GB1524179A - Intrinsic safety derice for use in the core of a nuclear reactor with a liquid coolant - Google Patents
Intrinsic safety derice for use in the core of a nuclear reactor with a liquid coolantInfo
- Publication number
- GB1524179A GB1524179A GB20182/77A GB2018277A GB1524179A GB 1524179 A GB1524179 A GB 1524179A GB 20182/77 A GB20182/77 A GB 20182/77A GB 2018277 A GB2018277 A GB 2018277A GB 1524179 A GB1524179 A GB 1524179A
- Authority
- GB
- United Kingdom
- Prior art keywords
- core
- nuclear reactor
- derice
- liquid coolant
- intrinsic safety
- 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.)
- Expired
Links
- 239000002826 coolant Substances 0.000 title abstract 3
- 239000007788 liquid Substances 0.000 title 1
- JHIVVAPYMSGYDF-UHFFFAOYSA-N cyclohexanone Chemical compound O=C1CCCCC1 JHIVVAPYMSGYDF-UHFFFAOYSA-N 0.000 abstract 1
- 230000000630 rising effect Effects 0.000 abstract 1
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
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
-
- 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
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)
Abstract
1524179 Reactor safety device SOC ANON NOVATOME INDUSTRIES 13 May 1977 [31 May 1976] 20182/77 Heading G6C A safety device in the-core of a nuclear reactor comprises a vertical tube 3 incorporated in a sub-assembly 1 and open at both ends to allow coolant flow through it, the tube containing a float 8 and one or more neutron absorbing elements 9, 11, the arrangement being such that when the coolant temperature exceeds a threshold value, the float and element(s), sink so that the element(s) is introduced into the active region of the core. A locking arrangement Figs. 6a, 6b (not shown) prevents the elements rising again without manual intervention.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7616380A FR2353929A1 (en) | 1976-05-31 | 1976-05-31 | INTRINSIC SAFETY DEVICE APPLICABLE TO THE CORE OF A LIQUID REFRIGERANT NUCLEAR REACTOR |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1524179A true GB1524179A (en) | 1978-09-06 |
Family
ID=9173787
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB20182/77A Expired GB1524179A (en) | 1976-05-31 | 1977-05-13 | Intrinsic safety derice for use in the core of a nuclear reactor with a liquid coolant |
Country Status (4)
| Country | Link |
|---|---|
| DE (1) | DE2723277A1 (en) |
| FR (1) | FR2353929A1 (en) |
| GB (1) | GB1524179A (en) |
| IT (1) | IT1076188B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2894635A1 (en) * | 2014-01-14 | 2015-07-15 | GE-Hitachi Nuclear Energy Americas LLC | Passive shutdown system and method of operating a liquid metal cooled reactor using the same |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0375230B1 (en) * | 1988-12-19 | 1995-03-29 | General Electric Company | Self-acting safety for nuclear reactors |
| FR3044156B1 (en) * | 2015-11-23 | 2017-11-10 | Commissariat Energie Atomique | PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROP |
| FR3044155B1 (en) * | 2015-11-23 | 2017-11-10 | Commissariat Energie Atomique | PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROP |
-
1976
- 1976-05-31 FR FR7616380A patent/FR2353929A1/en active Granted
-
1977
- 1977-05-13 GB GB20182/77A patent/GB1524179A/en not_active Expired
- 1977-05-18 IT IT23696/77A patent/IT1076188B/en active
- 1977-05-24 DE DE19772723277 patent/DE2723277A1/en not_active Withdrawn
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2894635A1 (en) * | 2014-01-14 | 2015-07-15 | GE-Hitachi Nuclear Energy Americas LLC | Passive shutdown system and method of operating a liquid metal cooled reactor using the same |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2353929B1 (en) | 1981-01-23 |
| IT1076188B (en) | 1985-04-27 |
| FR2353929A1 (en) | 1977-12-30 |
| DE2723277A1 (en) | 1977-12-15 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PCNP | Patent ceased through non-payment of renewal fee |