Performance analyses of the pool-top radiation level reduction systems at the ETRR-2 research reactor

Kerntechnik ◽  
2006 ◽  
Vol 71 (3) ◽  
pp. 130-133
Author(s):  
A. M. Shokr
Keyword(s):  
Research Reactor ◽  
Radiation Level ◽  
Performance Analyses ◽  
Level Reduction

Hot-Water Layer, Heat-Loss Characteristics of an Open-Pool-Type Research Reactor for Reducing the Pool Top Radiation Level

2010 ◽  
Author(s):  
Young-Chul Park
Keyword(s):  
Heat Loss ◽  
Flow Condition ◽  
Research Reactor ◽  
Water Layer ◽  
Hot Water ◽  
Radiation Level ◽  
Downward Flow ◽  
Reactor Coolant ◽  
Reactor Pool ◽  
Pool Type

During an open-pool-type research reactor operation, it is necessary to access the pool top area for un/loading irradiation test pieces by a required irradiation period. However, when the reactor pool top radiation level exceeds the limit of radiation level by the rising of reactor chimney water contaminated by radioactivity due to a natural convection of the pool water, access the reactor pool top area is denied due to the high radiation level. In the case of HANARO, a hot-water layer (HWL, hereinafter) is maintained below a depth of 1.2 m from the top of the reactor pool in order to reduce the radiation level of the reactor pool top area. After a normal operation of the HWL, the pool top radiation level is safely maintained below the limit of the pool top radiation level. For studying more the characteristics of the HWL under a reactor coolant downward flow condition, The HWL heat loss is calculated based on the HANARO HWL calculation model. The HWL heat loss characteristics were reviewed by variations of the HWL temperature, reactor core coolant flow direction, and reactor power. It was confirmed through the results that the HWL heat loss under a reactor coolant downward flow condition was increased by about 20% to 60% over that under a reactor coolant upward flow condition, as per the HWL temperature variation. It was the reason that the HWL bottom convection heat loss was increased by the higher flow rate under a reactor coolant downward flow condition than that under a reactor coolant in an upward flow condition.

Design of a Discharge Header and a Working Platform for a Research Reactor With a CFD Model

2013 ◽  
Author(s):  
Kyoungwoo Seo ◽  
Hyungi Yoon ◽  
Dae-young Chi ◽  
Seonghoon Kim ◽  
Juhyeon Yoon
Keyword(s):  
Research Reactor ◽  
Cold Water ◽  
Cooling System ◽  
Reactor Core ◽  
Water Layer ◽  
Hot Water ◽  
Primary Coolant ◽  
Radiation Level ◽  
Reactor Pool ◽  
Pool Type

Most research reactors are designed as an open-pool type and the reactor is located on the bottom of the open-pool. The reactor in the pool is connected to the primary cooling system, which is designed for adequate cooling of the heat generated from the reactor core. One of the characteristics of an open-pool type research reactor is that the primary coolant after passing through the reactor core and the primary cooling system (PCS) is returned to the reactor pool. Because the primary coolant contains many kinds of radionuclides, the research reactor should be designed to protect the radionuclides from being released outside the pool by a stratified stable water layer, which is formed between a hot water layer and cold water near the reactor and prevents the natural circulation of water in the pool. In this study, additional components such as a discharge header and a working platform inside the pool were developed to help diminish the radiation level to the pool top. To discharge coolant stably inside the reactor pool, a discharge header was installed at the end of the pool inlet pipe. Many holes were made in the discharge header to discharge the coolant slowly and minimize the disturbance of the hot water layer by the flow inside the pool. The working platform was also equipped inside the reactor pool to remove the convective flow near the pool top. The commercially available CFD code, ANSYS CFD-FLEUNT, was used to specifically design the discharge header and working platform for satisfying the requirement of the pool top radiation level. The computations were conducted to analyze the flow and temperature characteristics inside the pool for several geometries using an SST k-ω turbulent model and cell modeling, which were conducted to isolate the root cause of these differences and the given inlet conditions. The discharge header and working platform were designed using the CFD results.

A Study of Exposure of Overall Background Radiation In Syangja District of Nepal

2017 ◽  
pp. 92-95
Author(s):  
T Timilsina ◽  
K. R. Poudel ◽  
P. R. Poudel
Keyword(s):  
High Altitude ◽  
Background Radiation ◽  
Significant Risk ◽  
Total Radiation ◽  
Radiation Level ◽  
The People ◽  
Public Exposure

This study presents general exposure of background radiation to the people living or visiting nine places of Syangja district. A portable GM counter was used to quantify the total radiation at those places. The findings of this study show variation of radiation level at different places. Comparatively large values of radiation counts are observed at high altitude places (Gurung Dada: 70.23 cpm and Pokhari Dada: 64.77 cpm). The value of radiation count inside room is comparatively larger than that at outside room for these places. Moreover, small value of radiation count is observed at river side (Bank of Aandhikhola river: 21.63 cpm). Little large values are observed near Saligram stones and ancient statue than at other regions of one historical/religious place. Hence, results show fluctuations of background radiation level for different places. Some places have comparatively large value of radiation count while some places have comparatively small value. But there is no any abnormal value of radiation counts for all sample places. So there is, generally, no significant risk of public exposure to the background radiation for sample places.The Himalayan Physics Vol. 6 & 7, April 2017 (92-95)

Inspection of domestic nuclear fuel rods using neutron radiography at the Tehran Research Reactor

2016 ◽  
Vol 58 (9) ◽  
pp. 763-766 ◽  
Author(s):  
Mohammad Hosein Choopan Dastjerdi ◽  
Hossein Khalafi ◽  
Yaser Kasesaz ◽  
Amir Movafeghi
Keyword(s):  
Nuclear Fuel ◽  
Research Reactor ◽  
Neutron Radiography ◽  
Fuel Rods ◽  
Tehran Research Reactor ◽  
Nuclear Fuel Rods

Prediction of the onset of flow instability in the ETRR-2 research reactor under loss of flow accident

Kerntechnik ◽  
2007 ◽  
Vol 72 (1-2) ◽  
pp. 53-58 ◽  
Author(s):  
H. A. Khater ◽  
S. El-Din El-Morshdy ◽  
M. M. A. Ibrahim
Keyword(s):  
Research Reactor ◽  
Flow Instability

Research reactor model for isotope production based on the design of VVER-440 reactors

Kerntechnik ◽  
2020 ◽  
Vol 85 (2) ◽  
pp. 105-108
Author(s):  
A. Terekhova ◽  
A. Mahdi ◽  
R. Zykova
Keyword(s):  
Research Reactor ◽  
Isotope Production ◽  
Reactor Model

Performance analyses of the communication networks of a modern supervision and control system of research reactors

Kerntechnik ◽  
2009 ◽  
Vol 74 (1-2) ◽  
pp. 42-46
Author(s):  
E. I. El-Madbouly ◽  
M. K. Shaat ◽  
A. M. Shokr ◽  
G. H. Elrefaei
Keyword(s):  
Control System ◽  
Communication Networks ◽  
Research Reactors ◽  
Performance Analyses ◽  
And Control
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