Development and validation of atmospheric dispersion: Computer program using tritium air concentrations in the environment around heavy water reactor power plants

1998 ◽  
Vol 25 (14) ◽  
pp. 1119-1132 ◽  
Author(s):  
B.H. Rho ◽  
K.J. Lee
Keyword(s):  
Computer Program ◽  
Heavy Water ◽  
Power Plants ◽  
Atmospheric Dispersion ◽  
Reactor Power ◽  
Water Reactor ◽  
Heavy Water Reactor ◽  
Development And Validation ◽  
Air Concentrations

Thermal Hydraulic Analysis Due to the Changes in Heat Removal for Advanced Heavy Water Reactor

2004 ◽  
Author(s):  
B. Chatterjee ◽  
A. Srivastava ◽  
D. Mukhopadhyay ◽  
P. Majumdar ◽  
H. G. Lele ◽  
...  
Keyword(s):  
Heavy Water ◽  
Natural Circulation ◽  
Heat Removal ◽  
Reactor Power ◽  
Circulation System ◽  
Feed Water ◽  
Set Point ◽  
Water Reactor ◽  
Heavy Water Reactor ◽  
Pressure Controller

Advanced Heavy Water Reactor is natural circulation light water cooled and heavy water moderated pressure tube type of reactor. Changes in heat removal by primary heat transport system of a reactor have significant impact on various important system parameters like pressures, qualities, reactor power and flows. Increase in heat removal leads to Cooldown of the system subsequently reducing pressure, void increase and changes in power and flows of the system. Decrease in heat removal leads to warm-up of the system subsequently raising pressure, void collapse, and changes in power and flows of the system. The behaviour is complex as system under consideration is natural circulation system. Causes for events under category of increase in heat removal are mainly malfunctioning of feed water heaters, Isolation Condensers (IC) inlet valves and controllers. These events lead to cooldown of system and addition of positive reactivity addition due to void collapse. Various events considered are Feed Water System malfunctions that result in decrease in feed water temperature, inadvertent opening of IC valve, Failure of PHT Pressure Control System and Decrease in pressure controller set point to 67 bars. Causes for events under category of decrease in heat removal are mainly malfunctioning of controllers, feedwater valves and operating events like turbine trip. Functioning of passive cooling system and different valves play important role for these events. These events lead to increase in system pressure. Various events considered are Loss of normal feed water flow (multiple trains), Turbine trip without bypass without IC, Turbine trip without bypass with IC, Turbine trip with bypass without IC, Increase in PHT pressure controller set point, Decrease in level controller set point, Turbine Trip with setback, Decrease in steam flow and Class IV power failure. Changes in the system voids and pressures as a result of change in the heat removal leads to complex reactivity feedback due to coolant temperatures, void fraction and fuel temperatures. These changes in the reactor power together with void distribution change affect two-phase natural circulation flow. This paper brings out these aspects. It discusses descretisation of the system and brings out various design aspects. In this paper summary of analysis for each event is presented, various modeling complexities are brought out, evaluation of acceptance criteria is made and design implications of each event is discussed.

TRANSIENT ANALYSIS OF INADVERTENT CLOSURE OF BLEED CONDENSER LEVEL CONTROL VALVES OF 700 MWE INDIAN PRESSURIZED HEAVY WATER REACTOR

2018 ◽  
Author(s):  
S. Phani Krishna ◽  
Santanu Pahari ◽  
S. Hajela ◽  
Mukesh Singhal
Keyword(s):  
Heavy Water ◽  
Transient Analysis ◽  
Level Control ◽  
Water Reactor ◽  
Control Valves ◽  
Heavy Water Reactor

Effect of Inlet Configuration on Moderator Velocity and Temperature Distribution Inside the Calandria of a Heavy Water Reactor

2008 ◽  
Author(s):  
Abhijeet Mohan Vaidya ◽  
Naresh Kumar Maheshwari ◽  
Pallippattu Krishnan Vijayan ◽  
Dilip Saha ◽  
Ratan Kumar Sinha
Keyword(s):  
Temperature Distribution ◽  
Impact Velocity ◽  
Heavy Water ◽  
Computational Study ◽  
Water Reactor ◽  
Heavy Water Reactor ◽  
The Impact

Computational study of the moderator flow in calandria vessel of a heavy water reactor is carried out for three different inlet nozzle configurations. For the computations, PHOENICS CFD code is used. The flow and temperature distribution for all the configurations are determined. The impact of moderator inlet jets on adjacent calandria tubes is studied. Based on these studies, it is found that the inlet nozzles can be designed in such a way that it can keep the impact velocity on calandria tubes within limit while keeping maximum moderator temperature well below its boiling limit.

scholarly journals Calculation of Potential Radiation Doses Associated with Predisposal Management of Dismantled Steam Generators from Nuclear Power Plants

2020 ◽  
Vol 12 (12) ◽  
pp. 5149
Author(s):  
Ga Hyun Chun ◽  
Jin-ho Park ◽  
Jae Hak Cheong
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Doses ◽  
Steam Generators ◽  
Pressurized Water ◽  
Water Reactor ◽  
General Pathway ◽  
Heavy Water Reactor ◽  
Past Experiences

Although the generation of large components from nuclear power plants is expected to gradually increase in the future, comprehensive studies on the radiological risks of the predisposal management of large components have been rarely reported in open literature. With a view to generalizing the assessment framework for the radiological risks of the processing and transport of a representative large component—a steam generator—12 scenarios were modeled in this study based on past experiences and practices. In addition, the general pathway dose factors normalized to the unit activity concentration of radionuclides for processing and transportation were derived. Using the general pathway dose factors, as derived using the approach established in this study, a specific assessment was conducted for steam generators from a pressurized water reactor (PWR) or a pressurized heavy water reactor (PHWR) in Korea. In order to demonstrate the applicability of the developed approach, radiation doses reported from actual experiences and studies are compared to the calculated values in this study. The applicability of special arrangement transportation of steam generators assumed in this study is evaluated in accordance with international guidance. The generalized approach to assessing the radiation doses can be used to support optimizing the predisposal management of large components in terms of radiological risk.

scholarly journals Conceptual design of a large heavy water reactor for US siting

1979 ◽  
Author(s):  
N L Shapiro ◽  
J F Jesick
Keyword(s):  
Conceptual Design ◽  
Heavy Water ◽  
Water Reactor ◽  
Heavy Water Reactor

Paper 10: Experience with Glandless Pumps on the Winfrith Steam Generating Heavy Water Reactor

1969 ◽  
Vol 184 (11) ◽  
pp. 98-107
Author(s):  
B. Negus ◽  
D. Smith
Keyword(s):  
Heavy Water ◽  
Corrosion Products ◽  
Significant Problem ◽  
Water Reactor ◽  
Heavy Water Reactor

This paper describes experience with glandless pumps on the S.G.H.W.R., both wet and dry stator types being included. The performance of the pumps is discussed and details given of the problems which arose in operations. Experience suggests that deposition in the pumps of radioactive corrosion products will not be a significant problem. The paper is in four parts: the functions, characteristics, and instrumentation of the pumps are outlined, followed by a description of some of the key results from commissioning tests.

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