed so far including data on fission gas release.
机译:欧盟委员会联合研究中心-能源研究所(JRC-IE)目前正在HFR Petten中进行辐照实验HFR-EU1。辐照目标是5个球形高温反应堆(HTR)燃料卵石,其中2个是INET生产的,另外3个是以前德国生产的。两种类型均由TRISO涂层的颗粒制成,并经过测试其潜在的超高温性能和高燃耗性。辐照于2006年9月29日开始,到2008年2月24日,已累积了12个反应堆循环,总计332.8 efpd,计算出的最大燃耗为8.9%FIMA(INET)和11.2%FIMA(AVR)。 HFR-EU1测试的目的是在超出目前卵石床芯的HTR反应堆设计特征的条件下照射5个HTR燃料卵石。 HTR-Modul,HTR-10和PMBR。这应该证明卵石床HTR能够在可持续性方面提高性能(进一步提高功率转换效率,改善燃料使用),从而减少废物产生。除HFR停机时间和功率瞬变外,所有卵石的表面温度在辐照期间均保持恒定。 HFR-EU1应该证明在正常操作条件下低涂层颗粒失效分数的可行性,更具体地说: 1.燃料表面温度高达900°C(INET)和950°C(AVR)。 2. 17%FIMA(INET)和20%FIMA(AVR)的燃耗非常高,大大高于HTR-Modul的许可限制(约8%FIMA);在本文中将解释为什么由于过度的辐照时间要求和技术难题而不得不稍微降低这一目标; 本文提供了迄今为止进行的实验的辐照历史,包括裂变气体释放的数据。

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