Analysis on blow-down transient in water ingress accident of high temperature gas-cooled reactor

Wang, Yan; Zheng, Yongjun; Fu, Li; Shi, Lei

doi:10.1016/j.nucengdes.2013.12.009

Cited by 18 publications

(5 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…When a HTGR runs under normal operation, the impurities are introduced due to graphite degasification and small leakage of H 2 O from the secondary side to the primary side through the heat-exchanger tubes of steam generator 5 , which inevitably corrodes the graphite components at temperature higher than 400 °C 6 . In addition, the oxidation/corrosion of the graphite will be accelerated during an air or water ingress accident 7 , 8 . It has been found that the mechanical and thermal properties of graphite will be deteriorated by its oxidation/corrosion, shortening the lifetime of the graphite components 9 – 11 .…”

Section: Introductionmentioning

confidence: 99%

Characterizing thermal-oxidation behaviors of nuclear graphite by combining O2 supply and micro surface area of graphite

Zhou

Dong

Hua-qiang

et al. 2018

Sci Rep

Self Cite

View full text Add to dashboard Cite

The effects of different parameters on oxidation rate are non-linear, interactive and diversified in which the change of adequacy of O2 supply is an important indicator. The influence of microstructure on oxidation rate became stronger worsening the fitting linearity to calculate the activation energy based on present method with the decreased adequacy of O2 supply due to the increase of temperature, the decrease of gas flow rate, etc. Here, we proposed a method to characterize thermal-oxidation behaviors of nuclear graphite by combining O2 supply and micro surface area of graphite. The proposed method improved the linearity and reduced the standard error of Arrhenius plots of oxidized graphite IG-110 (10 L/min reactant gas) and ET-10 (0.2 L/min reactant gas). The value of activation energy of graphite IG-110 oxidized under ASTM D7542 condition is calculated as 220 kJ/mol by this method echoing the results of previous studies with sufficient O2 supply. For the conditions with less O2 supply at low gas flow rate and/or high temperature, the change of microstructure of oxidized graphite should be obtained as an important factor influencing oxidation rate of graphite.

show abstract

Section: Introductionmentioning

confidence: 99%

Characterizing thermal-oxidation behaviors of nuclear graphite by combining O2 supply and micro surface area of graphite

Zhou

Dong

Hua-qiang

et al. 2018

Sci Rep

Self Cite

View full text Add to dashboard Cite

show abstract

“…Siemens interatom 85,86 studied the water ingress into the core of reactor through one tube double‐ended in the steam generator, they found out that this action produces 600 kg water ingress into the primary circuit in the VHTR module, 82 found out that the total water inventory in the primary circuit can be limited with 3000 kg for all possible break size in module high‐temperature gas reactor. There are several studies 82,87‐90 investigated the water‐steam ingress for HTGR.…”

Section: Accident Analysismentioning

confidence: 99%

A review and safety aspects of modularhigh‐temperature gas‐cooledreactors

2020

View full text Add to dashboard Cite

Summary Modular high‐temperature gas‐cooled reactor (MHTGR) is being developed under the Next Generation Nuclear Plant Program in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, MHTGR seems to be a promising solution, particularly the possibility of producing hydrogen. Studying and developing safety analyses are required for the optimum design and safety of the MHTGR systems. The focus of several researchers, in previous years, has been directed in conducting investigations on natural convection heat transfer and flow dynamics in diverse geometries and operating conditions of MHTGR. The implementation of natural convection in nuclear reactors comes in the form of an engineered feature in accomplishing passive safety. In this review article, a comprehensive literature review has been introduced about the current status of the MHTGR. As part of an effort to understand the current status of the MHTGR safety analysis technology, this article introduced the MHTGR phenomena identification and event categorization and acceptance criteria.

show abstract

“…The additional components used for the accident conditions are: commissioning filter, post-accident cooler, postaccident water separator, and post-accident blower as seen in Figure 2. The technical specification of each train of HPS is shown in Table 2 [14,15]. HPS has main components i.e.…”

Section: Helium Purification Systemmentioning

confidence: 99%

Analysis of helium purification system capability during water ingress accident in RDE

Sriyono¹,

Kusmastuti²,

Bakhri³

et al. 2018

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

Abstract. The water ingress accident caused by steam generator tube rupture (SGTR) in RDE (Experimental Power Reactor) must be anticipated. During the accident, steam from secondary system diffused and mixed with helium gas in the primary coolant. To avoid graphite corrosion in the core, steam will be removed by Helium purification system (HPS). There are two trains in HPS, first train for normal operation and the second for the regeneration and accident. The second train is responsible to clean the coolant during accident condition. The second train is equipped with additional component, i.e. water cooler, post accident blower, and water separator to remove this mixture gas. During water ingress, the water release from rupture tube is mixed with helium gas. The water cooler acts as a steam condenser, where the steam will be separated by water separator from the helium gas. This paper analyses capability of HPS during water ingress accident. The goal of the research is to determine the time consumed by HPS to remove the total amount of water ingress. The method used is modelling and simulation of the HPS by using ChemCAD software. The BDBA and DBA scenarios will be simulated. In BDBA scenario, up to 110 kg of water is assumed to infiltrate to primary coolant while DBA is up to 35 kg. By using ChemCAD simulation, the second train will purify steam ingress maximum in 0.5 hours. The HPS of RDE has a capability to anticipate the water ingress accident.

show abstract

Analysis on blow-down transient in water ingress accident of high temperature gas-cooled reactor

Cited by 18 publications

References 3 publications

Characterizing thermal-oxidation behaviors of nuclear graphite by combining O2 supply and micro surface area of graphite

Characterizing thermal-oxidation behaviors of nuclear graphite by combining O2 supply and micro surface area of graphite

A review and safety aspects of modularhigh‐temperature gas‐cooledreactors

Analysis of helium purification system capability during water ingress accident in RDE

Contact Info

Product

Resources

About