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ES361211A1 - Nuclear reactor fuel assembly - Google Patents

Nuclear reactor fuel assembly

Info

Publication number
ES361211A1
ES361211A1ES361211AES361211AES361211A1ES 361211 A1ES361211 A1ES 361211A1ES 361211 AES361211 AES 361211AES 361211 AES361211 AES 361211AES 361211 A1ES361211 A1ES 361211A1
Authority
ES
Spain
Prior art keywords
fuel
fissile
per cent
atom per
content
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
ES361211A
Other languages
Spanish (es)
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.)
General Electric Co
Original Assignee
General Electric Co
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.)
Filing date
Publication date
Application filed by General Electric CofiledCriticalGeneral Electric Co
Publication of ES361211A1publicationCriticalpatent/ES361211A1/en
Expiredlegal-statusCriticalCurrent

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Abstract

A nuclear fuel element assembly comprises fuel elements arranged in a plurality of groups including an inner group and at least one outer group arranged concentrically around the inner group, the fuel of the elements of a first one of the groups having an initial predetermined enrichment of fissile Pu, and the initial Pu content (if any) of the fuel of the other or at least one other group being markedly different from that of the first. The Pu may be concentrated in the outer fuel elements of the assembly near the regions of highest neutron moderation, i.e. near zones of lowest thermal neutron energy, which arrangement provides for optimization of fuel cycle costs and fuel reliability. Alternatively, the Pu may be concentrated in the inner fuel elements of the assembly, which arrnagement provides for optimization of power and critical heat flux shaping by taking advantage of the increase in the ratio of the thermal fission cross-section of fissile Pu to that of fissile and of the unique higher heat flux capability of the central fuel elements of a boiling water reactor fuel assembly. In the first of these two embodiments, the outer fuel elements contain 1 to 2 atom per cent fissile Pu mixed with depleted or natural U of 0.25 to 0À71 atom per cent fissile U content, while the inner fuel elements contain U fuel of about 3 atom per cent fissile U content. In the second embodiment, the inner fuel elements contain 1 to 2 atom per cent fissile Pu mixed with U of 0À3 to 2 atom per cent fissile U content, while the outer fuel elements contain U fuel of 2 to 3 atom per cent fissile U content.
ES361211A1967-12-151968-12-07Nuclear reactor fuel assemblyExpiredES361211A1 (en)

Applications Claiming Priority (1)

Application NumberPriority DateFiling DateTitle
US69104467A1967-12-151967-12-15

Publications (1)

Publication NumberPublication Date
ES361211A1true ES361211A1 (en)1972-01-01

Family

ID=24774945

Family Applications (1)

Application NumberTitlePriority DateFiling Date
ES361211AExpiredES361211A1 (en)1967-12-151968-12-07Nuclear reactor fuel assembly

Country Status (10)

CountryLink
BE (1)BE725473A (en)
CH (1)CH499177A (en)
DE (1)DE1814641B2 (en)
ES (1)ES361211A1 (en)
FI (1)FI49089C (en)
FR (1)FR1598423A (en)
GB (1)GB1241456A (en)
IL (1)IL31145A (en)
NL (1)NL6817982A (en)
SE (1)SE345032B (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication numberPriority datePublication dateAssigneeTitle
EP0065697B1 (en)*1981-05-151985-09-11Hitachi, Ltd.Fuel assembly
FR2606201B1 (en)*1986-11-031988-12-02Electricite De France METHOD FOR MANAGING THE HEART OF A PRESSURIZED WATER NUCLEAR REACTOR
GB2221079A (en)*1988-07-191990-01-24Atomic Energy Authority UkA method and apparatus for inhibiting thermal cycling
US5089210A (en)*1990-03-121992-02-18General Electric CompanyMox fuel assembly design
CN115394459B (en)*2022-08-262024-08-20中国核动力研究设计院Ultra-high flux reactor core based on plate-shaped fuel assembly

Also Published As

Publication numberPublication date
GB1241456A (en)1971-08-04
NL6817982A (en)1969-06-17
IL31145A0 (en)1969-02-27
FI49089C (en)1975-03-10
IL31145A (en)1973-03-30
CH499177A (en)1970-11-15
BE725473A (en)1969-06-13
SE345032B (en)1972-05-08
DE1814641A1 (en)1969-07-24
FI49089B (en)1974-12-02
FR1598423A (en)1970-07-06
DE1814641B2 (en)1973-04-12

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