Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities

2020 ◽  
Vol 7 (1) ◽  
Author(s):  
Angelina-Nataliya V. Vukolova ◽  
Andrei A. Rusinkevich
Keyword(s):  
Power Plants ◽  
Boiling Water ◽  
Normal Operation ◽  
Boiling Water Reactor ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Operation Conditions ◽  
Discharge Activity ◽  
Radionuclide Composition

Abstract The article presents the analysis of the data on radionuclide composition of airborne discharges of 52 European nuclear power plants (NPPs) with water–water energetic reactor facilities (WWER), pressurized water reactor facilities (PWR), and boiling water reactor facilities (BWR) under normal operation conditions. It contains lists of radionuclides, registered in discharges of researched NPPs, and gives estimation of contributions of radionuclides, forming the discharge, into total activity of discharge and into total effective dose, created by the discharge activity. It was determined that the maximal contribution into discharge activity of all researched NPPs make noble gases, tritium, and carbon-14, while the latter is the main dose-making radionuclide.

scholarly journals SOURCE TERM ASSESSMENT FOR 100 MWE PRESSURIZED WATER REACTOR

2020 ◽  
Vol 22 (2) ◽  
pp. 61
Author(s):  
Pande Made Udiyani ◽  
Muhammad Budi Setiawan
Keyword(s):  
Power Plants ◽  
Public Perception ◽  
Source Term ◽  
Fission Products ◽  
Operating Conditions ◽  
Normal Operation ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Starting Point

One of the barriers on the implementation of nuclear energy in Indonesia is public perception towards the safety of nuclear power plants (NPPs). Therefore, it is necessary to perform a study about the radiation impact of normal and abnormal operations of an NPP. In accordance to the program of Ministry of Research and Technology period 2020-2024, concerning the plan to build a small modular reactor (SMR)-type NPP, a radiation safety study has been performed for the 100 MWe Pressurized Water Reactor (PWR-100MWe). Source term release of radioactive substances into the environment from PWR-100MWe is a starting point in the study of the radiological consequences of reactor operation. Therefore, this paper will examine the PWR-100MWe source term under normal and abnormal operating conditions, according to the design and the design basis accident (DBA). The initial trigger of the DBA is Lost of Coolant Accident (LOCA) such as Small LOCA and Large LOCA.  Due to the limitations of available SMR data, the study of PWR-100MWe source term refers to the assumption of the release fraction of fission products per subsystem in a larger 1000MWe PWR. It is expected from this assumption that pessimistic source term will be obtained. The study begins with calculation of PWR-100MWe core inventory using ORIGEN2 code based on PWR-100MWe reactor parameters. Through the mechanistic source term model and PWR-1000MWe release parameters, source terms will be obtained for normal operation and abnormal conditions i.e. DBA. Normal source term is used to calculate the consequences of normal operation, which will be used for environmental monitoring and environmental safety analysis of the site. Whereas accident source term is the basis for calculating the radiological consequences of accidents used for SAR documents and nuclear preparedness.Keywords: SMR, PWR-100MWe, normal operation, source term, accident

Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions

2016 ◽  
Vol 2 (2) ◽  
Author(s):  
Rudi Van Nieuwenhove
Keyword(s):  
Feasibility Study ◽  
Supercritical Water ◽  
External Pressure ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Water Conditions ◽  
Different Types

Different types of instruments have been developed both for in-pile fuel and materials studies at the Halden Reactor Project. In recent years, several of the standard instruments have been upgraded to be able to tolerate much higher temperatures. In particular, several instruments are now able to operate up to 650°C and 25 MPa, thus in the range suitable for supercritical water (SCW) studies. In addition, a feasibility study for an in-pile SCW loop has been carried out that shows that such a loop can be realized in the Halden reactor, allowing for all the instrumentation possibilities that are presently carried out in pressurized water reactor (PWR) and boiling water reactor (BWR) conditions. Another, and cheaper, alternative is to perform corrosion experiments inside a small capsule in which SCW is maintained by means of gamma heating and external pressure lines. The conceptual designs of the SCW loop and SCW capsule will be highlighted.

Sign in / Sign up

Export Citation Format

Share Document