KR-20260066715-A - Reactor building isolation test fixture for leakage rate testing

Abstract

An integrated system that may include a reactor; and a device comprising a reactor building isolation system configured to prevent the release of radioactive material from the reactor. The reactor building isolation system may include a containment vessel and a reactor building isolation test valve. The reactor building isolation test valve may include a body having a first test port and a first test port plug. The reactor building isolation test valve may include a cover configured to be coupled to the body, and the cover has a first seal, a second seal, an area between the first seal and the second seal, a second test port, and a second test port plug. The reactor building isolation system may include a reactor building isolation valve.

Inventors

• 케이넌 브라이언
• 복 프레스턴
• 맥기 게리
• 카딜로 어기
• 애셜 개럿

Assignees

• 뉴스케일 파워, 엘엘씨

Dates

Publication Date

20260512

Application Date

20240920

Priority Date

20240919

Claims (20)

1. As a reactor building isolation system, Containment vessel, A first reactor building isolation valve located downstream of the above containment vessel; A second reactor building isolation valve located downstream of the first reactor building isolation valve; and It includes a test valve located upstream of the first reactor building isolation valve and downstream of the containment vessel, and the test valve is, entity, A disk disposed within the above-mentioned main body—the disk is configured to accommodate a key and to be rotated by said key before and after performing a test operation utilizing at least one of said first reactor building isolation valve or said second reactor building isolation valve, and said disk is configured to be rotated together with said key—, and A reactor building isolation system comprising a cover coupled to the main body, wherein the cover is configured to be removed before insertion of the key so that the key can be inserted into the disk and rotated.
2. A reactor building isolation system according to claim 1, wherein the cover comprises at least one of a position indicator or a flow indicator.
3. A reactor building isolation system according to claim 1, wherein the cover comprises a test port configured to provide a fluid flow path through the cover.
4. A reactor building isolation system according to claim 1, wherein the main body comprises a test port configured to provide a fluid flow path through the main body.
5. A reactor building isolation system according to claim 1, wherein the test valve further comprises a spindle having a first end configured to engage with the cover and a second end opposite to the first end configured to engage with the disk.
6. A reactor building isolation system according to claim 1, wherein the cover comprises a spindle configured to extend into the main body.
7. A reactor building isolation system according to claim 1, wherein the cover comprises a spindle configured to engage with the disk.
8. As an integrated system, nuclear reactor; and It includes a reactor building isolation system, and the reactor building isolation system is, Reactor Building Isolation Test Valve - The above reactor building isolation test valve is, A test port configured to receive pressurized fluid, and Includes a test port plug configured to rotate to seal the above test port -; and An integrated system comprising a reactor building isolation valve — said reactor building isolation valve is located downstream of said reactor building isolation test valve and is configured to restrict fluid flow through a disk and seat assembly disposed within said reactor building isolation valve.
9. In paragraph 8, The above reactor building isolation test valve is the first reactor building isolation test valve, and The above integrated system further comprises a second reactor building isolation test valve.
10. In claim 8, the reactor building isolation test valve comprises a cover, and the cover has at least one of a position indicator or a flow indicator, in an integrated system.
11. In paragraph 8, The above test port is a first test port, and The above test port plug is a first test port plug, and The above reactor building isolation valve further includes a cover, and the cover is, A second test port configured to provide a fluid flow path through the above cover, and An integrated system comprising a second test port plug configured to rotate to seal the second test port.
12. In claim 8, the reactor building isolation test valve further comprises a spindle having a first end configured to engage with a cover and a second end opposite to the first end configured to engage with a disk, in an integrated system.
13. In claim 8, the reactor building isolation valve comprises a cover having a spindle, and the spindle is configured to extend into the body of the reactor building isolation valve, an integrated system.
14. In claim 8, the reactor building isolation valve comprises a cover having a spindle configured to engage with a disk, and the disk is disposed within the body of the reactor building isolation test valve, in an integrated system.
15. As an isolation test valve, A main body having a first test port configured to receive pressurized fluid, A first test port plug configured to rotate to seal the first test port, A disk disposed within the above main body - said disk accommodates an operating tool and is configured to be rotated by the operating tool before and after performing an isolation test operation, and said disk is configured to rotate together with the operating tool -; A cover configured to be coupled to the above-mentioned main body - the cover comprises a second test port configured to receive the pressurized fluid and a second test port plug configured to rotate to seal the second test port -; A first sealing portion disposed between the cover and the main body - the first sealing portion is disposed adjacent to the first side of the second test port -, and An isolation test valve comprising a second seal portion disposed between the cover and the main body, wherein the second seal portion is disposed adjacent to a second side of the second test port, and the second side of the second test port faces a first side of the second test port.
16. In item 15, the above cover comprises at least one of a position indicator or a flow indicator, an isolation test valve.
17. In item 15, the isolation test valve, wherein the cover comprises a spindle configured to extend into the body of the isolation test valve.
18. In paragraph 15, the isolation test valve, wherein the cover comprises a spindle configured to engage with the disk.
19. In claim 15, the isolation test valve further comprises a spindle having a first end configured to engage with the cover and a second end opposite to the first end configured to engage with the disk.
20. In item 15, the isolation test valve, wherein the first test port is on the first side of the disk and the second test port is on the second side of the disk, and the second side is opposite to the first side.

Description

Reactor building isolation test fixture for leakage rate testing Statement regarding federal government-sponsored research The present invention was made with government support under contract number DE-NE0008928 granted by the Department of Energy. The government holds specific rights to the present invention. Cross-reference of related applications The present application claims the benefit of U.S. Provisional Patent Application No. 63/539,761, filed September 21, 2023, with the title "CONTAINMENT ISOLATION TEST FIXTURE (CITF) FOR LEAK RATE TESTING", and the benefit of U.S. Patent Application No. 18/890,676, filed September 19, 2024, with the title "CONTAINMENT ISOLATION TEST FIXTURE FOR LEAK RATE TESTING", all of which are incorporated herein by reference in their entirety. The reactor utilizes a reactor building isolation system to isolate fluid systems within the reactor. The reactor building isolation system protects external systems from contamination and/or radiation exposure. The reactor building isolation system provides means (e.g., reactor building isolation valve(s)) for isolating fluid systems passing through penetrations within the pressure vessel. Fluid systems passing through penetrations within the pressure vessel may be used to transport potentially radioactive and/or contaminated fluids. By using a containment isolation system, the reactor can prevent or reduce the likelihood of any radioactive fluid and/or material leaking downstream of a containment isolation valve (CIV) when the CIV is shut off. To analyze the condition, capability, and/or reliability of the CIV, the CIV may be tested periodically. The results of CIV tests can be used to verify that the CIV has the potential to prevent or reduce the likelihood of fluid and/or material passing through the CIV in the event of an accident. Typically, the CIV is tested by operating the valve within the pressure vessel (i.e., the high-radiation zone) and/or by installing temporary test fittings for use during leak testing. Temporary test fittings that are not installed in the CIV during normal operation may be installed in the CIV during testing and then removed. "Specific details for carrying out the invention" are described with reference to the attached drawings. In the drawings, the leftmost digit(s) of a reference number identify the drawing in which that reference number first appears. The use of the same reference number in different drawings indicates similar or identical items. Additionally, the drawings may be considered to provide a rough depiction of the relative sizes of individual components within individual drawings. However, the drawings do not adhere to scale, and the relative sizes of individual components within individual drawings and between different drawings may differ from those depicted. In particular, some drawings may depict components in a specific size or shape, while others may depict the same components at a larger scale or in a different shape for clarity. FIG. 1 schematically illustrates an integrated nuclear power plant system including a small modular reactor (SMR) system having a nuclear power module (NPM) that includes a containment isolation test fixture (CITF) to be used during a reactor building isolation valve (CIV) leak test. FIG. 2 schematically illustrates an embodiment of an NPM integrated with a containment isolation system (CIS) having a CITF installed upstream of a CIV. Figure 3 illustrates an enlarged side cross-sectional view of a portion of the CIS utilizing CITF upstream of the CIV. Figure 4 illustrates an enlarged side cross-sectional view of CITF. FIG. 5 illustrates a side cross-sectional view of another embodiment of CITF, in which the cover is moved toward the main body of CITF. FIGS. 6a through 6c illustrate exemplary plan views of position markings for CITF on a CITF cover. FIG. 7 illustrates a cross-sectional view of one embodiment of a CITF having a spindle separated from a cover. Figure 8 illustrates a diagram of a P&ID isolation barrier to enable in-situ leakage rate pressure testing between the CNV and CIV. FIG. 9 illustrates a block diagram (900) having various states related to a process for performing a test operation. FIG. 10 is a partially schematic cross-sectional view of a reactor system constructed according to an embodiment of the present technology. FIG. 11 is a partially schematic cross-sectional view of a reactor system configured according to an additional embodiment of the present technology. FIG. 12 is a schematic diagram of a nuclear power plant system including a plurality of reactors according to an embodiment of the present technology. outline The present disclosure relates to a Small Modular Reactor (SMR) system utilizing at least one Nuclear Power Module (NPM) having a Reactor Building Isolation System (CIS) integrated with a Reactor Building Isolation Test Fixture (CITF) (e.g., Reactor Building Isolation Test Valve, Isolation Test Valve, etc.) included be