首页> 外文会议>Small modular reactors symposium 2011 >TRACE CODE ANALYSES FOR THE IAEA ICSP ON 'INTEGRAL PWR DESIGN NATURAL CIRCULATION FLOW STABILITY AND THERMO-HYDRAULIC COUPLING OF CONTAINMENT AND PRIMARY SYSTEM DURING ACCIDENTS'
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TRACE CODE ANALYSES FOR THE IAEA ICSP ON 'INTEGRAL PWR DESIGN NATURAL CIRCULATION FLOW STABILITY AND THERMO-HYDRAULIC COUPLING OF CONTAINMENT AND PRIMARY SYSTEM DURING ACCIDENTS'

机译:IAEA ICSP“事故发生时整体压水堆设计自然循环流稳定性以及围护和主系统的热工水力耦合”的跟踪代码分析

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摘要

Considering the world energy demand increase in order to fulfill an environmental and economic sustainability, the energy policy of each country has to diversify the sources of energy and use stable, safe energy production option able of producing electricity in a clean way contributing in cutting the CO_2 emission. In the framework of the sustainable development, today the use of advanced nuclear power plant, have an important role in the environmental and economic sustainability of country energy strategy. In the last 20 years, in fact, the international community, taking into account the operational experience of the nuclear reactors, starts the development of new advanced reactor designs considering also the use of natural circulation for the cooling of the core in normal and transient conditions. In this framework, Oregon State University (OSU) has constructed, under a U.S. Department of Energy grant, a system level test facility to examine natural circulation phenomena characterizing the Multi-Application Small Light Water Reactor (MASLWR) design, a small modular integral pressurized light water reactor relying on natural circulation during both steady state and transient operation. It includes an integrated helical coil steam generator as well. Starting from an experimental campaign in support of the MASLWR concept design verification, the planned work, will be not only to specifically investigate the concept design further but also advance the broad understanding of integral natural circulation reactor plants and accompanying passive safety features as well. An IAEA International Collaborative Standard Problem (ICSP) on "Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System During Accidents" is hosting at OSU and the experimental data will be developed at the OSU-MASLWR facility. The purpose of this IAEA ICSP is to provide experimental data on single/two-phase flow instability phenomena under natural circulation conditions and coupled containment/reactor vessel behavior in integral-type light water reactors. These data can be used to assess thermal hydraulic codes for reactor system design and analysis as well. The first planned test investigates a stepwise reduction in the primary mass inventory of the facility while operating at reduced power (decay power). The second planned test, investigates a loss of feed water transient with subsequent primary blowdown due to automatic depressurization system actuation and long term cooling phase. The target of this paper is to contribute to the thermal hydraulic analysis of the expected phenomena of these transients on the basis of the TRACE V5 Patch 01 calculated data developed during the double-blind phase of the ICSP.
机译:考虑到世界能源需求的增长,以实现环境和经济的可持续性,每个国家的能源政策都必须使能源来源多样化,并使用能够以清洁方式发电的稳定,安全的能源生产方式,从而有助于减少CO_2发射。在可持续发展的框架内,当今使用先进核电站在国家能源战略的环境和经济可持续性方面具有重要作用。实际上,在过去的20年中,国际社会考虑到核反应堆的运行经验,开始开发新的先进反应堆设计,同时考虑到在自然和瞬态条件下使用自然循环冷却堆芯。在此框架下,俄勒冈州立大学(OSU)在美国能源部的资助下,建立了系统级测试设施,以检查自然循环现象,该现象表征了多用途小型轻水反应堆(MASLWR)设计,小型模块化整体加压轻水反应堆在稳态和瞬态运行期间均依赖自然循环。它还包括一个集成的螺旋线圈蒸汽发生器。从支持MASLWR概念设计验证的实验活动开始,计划的工作将不仅是进一步专门研究概念设计,而且还将增进对整体自然循环反应堆设备以及伴随的被动安全功能的广泛理解。关于“事故发生时安全壳与主要系统的整体压水堆设计自然循环流稳定性和热工水力耦合”的国际原子能机构国际合作标准问题(ICSP)将在OSU举行,并将在OSU-MASLWR设施开发实验数据。 IAEA ICSP的目的是提供有关自然循环条件下单相/两相流动不稳定性现象以及整体式轻水反应堆中密闭/反应堆行为的实验数据。这些数据也可用于评估反应堆系统设计和分析的热工水力代码。计划中的第一个测试研究在降低功率(衰减功率)的同时逐步减少设施的主要质量清单。第二个计划中的测试调查了由于自动降压系统启动和长期冷却阶段而导致的随后的初次排污带来的给水瞬态损失。本文的目标是基于在ICSP双盲阶段开发的TRACE V5 Patch 01计算数据,对这些瞬态的预期现象进行热力水力分析。

著录项

  • 来源
    《Small modular reactors symposium 2011》|2011年|p.257-267|共11页
  • 会议地点 Washington DC(US);Washington DC(US)
  • 作者单位

    Dipartimento dell'Energia-Sezione Ingegneria Nucleare-, Universita degli Studi di Palermo Viale delle Scienze, Edificio 6, 90128 Palermo, Italy;

    Department of Nuclear Engineering and Radiation Health Physics, Oregon State University 116 Radiation Center, Corvallis, OR 97331-5902, USA;

    Dipartimento dell'Energia-Sezione Ingegneria Nucleare-, Universita degli Studi di Palermo Viale delle Scienze, Edificio 6, 90128 Palermo, Italy;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 核反应堆工程;
  • 关键词

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