CA599587A - Nuclear reactors - Google Patents

Nuclear reactors

Info

Publication number
CA599587A
CA599587A CA599587A CA599587DA CA599587A CA 599587 A CA599587 A CA 599587A CA 599587 A CA599587 A CA 599587A CA 599587D A CA599587D A CA 599587DA CA 599587 A CA599587 A CA 599587A
Authority
CA
Canada
Prior art keywords
nuclear reactors
reactors
nuclear
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
Application number
CA599587A
Inventor
R. Smith Derek
S. Mckean Roderick
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.)
AEI John Thompson Nuclear Energy Co Ltd
Original Assignee
AEI John Thompson Nuclear Energy Co Ltd
Publication date
Application granted granted Critical
Publication of CA599587A publication Critical patent/CA599587A/en
Expired legal-status Critical Current

Links

CA599587A Nuclear reactors Expired CA599587A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA599587T

Publications (1)

Publication Number Publication Date
CA599587A true CA599587A (en) 1960-06-07

Family

ID=35815368

Family Applications (1)

Application Number Title Priority Date Filing Date
CA599587A Expired CA599587A (en) Nuclear reactors

Country Status (1)

Country Link
CA (1) CA599587A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4948555A (en) * 1987-10-14 1990-08-14 Framatome Removal device for controlling the flow rate of coolant fluid in a fast-neutron nuclear reactor assembly and corresponding control process and assembly

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4948555A (en) * 1987-10-14 1990-08-14 Framatome Removal device for controlling the flow rate of coolant fluid in a fast-neutron nuclear reactor assembly and corresponding control process and assembly

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