Analysis of natural circulation phenomena in VVER-1000

Mousavian, Seyed Khalil; D'Auria, Francesco Saverio; Salehi, Mahmoud A.

doi:10.1016/j.nucengdes.2003.11.012

Cited by 17 publications

(3 citation statements)

References 21 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Active and passive designs are adopted to withstand design basis accidents in terms of safety injection and residual heat removal, similar to VVER1000 (Mousavian et al, 2004). The safety systems are designed with the principle of enhanced diversity and redundancy, which is realized by N+3.…”

Section: Safetymentioning

confidence: 99%

Generation III pressurized water reactors and China’s nuclear power

Wang¹,

Ma²,

Fang³

2016

J. Zhejiang Univ. Sci. A

View full text Add to dashboard Cite

Abstract:The design philosophy, overall performance, safety, and economy of three typical generation III (GIII) pressurized water reactors, EPR, AES2006, and CAP1400, are analyzed comprehensively in this paper. Based on comparison with and the lessons learned from the Fukushima nuclear accident, we forecast a future reactor for China's commercial nuclear power plant. Moreover, we put forward important technological fields of GIII nuclear power plants to which attention should be paid, including the enhancement of defense in depth, defense against extreme external events, severe accident mitigation, design simplification and standardization, improvement in economic competitiveness, load following capability, and adaptation to climate change.

show abstract

Section: Safetymentioning

confidence: 99%

Generation III pressurized water reactors and China’s nuclear power

Wang¹,

Ma²,

Fang³

2016

J. Zhejiang Univ. Sci. A

View full text Add to dashboard Cite

show abstract

“…Advanced nuclear power plants are equipped with passive systems for emergency decay heat removal from reactor equipment (PEHRSs) to the final heat absorber (ambient air) in case of development of accidents accompanied with primary cooling circuit leakage and for transferring heat to the final heat absorber (ambient air) (Mousavian et al 2004;Maio Vitale et al 2012;Zhang et al 2012;Dmitriev et al 2013). For nuclear power plants designed in Russia, passive safety systems were firstly used in the AES-92 Project followed by all subsequent design projects (AES-2006, VVER-1200.…”

Section: Introductionmentioning

confidence: 99%

Heat transfer intensification in emergency cooling heat exchanger and dry cooling towers on nuclear power plant using air-water mist flow

Abed¹,

Щеклеин²,

Pakhaluev³

2019

NUCET

View full text Add to dashboard Cite

Advanced nuclear power plants are equipped with passive emergency heat removal systems (PEHRS) for removing the decay heat from reactor equipment in accidents accompanied by primary circuit leakage to the final heat absorber (ambient air). Herein, the intensity of heat dissipation to air from the outer surface of the heat exchanger achieved by buoyancy induced natural convection is extremely low, which need to a large heat exchanger surface area, apply different types of heat transfer intensification including (grooves, ribs and extended surfaces, positioning at higher altitudes, etc.). The intensity of heat removal is also strongly dependent on the ambient air temperature (disposable temperature head). Construction of nuclear power plants in countries with high ambient temperatures (Iran, Bangladesh, Egypt, Saudi Arabia, and others) which are characterized by a high level of ambient temperature imposes additional requirements on the increase of the heat exchange surfaces. The experimental investigation results of heat transfer intensification by a low energy ultrasonic which supply a fine liquid droplet (size ~3 µm) in the cooling air are presented in the present paper. In such case, the heat transfer between the surface and cooling flow involves the following three physical effects: convection, conductive heat transfer, and evaporation of water droplets. The last two effects weakly depend on the ambient air temperature and provide an active heat removal in any situation. The investigation was performed using a high-precision calorimeter with a controlled rate of heat supply (between 7800 and 12831 W/m2) imitating heated surface within the range of Reynolds numbers from 2500 to 55000 and liquid (water) flow rates from 23.39 to 111.68 kg·m-2·h-1. The studies demonstrated that the presence of finely dispersed water results in a significant increase in heat transfer compared with the case of using purely air-cooling. With a fixed heat flux, the energy efficiency increases with increasing water concentration, reaching the values over 600 W·m-2·C-1 at 111.68 kg·m-2·h-1, which is 2.8 times higher than for air cooling. With further development of research in order to clarify the optimal areas of intensification, it is possible to use this technology to intensify heat transfer to the air in dry cooling towers of nuclear power plants and thermal power plants used in hot and extreme continental climates.

show abstract

“…The PRHRSs via the secondary side of the steam generators for WWER-1000/V-392 and WWER-640/V-407 plants (Hyvärinen [4]; IAEA-TECDOC-1391, [5]; Krepper [6]; Mousavian et al [7]) are intended to remove decay heat from the reactor in a case of a station blackout with intact primary and secondary circuits, and to depressurize the RCS under a small break LOCA. The PRHRS of V-392 consists of four independent trains, each of which has pipelines for steam supply and removal of condensate, valves, and an aircooled heat exchanger installed outside the containment.…”

Section: Introductionmentioning

confidence: 99%

Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor

Gou

Qiu

et al. 2009

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary side of the steam generator, for an integral pressurized water reactor is presented in this paper. Three-interknited natural circulation loops are adopted by this PRHRS to remove the residual heat of the reactor core after a reactor trip. Based on the one-dimensional model and a simulation code (SCPRHRS), the transient behaviors of the PRHRS as well as the effects of the height difference between the steam generator and the heat exchanger and the heat transfer area of the heat exchanger are studied in detail. Through the calculation analysis, it is found that the calculated parameter variation trends are reasonable. The higher height difference between the steam generator and the residual heat exchanger and the larger heat transfer area of the residual heat exchanger are favorable to the passive residual heat removal system.

show abstract

Analysis of natural circulation phenomena in VVER-1000

Cited by 17 publications

References 21 publications

Generation III pressurized water reactors and China’s nuclear power

Generation III pressurized water reactors and China’s nuclear power

Heat transfer intensification in emergency cooling heat exchanger and dry cooling towers on nuclear power plant using air-water mist flow

Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor

Contact Info

Product

Resources

About