GB1380601A - Plant for irradiation of fuel elements or components of nuclear reactors - Google Patents
Plant for irradiation of fuel elements or components of nuclear reactorsInfo
- Publication number
- GB1380601A GB1380601A GB1587372A GB1587372A GB1380601A GB 1380601 A GB1380601 A GB 1380601A GB 1587372 A GB1587372 A GB 1587372A GB 1587372 A GB1587372 A GB 1587372A GB 1380601 A GB1380601 A GB 1380601A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reactor
- reactors
- neutron
- specimen
- pulsed
- 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
- G21C1/303—Experimental or irradiation arrangements inside the reactor
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
Abstract
1380601 Reactors; irradiating materials GES FUER KERNFORSCHUNG mbH 6 April 1972 [7 April 1971] 15873/72 Heading G6C Plant for irradiating test specimens comprises a pair of adjacent critical reactor systems 1, 2 of which one, e.g. system 2, is a pulsed reactor. In the embodiment of Fig. 1 an irradiation channel 4 extends between the reactors which are separated by a neutron shield 3. A test specimen 5 can be moved from initial position 7 in reactor 1 where it achieves a temperature distribution equivalent to that of a normal reactor environment, to a position 8 in reactor 2 where it receives a pulsed neutron flux simulating an overload condition in the normal reactor environment. Initiation of the pulse is automatic in response to movement of the speciment to position 8. Coolant in channel 4 may flow in a closed loop (independent of coolant for the reactors 1, 2) or an open loop. In the embodiment of Fig. 2 the specimen remains stationary in the irradiation channel which extends through a gap between the reactors. Instead, a tubular neutron shield 9, part of which provides a neutron window, is rotatable through 180 degrees to expose the specimen firstly to reactor 1 and subsequently to the pulsed reactor 2. In a modification the neutron shield 9 has opposite but axially offset neutron-absorbing portions and is movable axially, without rotation, to expose the specimen. The test specimens may be reactor fuel elements or other reactor components.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2116937A DE2116937C3 (en) | 1971-04-07 | 1971-04-07 | Procedure for testing fuel assemblies for nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1380601A true GB1380601A (en) | 1975-01-15 |
Family
ID=5804100
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1587372A Expired GB1380601A (en) | 1971-04-07 | 1972-04-06 | Plant for irradiation of fuel elements or components of nuclear reactors |
Country Status (3)
Country | Link |
---|---|
DE (1) | DE2116937C3 (en) |
FR (1) | FR2132793B3 (en) |
GB (1) | GB1380601A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109273119A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Optimize the method for neutron detector position when measuring big reactivity on critical assembly |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4764339A (en) * | 1986-12-16 | 1988-08-16 | The United States Of America As Represented By The United States Department Of Energy | High flux reactor |
-
1971
- 1971-04-07 DE DE2116937A patent/DE2116937C3/en not_active Expired
-
1972
- 1972-04-06 GB GB1587372A patent/GB1380601A/en not_active Expired
- 1972-04-07 FR FR7212372A patent/FR2132793B3/fr not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109273119A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Optimize the method for neutron detector position when measuring big reactivity on critical assembly |
CN109273119B (en) * | 2018-09-13 | 2022-02-11 | 中国核动力研究设计院 | Method for optimizing the position of a neutron detector during the measurement of high reactivity on a critical device |
Also Published As
Publication number | Publication date |
---|---|
FR2132793B3 (en) | 1974-05-10 |
FR2132793A3 (en) | 1972-11-24 |
DE2116937A1 (en) | 1972-10-19 |
DE2116937B2 (en) | 1979-07-19 |
DE2116937C3 (en) | 1980-04-24 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |