GB1205849A – Liquid-safety rod system for a nuclear reactor
– Google Patents
GB1205849A – Liquid-safety rod system for a nuclear reactor
– Google Patents
Liquid-safety rod system for a nuclear reactor
Info
Publication number
GB1205849A
GB1205849A
GB50154/68A
GB5015468A
GB1205849A
GB 1205849 A
GB1205849 A
GB 1205849A
GB 50154/68 A
GB50154/68 A
GB 50154/68A
GB 5015468 A
GB5015468 A
GB 5015468A
GB 1205849 A
GB1205849 A
GB 1205849A
Authority
GB
United Kingdom
Prior art keywords
solution
reservoir
valve
poison
tubes
Prior art date
1967-10-26
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
Application number
GB50154/68A
Inventor
Alberto Agazzi
Armando Broggi
Sergio Galli De Paratesi
Luciano Ghiurghi
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
Priority date (The priority date 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 date listed.)
1967-10-26
Filing date
1968-10-22
Publication date
1970-09-16
1968-10-22
Application filed by European Atomic Energy Community Euratom
filed
Critical
European Atomic Energy Community Euratom
1970-09-16
Publication of GB1205849A
publication
Critical
patent/GB1205849A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
Classifications
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C7/00—Control of nuclear reaction
G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
G21C7/22—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
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
G21C9/033—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 an absorbent fluid
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
Abstract
1,205,849. Controlling reactors. EUROPEAN ATOMIC ENERGY COMMUNITY. 22 Oct., 1968 [26 Oct., 1967], No. 50154/68. Heading G6C. [Also in Division F1 A liquid-safety-rod system has a reservoir 17 for neutron poison solution below the level of a lower collector 3 connecting the lower ends of tubes 2 (only one shown) which extend upwardly through the reactor core, a poison-solution accumulator 5 with a flexible diaphragm 6 dividing it into a lower chamber 8 for poison solution and an upper chamber 9 for gas pressure connected by means of a quick-acting three-way valve 40, 41, 42 either to a source 11 of high pressure driving gas or to a reference low pressure 13, and an overflow reservoir 15 having an overflow discharge pipe 16 at a level 33 just below the bottom of the reactor core to determine the normal operating level of the poison solution. The discharge pipe 16 leads to the poison-solution reservoir 17 which is at a level below that of the overflow reservoir 15. The lower chamber 8 and the overflow reservoir 15 are connected at their lower ends to the lower collector 3, there being an isolation valve 14 between the chamber 8 and the reservoir 15. During the normal operation of the reactor, all the valves in the system are closed except the valve 40, 41, 42 which is open in the directions 41, 42, resulting in the chamber 9 being connected to the reference low pressure 13. The chamber 8 and the tubes 2 up to the level 33 are filled with poison solution. On an alarm signal, the valve 40, 41, 42 is opened in the directions 40, 41 and the driving gas from the source 11 forces the diaphragm 6 down against the lower wall of the accumulator 5, ejecting the poison solution into the tubes 2. If, after this emergency introduction, circulation of the poison solution is necessary, for example, if it would tend to decompose on heating in the reactor core, the solution is pumped by means of a pump 21 through a three-way valve 43, 44, 45 open in the directions 43, 45 and a valve 46 into the tubes 2 from which it returns via an upper collector 4 and a three-way valve 27, 28, 29 open in the directions 27, 28 to the reservoir 17. To remove the poison solution from the core, the valve 40, 41, 42 is re-opened in the directions 41, 42 and the high pressure gas discharged towards the low pressure 13. The solution enters the accumulator 5 again by gravity from the tubes 2. To empty the tubes 2, the valves 46 and 20 must be opened, the solution then descending by gravity into the reservoir 17. The tubes 2 may then be washed using a circuit comprising a washing-liquid reservoir 22, a washing-residue reservoir 23, a pump 24 and a valve 25. Washing is effected by opening the valves 25 and 46 and valve 27, 28, 29 in the directions 27, 29 and starting the pump 24.
GB50154/68A
1967-10-26
1968-10-22
Liquid-safety rod system for a nuclear reactor
Expired
GB1205849A
(en)
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
BE50095
1967-10-26
Publications (1)
Publication Number
Publication Date
GB1205849A
true
GB1205849A
(en)
1970-09-16
Family
ID=3840792
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB50154/68A
Expired
GB1205849A
(en)
1967-10-26
1968-10-22
Liquid-safety rod system for a nuclear reactor
Country Status (8)
Country
Link
US
(1)
US3607644A
(en)
BE
(1)
BE705693A
(en)
DE
(1)
DE1804206A1
(en)
FR
(1)
FR1587233A
(en)
GB
(1)
GB1205849A
(en)
LU
(1)
LU56402A1
(en)
NL
(1)
NL6813578A
(en)
SE
(1)
SE332864B
(en)
Families Citing this family (2)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
US3261624A
(en)
*
1964-04-28
1966-07-19
Southwest Products Co
Duct joint
US6181028B1
(en)
1999-08-19
2001-01-30
Generac Power Systems, Inc.
Transfer mechanism for transferring power between a utility source and a stand-by generator
1967
1967-10-26
BE
BE705693D
patent/BE705693A/xx
unknown
1968
1968-07-03
LU
LU56402D
patent/LU56402A1/xx
unknown
1968-08-14
SE
SE10962/68A
patent/SE332864B/xx
unknown
1968-09-23
NL
NL6813578A
patent/NL6813578A/xx
unknown
1968-10-02
US
US764413A
patent/US3607644A/en
not_active
Expired – Lifetime
1968-10-16
DE
DE19681804206
patent/DE1804206A1/en
active
Pending
1968-10-22
GB
GB50154/68A
patent/GB1205849A/en
not_active
Expired
1968-10-25
FR
FR1587233D
patent/FR1587233A/fr
not_active
Expired
Also Published As
Publication number
Publication date
LU56402A1
(en)
1968-10-21
US3607644A
(en)
1971-09-21
NL6813578A
(en)
1969-04-29
SE332864B
(en)
1971-02-22
BE705693A
(en)
1968-04-26
DE1804206A1
(en)
1969-07-03
FR1587233A
(en)
1970-03-13
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Legal Events
Date
Code
Title
Description
1971-01-27
PS
Patent sealed [section 19, patents act 1949]
1973-05-16
PLNP
Patent lapsed through nonpayment of renewal fees
