Simulation of the occupational radiation dose caused by contamination of primary circuit media in pressurized water reactors

Kerntechnik ◽  
2016 ◽  
Vol 81 (5) ◽  
pp. 553-558
Author(s):  
A. Artmann ◽  
G. Bruhn ◽  
S. Schneider ◽  
E. Strub
Keyword(s):  
Radiation Dose ◽  
Pressurized Water Reactors ◽  
Primary Circuit ◽  
Pressurized Water ◽  
Water Reactors ◽  
Occupational Radiation

Use of Percentile Rank Sum Method in Identifying Repetitive High Occupational Radiation Dose Jobs in a Nuclear Power Plant

2004 ◽  
Author(s):  
Young Ho Cho ◽  
Hyun-Seok Ko ◽  
Suk-Hoon Kim ◽  
Chang Sun Kang ◽  
Joo Hyun Moon ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radiation Dose ◽  
Nuclear Power ◽  
Cost Effective ◽  
Pressurized Water ◽  
Percentile Rank ◽  
Water Reactors ◽  
The Cost ◽  
Occupational Radiation

The cost-effective reduction of occupational radiation dose (ORD) at a nuclear power plant could not be achieved without going through an extensive analysis of accumulated ORD data of existing plants. Through the data analysis, it is required to identify what are the jobs of repetitive high ORD at the nuclear power plant. In this study, Percentile Rank Sum Method (PRSM) is proposed to identify repetitive high ORD jobs, which is based on non-parametric statistical theory. As a case study, the method is applied to ORD data of maintenance and repair jobs at Kori units 3 and 4 that are pressurized water reactors with 950 MWe capacity and have been operated since 1986 and 1987, respectively in Korea. The results was verified and validated, and PRSM has been demonstrated to be an efficient method of analyzing the data.

A Possible Hazard from Nuclear Submarine Corrosion Products

1970 ◽  
Vol 56 (1) ◽  
pp. 183-185
Author(s):  
M. Hatfield
Keyword(s):  
Radiation Dose ◽  
Corrosion Product ◽  
Quantitative Information ◽  
Corrosion Products ◽  
Pressurized Water Reactors ◽  
Nuclear Submarine ◽  
Pressurized Water ◽  
Water Reactors ◽  
No Absorption

AbstractThere is a lack of quantitative information on the fate of radioactive corrosion products from pressurized water reactors. An experiment with rats is reported which shows that there is virtually no absorption of corrosion product cobalt from the gut. The implications in assessing radiation dose following an accidental intake of corrosion products are discussed.

scholarly journals Multiscale Filtering of Compressible Wave Propagation in Complex Geometry through a Wavelet-Based Approach in the Framework of Pressurized Water Reactors Depressurization Transient Analysis

Fluids ◽  
2020 ◽  
Vol 5 (2) ◽  
pp. 64
Author(s):  
Samy Mokhtari ◽  
Guillaume Ricciardi ◽  
Vincent Faucher ◽  
Pierre Argoul ◽  
Lucas Adélaide
Keyword(s):  
Wave Propagation ◽  
Pressure Field ◽  
Complex Geometry ◽  
Primary Objective ◽  
Pressurized Water Reactors ◽  
Primary Circuit ◽  
Rod Bundles ◽  
Pressurized Water ◽  
Filtering Technique ◽  
Water Reactors

The proposed research takes place in the framework of the analysis of the mechanical consequences of accidental scenarios for pressurized water reactors (PWR). It is particularly dedicated to the effects of the propagation of a transverse rarefaction wave through the assemblies of the nuclear core, consecutive to a pipe break in the primary circuit of the reactor. This paper focuses on the representation, with a reduced number of well-chosen variables, of a pressure wave propagating through a highly congested medium composed of rod bundles, with the primary objective of accurately evaluating the resulting pressure forces exerted on the rods. To achieve this goal, a description of the fluid domain as a homogenized or porous medium is introduced, yielding the need for a new filtering technique to be applied to the fluid fields. A new homogenized and multiscale representation of the fluid variables, based on continuous wavelet transform (CWT), is thus proposed. The capabilities of CWT to accurately approximate a reference representative unsteady pressure field, corresponding to a wave propagation at microscale, is assessed. The proposed technique is applied to a pressure field obtained numerically at local scale. The number of variables that shall be kept at macroscale to have a meaningful representation of the pressure field is fully evaluated through the comparison of the fluid force applied to the microstructure.

INCONEL FILLER METAL 52

Alloy Digest ◽  
1992 ◽  
Vol 41 (9) ◽  
Keyword(s):  
Corrosion Resistance ◽  
Arc Welding ◽  
Filler Metal ◽  
Pressurized Water Reactors ◽  
Pressurized Water ◽  
High Chromium ◽  
Inconel Alloy ◽  
Gas Tungsten Arc ◽  
Alloy 690 ◽  
Water Reactors

Abstract INCONEL FILLER METAL 52 is a high chromium filler metal for gas-metal-arc and gas-tungsten-arc welding of Inconel Alloy 690 (See Alloy Digest Ni-266, March 1981). Higher chromium is beneficial in resisting stress-corrosion cracking in high purity water for pressurized water reactors and for resistance to oxidizing acids. This datasheet provides information on composition and tensile properties. It also includes information on corrosion resistance as well as joining. Filing Code: Ni-412. Producer or source: Inco Alloys International Inc..

JESSOP-SAVILLE ZIRCONIUM ALLOY

Alloy Digest ◽  
1965 ◽  
Vol 14 (3) ◽  
Keyword(s):  
Corrosion Resistance ◽  
Zirconium Alloy ◽  
Heat Treating ◽  
Pressurized Water Reactors ◽  
Neutron Absorption ◽  
High Melting Point ◽  
Absorption Properties ◽  
Pressurized Water ◽  
Excellent Corrosion Resistance ◽  
Water Reactors

Abstract JESSOP-SAVILLE ZIRCONIUM Alloy has a high melting point and possesses excellent corrosion resistance coupled with low neutron absorption properties. It is equivalent to ZIRCALOY 2. It is recommended for pressurized water reactors. This datasheet provides information on composition, physical properties, elasticity, and tensile properties as well as creep. It also includes information on corrosion resistance as well as forming, heat treating, machining, joining, and surface treatment. Filing Code: Zr-2. Producer or source: Jessop-Saville Ltd, Brightside Works.

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