Determination of Failure Criteria for Electric Cables Exposed to Fire for Use in a Nuclear Power Plant Risk Analysis

2007 ◽  
Vol 4 (5) ◽  
pp. 100469
Author(s):  
Jill E. Norcott ◽  
Thomas K. Blanchat ◽  
M. Hirschler ◽  
S. W. Dean
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Risk Analysis ◽  
Nuclear Power ◽  
Failure Criteria ◽  
Electric Cables

The Determination of Shock Accelerations on a Small Nuclear Power Plant Structural Elements When Falling to the Surface

2020 ◽  
Vol 34 (1) ◽  
pp. 7-15
Author(s):  
O.A. Gubeladze ◽  
A.R. Gubeladze
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Structural Elements

Experimental determination of damping in nuclear power plant structures and equipment

1973 ◽  
Vol 25 (1) ◽  
pp. 112-125 ◽  
Author(s):  
G.C. Hart ◽  
P. Ibáñez
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Experimental Determination ◽  
Nuclear Power

scholarly journals Nuclear power plant safety assurance and justification of NPP operational acceptability throughout determination of maintenance parameter instituting

2019 ◽  
Vol 2019 (4) ◽  
pp. 83-94
Author(s):  
Aleksandr Vladimirovich Antonov ◽  
Gennady Alekseevich Ershov ◽  
Olga Ivanovna Morozova
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Assurance ◽  
Plant Safety ◽  
Nuclear Power Plant Safety

Improved method for the determination of manganese in nuclear power plant waters

1993 ◽  
Vol 640 (1-2) ◽  
pp. 371-378 ◽  
Author(s):  
Archava Siriraks ◽  
John Stillian ◽  
Dennis Bostic
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Improved Method

Determination of Frequency Characteristics of a Power System in the Course of Commissioning Operations Performed on the Excitation System of the TG5 Turbogenerator of the Beloyarskaya Nuclear Power Plant

2020 ◽  
Vol 53 (6) ◽  
pp. 765-771
Author(s):  
A. L. Komkov ◽  
A. A. Vishnyakov ◽  
N. Yu. Filimonov ◽  
A. A. Yurganov ◽  
I. M. Bikbaev ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Power System ◽  
Nuclear Power ◽  
Frequency Characteristics ◽  
Excitation System

Radioanalytical procedures for the separation and determination of alpha, beta and X emitters in environmental samples of a nuclear power plant before decommissioning

1993 ◽  
Vol 130-131 ◽  
pp. 403-417 ◽  
Author(s):  
Corrado Testa ◽  
Donatella Desideri ◽  
Maria Assunta Meli ◽  
Carla Roselli ◽  
Giulio Queirazza ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Environmental Samples ◽  
Nuclear Power ◽  
Alpha Beta ◽  
Radioanalytical Procedures

Determination of the source rate released into the environment from a nuclear power plant

2005 ◽  
Vol 113 (3) ◽  
pp. 308-313 ◽  
Author(s):  
Hyo-Joon Jeong ◽  
Eun-Han Kim ◽  
Kyung-Suk Suh ◽  
Won-Tae Hwang ◽  
Moon-Hee Han ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Source Rate

scholarly journals Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels

2016 ◽  
Vol 2016 ◽  
pp. 1-4 ◽  
Author(s):  
Mahdi Rezaeian ◽  
Jamshid Kamali
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Initial Step ◽  
Total Activity ◽  
Radioactive Source ◽  
Pressurized Water Reactor ◽  
Spent Fuel ◽  
Pressurized Water

Due to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with spent nuclear fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specification is the initial step for any radiation protection design. In this study, radioactive source specification of the spent fuels of Bushehr nuclear power plant, which is a VVER-1000 type pressurized water reactor, was determined. For the depletion and decay calculations, ORIGEN code was utilized. The results are presented for burnups of 30 to 49 GWd/MTHM and different cooling times up to 100 years. According to these results, total activity of a spent fuel assembly with initial enrichment of 3.92%, burnup of 49 GWd/MTHM, and cooling time of 3 years is 1.92 × 1016 Bq. The results can be utilized specifically in transportation/storage cask design for spent fuel management of Bushehr nuclear power plant.

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