UST921015I4 - Nuclear reactor corii cooling arrangement - Google Patents
Nuclear reactor corii cooling arrangement Download PDFInfo
- Publication number
- UST921015I4 UST921015I4 US921015DH UST921015I4 US T921015 I4 UST921015 I4 US T921015I4 US 921015D H US921015D H US 921015DH US T921015 I4 UST921015 I4 US T921015I4
- Authority
- US
- United States
- Prior art keywords
- nuclear reactor
- systems
- cooling arrangement
- flow
- corii
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000001816 cooling Methods 0.000 title abstract description 9
- 239000002826 coolant Substances 0.000 abstract description 5
- 239000012530 fluid Substances 0.000 abstract description 4
- 230000003068 static effect Effects 0.000 abstract description 2
- 230000003685 thermal hair damage Effects 0.000 abstract description 2
- 238000005253 cladding Methods 0.000 description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- a core cooling system for a nuclear reactor having a plurality of primary fluid flow systems.
- the reactor coolant flow from the primary systems is joined upon entering the pressure vessel. J ointure is accomplished in a common chamber causing high coolant flow velocities at low static pressures. If a pipe ruptures in one of the primary fluid flow systems, the low pressure in the common chamber minimizes leakage from the intact flow systems. This allows continuation of coolant flow through the nuclear core for a sufiicient length of time to eifectively eliminate the possibility of thermal damage.
- NUCLEAR REACTOR CORE COOLING ARRANGEMENT Filed Sept. 13, 1972 5 Sheets-Sheet 1 April 16, 1974 A. H. REDDING I NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Shoot 2 Filed Sept. 13, 1972 OIVF April 16, 1974 I H REDDlNG TQZLGIS NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Sheet 3 Filed Sept. 13. 1972 new.
- NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shbets-Sheot 4 4 6 8 10 I2 I4 I6 l8 T I ME (S ECONDS) A ril 16, 1974 A. H. REDDING NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shasta-Sheet 5 Filed Sept. 13.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Structures Of Non-Positive Displacement Pumps (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US28861072A | 1972-09-13 | 1972-09-13 |
Publications (1)
Publication Number | Publication Date |
---|---|
UST921015I4 true UST921015I4 (en) | 1974-04-16 |
Family
ID=23107861
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US921015D Pending UST921015I4 (en) | 1972-09-13 | 1972-09-13 | Nuclear reactor corii cooling arrangement |
US05/550,905 Expired - Lifetime US4080252A (en) | 1972-09-13 | 1975-02-18 | Nuclear reactor core cooling arrangement |
Family Applications After (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US05/550,905 Expired - Lifetime US4080252A (en) | 1972-09-13 | 1975-02-18 | Nuclear reactor core cooling arrangement |
Country Status (5)
Country | Link |
---|---|
US (2) | UST921015I4 (enrdf_load_stackoverflow) |
JP (1) | JPS5215757B2 (enrdf_load_stackoverflow) |
DE (1) | DE2345418A1 (enrdf_load_stackoverflow) |
FR (1) | FR2209173B1 (enrdf_load_stackoverflow) |
GB (1) | GB1417638A (enrdf_load_stackoverflow) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4035231A (en) | 1974-03-12 | 1977-07-12 | Electricite De France (Service National) | Emergency cooling device for a nuclear reactor |
CN107180659B (zh) * | 2017-05-09 | 2023-12-15 | 中广核研究院有限公司 | 变阻力式管道流速限制装置 |
Families Citing this family (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS585400B2 (ja) * | 1975-09-19 | 1983-01-31 | 株式会社日立製作所 | 機器もしくは配管の保温装置 |
GB2369236B (en) * | 1980-02-22 | 2002-09-18 | Rolls Royce & Associates Ltd | Reactor vessel for a nuclear power generating system |
US4412969A (en) * | 1982-03-09 | 1983-11-01 | Tilbrook Roger W | Combination pipe rupture mitigator and in-vessel core catcher |
US5267285A (en) * | 1992-06-24 | 1993-11-30 | Westinghouse Electric Corp. | Apparatus for suppressing formation of vortices in the coolant fluid of a nuclear reactor and associated method |
US7245689B2 (en) * | 2003-06-18 | 2007-07-17 | Mitsubishi Heavy Industries, Ltd | Nuclear reactor internal structure |
JP4786616B2 (ja) * | 2007-08-31 | 2011-10-05 | 三菱重工業株式会社 | 原子炉 |
CN105717545B (zh) * | 2016-02-22 | 2018-05-18 | 田志恒 | 一种监测管道内是否存在液态金属的装置 |
CN113432831B (zh) * | 2021-06-11 | 2022-04-05 | 西安交通大学 | 一种用于旋涡夹带现象研究的一体式实验装置及实验方法 |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3123533A (en) * | 1964-03-03 | Pressure relief device for neutronic reactors | ||
NL260537A (enrdf_load_stackoverflow) * | 1961-01-26 | |||
CH460536A (de) * | 1965-07-30 | 1968-07-31 | Gen Electric | Pumpvorrichtung mit einer Strahlpumpe |
US3621926A (en) * | 1968-02-13 | 1971-11-23 | Gen Electric | Nuclear reactor coolant recirculation system |
US3623948A (en) * | 1968-04-25 | 1971-11-30 | Babcock & Wilcox Co | Pressurized-water nuclear reactor |
JPS5147864B2 (enrdf_load_stackoverflow) * | 1972-06-02 | 1976-12-17 |
-
1972
- 1972-09-13 US US921015D patent/UST921015I4/en active Pending
-
1973
- 1973-09-03 GB GB4135873A patent/GB1417638A/en not_active Expired
- 1973-09-08 DE DE19732345418 patent/DE2345418A1/de not_active Withdrawn
- 1973-09-13 JP JP48102720A patent/JPS5215757B2/ja not_active Expired
- 1973-09-13 FR FR7332997A patent/FR2209173B1/fr not_active Expired
-
1975
- 1975-02-18 US US05/550,905 patent/US4080252A/en not_active Expired - Lifetime
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4035231A (en) | 1974-03-12 | 1977-07-12 | Electricite De France (Service National) | Emergency cooling device for a nuclear reactor |
CN107180659B (zh) * | 2017-05-09 | 2023-12-15 | 中广核研究院有限公司 | 变阻力式管道流速限制装置 |
Also Published As
Publication number | Publication date |
---|---|
JPS5215757B2 (enrdf_load_stackoverflow) | 1977-05-02 |
US4080252A (en) | 1978-03-21 |
JPS4968199A (enrdf_load_stackoverflow) | 1974-07-02 |
FR2209173B1 (enrdf_load_stackoverflow) | 1976-11-19 |
DE2345418A1 (de) | 1974-03-21 |
GB1417638A (en) | 1975-12-10 |
FR2209173A1 (enrdf_load_stackoverflow) | 1974-06-28 |
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