Study on Minimum Wall Thickness Requirement of Reactor Vessel of Fast Reactor for Seismic Buckling by System Based Code

Volume 1B: Codes and Standards ◽

10.1115/pvp2013-97858 ◽

2013 ◽

Author(s):

Shigeru Takaya ◽

Daigo Watanabe ◽

Shinobu Yokoi ◽

Yoshio Kamishima ◽

Kenichi Kurisaka ◽

...

Keyword(s):

Wall Thickness ◽

Fast Reactor ◽

Design Method ◽

Random Variable ◽

Mean Value ◽

Reactor Vessel ◽

Seismic Load ◽

Reliability Design ◽

Plant Safety ◽

Distribution Type

In this paper, minimum wall thickness requirement of reactor vessel of fast reactor for seismic buckling is discussed on the basis of the System Based Code (SBC) concept. One of key concepts of SBC is the margin optimization. To implement this concept, reliability design method is employed, and the target reliability for seismic buckling of reactor vessel is derived from nuclear plant safety goals. Input data for reliability evaluation such as distribution type, mean value and standard deviation of random variable are prepared. Seismic hazard is considered to evaluate uncertainty of seismic load. Wall thickness needed to achieve the target reliability is evaluated, and as a result, it is shown that the minimum wall thickness can be reduced from that required by a deterministic design method.

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Study on Minimum Wall Thickness Requirement for Seismic Buckling of Reactor Vessel Based on System Based Code Concept

Journal of Pressure Vessel Technology ◽

10.1115/1.4029322 ◽

2015 ◽

Vol 137 (5) ◽

Cited By ~ 2

Author(s):

Shigeru Takaya ◽

Daigo Watanabe ◽

Shinobu Yokoi ◽

Yoshio Kamishima ◽

Kenichi Kurisaka ◽

...

Keyword(s):

Wall Thickness ◽

Design Method ◽

Random Variable ◽

Mean Value ◽

Reactor Vessel ◽

Seismic Load ◽

Reliability Design ◽

Plant Safety ◽

Key Features ◽

Distribution Type

The minimum wall thickness required to prevent seismic buckling of a reactor vessel (RV) in a fast reactor is derived using the system based code (SBC) concept. One of the key features of SBC concept is margin optimization; to implement this concept, the reliability design method is employed, and the target reliability for seismic buckling of the RV is derived from nuclear plant safety goals. Input data for reliability evaluation, such as distribution type, mean value, and standard deviation of random variables, are also prepared. Seismic hazard is considered to evaluate uncertainty of seismic load. Minimum wall thickness required to achieve the target reliability is evaluated, and is found to be less than that determined from a conventional deterministic design method. Furthermore, the influence of each random variable on the evaluation is investigated, and it is found that the seismic load has a significant impact.

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The Application of Hasofer-Lind Method in Reliability Design of Thin-Walled Cylindrical Shell

Applied Mechanics and Materials ◽

10.4028/www.scientific.net/amm.249-250.303 ◽

2012 ◽

Vol 249-250 ◽

pp. 303-306

Author(s):

Yu Long Zheng ◽

Zhi Min Lu ◽

Lin Lin Wang ◽

Lin Zhang ◽

Guang Liang Zhou

Keyword(s):

Cylindrical Shell ◽

Internal Pressure ◽

Wall Thickness ◽

Design Method ◽

Performance Function ◽

Reliability Design ◽

Second Moment ◽

The Difference ◽

Second Moment Method ◽

The Second Moment Method

Hasofer-Lind method was applied to reliability design of cylindrical shell with internal pressure. The respective reliability design thickness of different diameter ratio was obtained in the case and compared with the thickness by the second moment reliability design method. The results showed that the wall thickness of cylindrical shell with internal pressure is the thinnest by using Hasofer-Lind method. And it is closest to the wall thickness of the second moment method in which the performance function was defined as the difference in actual wall thickness and the wall thickness needed for cylindrical shell with internal pressure.

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Development of Limit State Design for Fast Reactor by System Based Code

Volume 1B: Codes and Standards ◽

10.1115/pvp2013-97154 ◽

2013 ◽

Author(s):

Daigo Watanabe ◽

Yasuharu Chuman ◽

Tai Asayama ◽

Shigeru Takaya ◽

Hideo Machida ◽

...

Keyword(s):

Fast Reactor ◽

Thermal Load ◽

Design Method ◽

Limit State ◽

Reactor Vessel ◽

Design Criteria ◽

Plant Design ◽

Allowable Stress ◽

Limit State Design ◽

Current Design

Limit state design was newly developed in order to apply the margin exchange which is one of the innovative concepts of the System Based Code (SBC). It was shown that limit state design method is applicable to plant design instead of current design criteria. In this report, working example of a reactor vessel of a Fast Reactor subject to thermal load is conducted to demonstrate this concept. As the result allowable stress was increased by changing the acceptance criteria from current design criteria to limit state design criteria.

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Temperature Dependence of Thermophysical Properties of Full-Scale Corium of Fast Energy Reactor

Science and Technology of Nuclear Installations ◽

10.1155/2017/8294653 ◽

2017 ◽

Vol 2017 ◽

pp. 1-7

Author(s):

Mazhyn K. Skakov ◽

Nurzhan Ye. Mukhamedov ◽

Alexander D. Vurim ◽

Ilya I. Deryavko

Keyword(s):

Heat Capacity ◽

Thermal Diffusivity ◽

Fast Reactor ◽

Thermophysical Properties ◽

Heat Conductivity ◽

Nuclear Reactor ◽

Reactor Vessel ◽

Full Scale ◽

Temperature Fields ◽

First Time

For the first time the paper determines thermophysical properties (specific heat capacity, thermal diffusivity, and heat conductivity) of the full-scale corium of the fast energy nuclear reactor within the temperature range from ~30°С to ~400°С. Obtained data are to be used in temperature fields calculations during modeling the processes of corium melt retention inside of the fast reactor vessel.

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Development of reactor vessel thermal hydraulic evaluation method under natural circulation decay heat removal conditions in sodium-cooled fast reactor

The Proceedings of Mechanical Engineering Congress Japan ◽

10.1299/jsmemecj.2020.s08111 ◽

2020 ◽

Vol 2020 (0) ◽

pp. S08111

Author(s):

Erina HAMASE ◽

Yasutomo IMAI ◽

Norihiro DODA ◽

Masaaki TANAKA

Keyword(s):

Fast Reactor ◽

Evaluation Method ◽

Natural Circulation ◽

Heat Removal ◽

Reactor Vessel ◽

Decay Heat

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Numerical integration by systematic sampling

Mathematical Proceedings of the Cambridge Philosophical Society ◽

10.1017/s0305004100025524 ◽

1950 ◽

Vol 46 (1) ◽

pp. 111-115 ◽

Cited By ~ 25

Author(s):

P. A. P. Moran

Keyword(s):

Numerical Integration ◽

Bounded Variation ◽

Mathematical Problem ◽

Random Variable ◽

Mean Value ◽

Lattice Points ◽

Systematic Sampling ◽

Image Position ◽

Infinite Sum

Recent investigations by F. Yates (1) in agricultural statistics suggest a mathematical problem which may be formulated as follows. A function f(x) is known to be of bounded variation and Lebesgue integrable on the range −∞ < x < ∞, and its integral over this range is to be determined. In default of any knowledge of the position of the non-negligible values of the function the best that can be done is to calculate the infinite sumfor some suitable δ and an arbitrary origin t, where s ranges over all possible positive and negative integers including zero. S is evidently of period δ in t and ranges over all its values as t varies from 0 to δ. Previous writers (Aitken (2), p. 45, and Kendall (3)) have examined the resulting errors for fixed t. (They considered only symmetrical functions, and supposed one of the lattice points to be located at the centre.) Here we do not restrict ourselves to symmetrical functions and consider the likely departure of S(t) from J (the required integral) when t is a random variable uniformly distributed in (0, δ). It will be shown that S(t) is distributed about J as mean value, with a variance which will be evaluated as a function of δ, the scale of subdivision.

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