JP5636313B2 - Primary containment vessel - Google Patents

Description

  The present invention relates to a reactor containment vessel.

  In a nuclear facility, a reactor containment vessel is provided around a reactor pressure vessel or the like. The reactor containment vessel is provided for the purpose of confining leaked radioactive material inside and preventing it from being released to the outside in the event of an accident.

  Steel containment vessels have been used for most of the reactor containment vessels, but from the viewpoint of high power and economy, prestressed concrete containment vessels (PCCV), reinforced concrete containment vessels (RCCV), etc. A concrete containment container is often used.

  In the future, a steel plate concrete containment vessel (SCCV), which is a structural type capable of further improving performance and shortening the work period, is considered, and various studies have been made to realize the structure.

  The steel plate concrete containment vessel has a sandwich structure in which both sides of the concrete portion are sandwiched between steel plates. And the steel plate inside the container is expected to be capable of confining radioactive materials at the time of an accident and preventing leakage.

  For example, in the containment containers described in Patent Documents 1 and 2, the steel plate and concrete are integrally resisted by stud bolts and tie bars against the pressure load and temperature load in the event of an accident, and the containment container is made radioactive. When the coolant containing is discharged | emitted, it has the structure which anticipates the function for confining these in a containment vessel in the steel plate inside a containment vessel.

JP 2006-78256 A Japanese Patent Laid-Open No. 5-60891

  As described above, in the SCCV currently under review, the steel plate inside the containment vessel directly receives the temperature rise in the event of an accident. It is a severe design condition that requires a material confinement function.

In addition, since the steel plate inside the containment vessel is constrained to the concrete by stud bolts or the like provided at predetermined intervals, the steel plate that is about to stretch against the sudden rise in temperature inside the containment vessel has a moderate temperature rise. Compressive buckling is likely to occur when restrained by certain concrete.
Regarding the prevention of compression buckling due to high temperature, Niwa et al. Did not generate compression buckling at B / t = 20 when the steel sheet surface temperature was 300 ° C. with respect to the relationship between the steel sheet thickness t and the stud bolt interval B. B / t = 40 and 50 (Nobuyuki Niwa, Ippei Matsuo, Junichi Miyamoto, Yoshikazu Sawamoto “Characteristic confirmation experiment of SC structure under high temperature, Part 1 Thermal buckling experiment”, Architectural Institute of Japan Summaries of annual conference lectures (Kyushu), C-1, p. 1257-1258, 20077.8).

  Furthermore, as shown in the document “Relationship between temperature characteristics of EUROCODE IV (general) steel materials”, the steel sheet has a property that its elastic limit strength and tensile strength rapidly decrease under high temperature conditions. For this reason, in order to exert the function of confining radioactive materials, a highly reliable evaluation method is required in terms of design.

  Further, there may be a floor-like internal structure or the like inside the containment vessel, and these have a structure that directly contacts the containment vessel. The members such as the internal structure are attached to an internal steel plate that is required to have a radioactive substance confinement function, and there are many design and manufacturing restrictions.

  The present invention has been made in view of the above problems, and an object of the present invention is to provide a reactor containment vessel that enables highly reliable design and evaluation.

A first invention for achieving the above object is a reactor containment vessel having an inner steel plate and an outer steel plate, and a casing made of concrete filled between the inner steel plate and the outer steel plate, the outer steel plate Is a reactor containment vessel characterized in that a steel material for pressure vessels is used and leakage of radioactive materials is prevented by the outer steel plate.

Before SL pressure vessel steel, for example, medium-low temperature pressure vessel steel plate, or a medium room temperature pressure vessel carbon steel steel plate.

  Moreover, you may use structural steel materials for the said inner side steel plate. The structural steel material is, for example, any one of a general structural rolled steel material, a welded structural rolled steel material, and a building structural rolled steel material.

  With the above configuration, leakage of radioactive materials during an accident or the like is prevented by the outer steel plate of the reactor containment vessel. As the outer steel plate, a steel material for a pressure vessel such as a steel plate material for a medium-low temperature pressure vessel or a carbon steel plate material for a medium-temperature pressure vessel can be used. Since the outer steel plate is in contact with the outside air and has a concrete layer on the inner side, it is hardly affected by high temperatures or the like even in the event of an accident, and more reliable design and evaluation becomes possible.

  In addition, when a member such as a floor-shaped internal structure is attached to an inner steel plate that does not require a radioactive material confinement function, it is under severe conditions, but there are relatively few design and manufacturing restrictions and reasonable details (containment) Structure).

  According to the present invention, it is possible to provide a reactor containment vessel that enables highly reliable design and evaluation.

Diagram showing an example of a containment vessel Figure showing an example of steel-plate concrete structure of a containment vessel

  Hereinafter, the reactor containment vessel according to the embodiment of the present invention will be described in detail with reference to FIGS. 1 and 2.

FIG. 1 is a diagram illustrating an example of a containment vessel 1. The reactor containment vessel 1 is provided in the reactor building 100. The reactor containment vessel 1 is provided with a reactor pressure vessel (not shown), a steam generator, and the like. For example, as shown in FIG. 1, the reactor containment vessel 1 includes a vertical member 2 a such as a cylindrical side wall and a horizontal member 2 b such as a top slab provided on the vertical member 2 a. . Further, the reactor containment vessel 1 is provided with a floor member 4 or the like as an internal structure. The floor member 4 has a structure in which concrete is reinforced with a member such as a steel plate or a reinforcing bar, and the member such as the steel plate or the reinforcing bar is connected to an inner steel plate 5 described later.
The shape of the reactor containment vessel 1 is not limited to this. For example, the side wall portion may have a rectangular shape, a cylindrical side wall portion provided with a hemispherical ceiling portion, a frustum shape, or the like. These may be appropriately determined according to the type, form, safety, etc. of the boiling water reactor or the pressurized water reactor. The internal structure of the floor member 4 and the like is also provided as necessary.

  FIG. 2 is a view showing an example of a steel plate concrete structure of the reactor containment vessel 1. 2A is a horizontal sectional view showing an example of the vertical member 2a such as a side wall, FIG. 2B is a vertical sectional view showing an example of the vertical member 2a, and FIG. 2C is a horizontal member such as a top slab. It is a vertical direction sectional view showing an example of 2b. As shown in each figure, the reactor containment vessel 1 has a structural casing having a steel plate concrete structure configured by filling concrete 3 between an inner steel plate 5 and an outer steel plate 7. The inner side refers to the side toward the inside of the reactor containment vessel 1, and the outer side refers to the side toward the outside of the reactor containment vessel 1. Further, the concrete 3 may be reinforced concrete reinforced with reinforcing bars, and may be prestressed concrete or the like.

  The inner steel plate 5 and the outer steel plate 7 are fixed to the concrete 3 by stud bolts 9 provided at predetermined intervals. In addition, a tie bar 11 or the like that connects the inner steel plate 5 and the outer steel plate 7 is provided and reinforced. The reinforcement in the steel plate concrete structure is not limited to this, and may be determined as appropriate according to the purpose, such as a steel plate.

  In the present invention, the above-described radioactive substance is confined in the outer steel plate 7 to prevent the leakage. In other words, the outer steel plate 7 is designed so that no cracks or the like occur in response to various environmental conditions at the time of the assumed (predetermined) accident even in the event of an assumed accident. For this reason, steel materials for pressure vessels, such as SPV materials (steel plate materials for medium-low temperature pressure vessels) and SGV materials (carbon steel plate materials for medium-temperature pressure vessels), can be used for the outer steel plate 7. These steel materials for pressure vessels have high strength and weldability and are more suitable for such purposes. And other conditions, such as the shape, such as the intensity | strength and thickness, the joining method between the outer side steel plates 7, are defined according to said objective.

  The outer steel plate 7 has the concrete 3 as a heat insulating member on the inner side, and the outer side is in contact with the outside air. Therefore, the outer steel plate 7 is almost normal temperature even in the event of an accident, and is not affected by high temperature or the like. Etc. do not occur. Therefore, design is possible based on the yield point strength of a steel sheet at room temperature, and no cracking occurs, and highly reliable design and evaluation that can fully utilize the strength of the steel sheet are possible.

  And the inner side steel plate 5 is designed so that it may fulfill the role of satisfying the structural body strength of the reactor containment vessel 1 against dead loads, earthquake loads, and the like. For the inner steel plate 5, structural steel materials such as SS material (rolled steel material for general structure), SM material (rolled steel material for welded structure), and SN material (rolled steel material for building structure) can be used. Its strength, shape, etc. are determined according to the above-mentioned purpose. As a result of not having the role of confining radioactive material in the inner steel plate 5, structural steel materials used in the construction field such as SS material, SM material, SN material, etc. can be used, and other methods such as joining methods between steel plates The degree of freedom increases. Also, when connecting members such as steel plates and reinforcing bars of the floor member 4 to the inner steel plate 5, it is under severe conditions, but compared with the case where the inner steel plate 5 has a role of confining radioactive substances. The above restrictions are relatively few, and it becomes possible to adopt rational details (containment structure).

  As described above, according to the embodiment of the reactor containment vessel of the present invention, leakage of radioactive materials during an accident or the like is prevented by the outer steel plate of the reactor containment vessel. As the outer steel plate, a steel material for a pressure vessel such as a steel plate material for a medium-low temperature pressure vessel or a carbon steel plate material for a medium-temperature pressure vessel can be used. The outer steel sheet is in contact with the outside air and has a concrete layer on the inner side, so that it is maintained near room temperature even in the event of an accident. Therefore, it is possible to perform design and evaluation with higher reliability without being affected by high temperature and the like.

  In addition, when a member such as a floor-shaped internal structure is attached to an inner steel plate that does not require a radioactive material confinement function, it is under severe conditions, but there are relatively few design and manufacturing restrictions and reasonable details (containment) Structure).

  The preferred embodiments of the reactor containment vessel according to the present invention have been described above with reference to the accompanying drawings, but the present invention is not limited to such examples. It will be apparent to those skilled in the art that various changes or modifications can be conceived within the scope of the technical idea disclosed in the present application, and these naturally belong to the technical scope of the present invention. Understood.

1 ……… Container 3 ……… Concrete 5 ……… Inner steel plate 7 ……… Outer steel plate 9 ……… Stud bolt 11 ……… Tie bar

Claims (4)

A reactor containment vessel having an inner steel plate and an outer steel plate, and a casing made of concrete filled between the inner steel plate and the outer steel plate,
A reactor containment vessel characterized in that a steel material for a pressure vessel is used for the outer steel plate, and leakage of radioactive materials is prevented by the outer steel plate. The pressure vessel steel, reactor containment vessel according to claim 1, wherein the middle low temperature pressure vessel steel plate, or a medium room temperature pressure vessel carbon steel steel plate. Wherein the inner steel plates, reactor containment vessel according to claim 1 or claim 2, characterized in that structural steel is used. The reactor containment vessel according to claim 3 , wherein the structural steel material is any one of a general structural rolled steel material, a welded structural rolled steel material, and a building structural rolled steel material.

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