Environmental Radiation Monitoring System Development for Atmospheric Plumes from Light Water Reactor Nuclear Power Plants

1982 ◽  
Vol 56 (3) ◽  
pp. 580-590 ◽  
Author(s):  
Tachimori Ohba ◽  
Satsuharu Takimoto ◽  
Yoshio Kitada ◽  
Tomio Tsunoda ◽  
Akira Kobayashi ◽  
...  
1978 ◽  
Vol 45 (1) ◽  
pp. 1-51 ◽  
Author(s):  
R. Bardtenschlager ◽  
D. Bottger ◽  
A. Gasch ◽  
N. Majohr

2021 ◽  
Vol 23 (3) ◽  
pp. 91
Author(s):  
Jupiter Sitorus Pane ◽  
Pande Made Udiyani ◽  
Muhammad Budi Setiawan ◽  
Surip Widodo ◽  
I Putu Susila

Environmental radiation monitoring is one of the important efforts in protecting society and the environment from radiation hazards, both natural and artificial. The presence of three nuclear research reactors and plans to build a nuclear power plant reactor prompted Indonesia to prepare a radiation monitoring system for safety and security (SPRKK). The goal of the study is to provide an appropriate method for developing radiation monitoring system to support the development of nuclear power plant in the near future.  For this preliminary study, the author developed a code program using Gaussian distribution model approach for predicting radionuclide release and individual dose acceptancy by human being within 16 wind directions sectors and up to 50 km distance. The model includes estimation of source term from the nuclear installation, release of radionuclides source into air following Gaussian diffusion model, some of the release deposit to the land and entering human being through inhalation, direct external exposure, and resuspension, and predicted its accepted individual dose. This model has been widely used in various code program such as SimPact and PC-Cosyma. For this study, the model will be validated using SimPact code program. The model has been successfully developed with less than 5% deviation.   Further study will be done by evaluating the model with real measuring data from research reactor installation and prepare for interfacing with real time radiation data acquisition and monitoring as part of radiation monitoring system during normal and accident condition.


Author(s):  
Jason Carneal

The American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) establishes the requirements for preservice and inservice testing and examination of certain components to assess their operational readiness in light-water reactor nuclear power plants. The Code of Federal Regulations (CFR) endorses and mandates the use of the ASME OM Code for testing air-operated valves in 10 CFR 50.55a(b)(3)(ii) and 10 CFR 50.55a(f)(4), respectively. ASME has recently approved Mandatory Appendix IV, Revision 0. NRC currently anticipates that Mandatory Appendix IV will first appear in the 2014 Edition of the ASME OM Code. Publication of the 2014 Edition of the ASME OM Code begins the NRC rulemaking process to modify 10 CFR 50.55a to incorporate the 2014 Edition of the ASME OM Code by reference. NRC staff has actively participated in the development of Mandatory Appendix IV, Revision 0, through participation in the ASME OM Code Subgroup on Air-Operated Valves (SG-AOV). The purpose of this paper is to provide NRC staff perspectives on the contents and implementation of Mandatory Appendix IV, Revision 0. This paper specifically discusses Mandatory Appendix IV, Sections IV-3100, “Design Review,” IV-3300, “Preservice Test,” IV-3400, “Inservice Test,” IV-3600, “Grouping of AOVs for Inservice Diagnostic Testing,” and IV-3800, “Risk Informed AOV Inservice Testing.” These topics were selected based on input received during NRC staff participation in the SG-AOV and other industry meetings. The goal of this paper is to provide NRC staff perspectives on the topics of most interest to NRC staff and members of the SG-AOV. Paper published with permission.


Author(s):  
Fred Setzer

This paper presents a discussion of the activities ongoing within the ASME (formerly the American Society of Mechanical Engineers) Operation and Maintenance of Nuclear Power Plants (OM) Code Subgroup on Air Operated Valves (SG-AOV), along with an overview of Revision 0 of Mandatory Appendix IV, “Preservice and Inservice Testing of Active Pneumatically Operated Valve Assemblies in Light-Water Reactor Power Plants.” Paper published with permission.


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