US4097330A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Instrumentation assembly for nuclear reactor
Assignee: General Electric Co
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Filing: 1977-01-10
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Granted: 1978-06-27
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Expires: 1997-01-10
Abstract
Abstract In a moderated nuclear reactor core, an in-core neutron detector assembly with means for fixing the location of the detectors and for displacing the moderator in the vicinity of the detectors to thereby flatten and reduce the thermal neutron flux to which the neutron detectors are exposed.
Inventors
- 👤 John P. Neissel
- 👤 Harry H. Hendon
- 👤 James H. Terhune
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-04 09:44
CPC Classifications
G; G21; G21C; G21C17/00; G21C17/10; G21C17/108; Y; Y02; Y02E; Y02E30/00; Y02E30/30
Claims Analysis
Total Claims: 22
Claim 1
Independent Claim
237 words
A neutron detector assembly for use in a fluid moderated thermal neutron reactor core wherein said core includes a plurality of replaceable fuel assemblies of substantially square cross section shape and wherein said fuel assemblies are positioned in spaced relation to provide gaps for fluid moderator therebetween, comprising: an elongated solid moderator-displacing member adapted for positioning in said core between the corners of an adjacent four of said spaced fuel assemblies, said member extending through said core for a length at least equal to the active height of said core, said member having transverse cross section dimensions equal to the diagonal distance between the corners of said four fuel assemblies less a tolerance required for insertion, removal and thermal expansion of said fuel assemblies whereby the moderator in the space between said corners of said adjacent four fuel assemblies is substantially completely displaced to thereby depress and flatten the neutron flux therebetween, said moderator-displacing member being formed with at least one longitudinal passage for receiving a neutron detector for monitoring the neutron flux in said space over the power range of operation of said core, said moderator-displacing member being formed of a metal selected such that said transverse cross section dimensions thereof are less than one-fourth of the reciprocal of the slowing-down power of said metal for fast neutrons and less than one-half of the reciprocal of the macroscopic absorption cross of said metal for thermal neutrons.
Claim 2
Dependent Claim
237 words
A neutron detector assembly for use in a fluid moderated thermal neutron reactor core wherein said core includes a plurality of replaceable fuel assemblies of substantially square cross section shape and wherein said fuel assemblies are positioned in spaced relation to provide gaps for fluid moderator therebetween, comprising: an elongated solid moderator-displacing member adapted for positioning in said core between the corners of an adjacent four of said spaced fuel assemblies, said member extending through said core for a length at least equal to the active height of said core, said member having transverse cross section dimensions equal to the diagonal distance between the corners of said four fuel assemblies less a tolerance required for insertion, removal and thermal expansion of said fuel assemblies whereby the moderator in the space between said corners of said adjacent four fuel assemblies is substantially completely displaced to thereby depress and flatten the neutron flux therebetween, said moderator-displacing member being formed with at least one longitudinal passage for receiving a neutron detector for monitoring the neutron flux in said space over the power range of operation of said core, said moderator-displacing member being formed of a metal selected such that said transverse cross section dimensions thereof are less than one-fourth of the reciprocal of the slowing-down power of said metal for fast neutrons and less than one-half of the reciprocal of the macroscopic absorption cross of said metal for thermal neutrons.
Claim 3
Dependent Claim
17 words
The neutron detector assembly of claim 1 wherein said moderator-displacing member has a cruciform cross section shape.
Claim 4
Dependent Claim
23 words
The neutron detector assembly of claim 2 wherein said moderator-displacing member is formed with curved surfaces between adjacent arms of said cruciform shape.
Claim 5
Dependent Claim
18 words
The neutron detector assembly of claim 1 wherein said moderator-displacing member has a substantially square cross sectional shape.
Claim 6
Dependent Claim
18 words
The neutron detector assembly of claim 1 wherein said moderator-displacing member has a substantially circular cross sectional shape.
Claim 7
Dependent Claim
37 words
The neutron detector assembly of claim 1 wherein said moderator-displacing member is formed with a plurality of longitudinally extending passages for receiving a respective plurality of neutron detectors positioned at pre-determined longitudinally spaced positions in said passages.
Claim 8
Dependent Claim
37 words
The neutron detector assembly of claim 6 wherein said moderator-displacing member is additionally formed with a central longitudinally extending passage for receiving a selectively insertable neutron detector adapted for movement along the length of said central passage.
Claim 9
Dependent Claim
25 words
The neutron detector assembly of claim 1 wherein said moderator-displacing member is formed of a material selected from the group zirconium and alloys of zirconium.
Claim 10
Dependent Claim
29 words
The neutron detector assembly of claim 1 wherein said moderator-displacing member is formed of a material selected from the group niobium, aluminum, zinc, zirconium, molybdenum, magnesium and alloys thereof.
Claim 11
Dependent Claim
16 words
The neutron detector assembly of claim 1 including means for preventing moderator from entering said passage.
Claim 12
Dependent Claim
217 words
A neutron detector assembly for use in a fluid moderated thermal neutron reactor core wherein said core includes a plurality of fuel assemblies and wherein said fuel assemblies are spaced apart to provide gaps for fluid moderator therebetween, comprising: an elongated solid moderator-displacing member adapted for positioning in a space formed by said gaps between adjacent ones of said spaced fuel assemblies and extending into the active portion of said core, said moderator-displacing member being formed with at least one longitudinal passage for receiving a neutron detector for monitoring the neutron flux in said space over the power range of operation of said core, said member having transverse cross section dimensions equal to the transverse cross section dimensions of said space less a tolerance required for insertion, removal and thermal expansion of said fuel assemblies whereby the moderator in said space is substantially completely displaced, said member being formed of a metal selected such that the largest transverse cross section dimension of said member is less than one-fourth of the reciprocal of the slowing-down power of said metal for fast neutrons and less than one-half of the reciprocal of the macroscopic absorption cross section of said metal for thermal neutrons whereby the neutron flux in said space in the vicinity of said detector is depressed and flattened.
Claim 13
Dependent Claim
217 words
A neutron detector assembly for use in a fluid moderated thermal neutron reactor core wherein said core includes a plurality of fuel assemblies and wherein said fuel assemblies are spaced apart to provide gaps for fluid moderator therebetween, comprising: an elongated solid moderator-displacing member adapted for positioning in a space formed by said gaps between adjacent ones of said spaced fuel assemblies and extending into the active portion of said core, said moderator-displacing member being formed with at least one longitudinal passage for receiving a neutron detector for monitoring the neutron flux in said space over the power range of operation of said core, said member having transverse cross section dimensions equal to the transverse cross section dimensions of said space less a tolerance required for insertion, removal and thermal expansion of said fuel assemblies whereby the moderator in said space is substantially completely displaced, said member being formed of a metal selected such that the largest transverse cross section dimension of said member is less than one-fourth of the reciprocal of the slowing-down power of said metal for fast neutrons and less than one-half of the reciprocal of the macroscopic absorption cross section of said metal for thermal neutrons whereby the neutron flux in said space in the vicinity of said detector is depressed and flattened.
Claim 14
Dependent Claim
17 words
The neutron detector assembly of claim 11 wherein said moderator-displacing member has a cruciform cross section shape.
Claim 15
Dependent Claim
23 words
The neutron detector assembly of claim 12 wherein said moderator-displacing member is formed with curved surfaces between adjacent arms of said cruciform shape.
Claim 16
Dependent Claim
18 words
The neutron detector assembly of claim 11 wherein said moderator-displacing member has a substantially square cross sectional shape.
Claim 17
Dependent Claim
18 words
The neutron detector assembly of claim 11 wherein said moderator-displacing member has a substantially circular cross sectional shape.
Claim 18
Dependent Claim
37 words
The neutron detector assembly of claim 11 wherein said moderator-displacing member is formed with a plurality of longitudinally extending passages for receiving a respective plurality of neutron detectors positioned at pre-determined longitudinally spaced positions in said passages.
Claim 19
Dependent Claim
37 words
The neutron detector assembly of claim 16 wherein said moderator-displacing member is additionally formed with a central longitudinally extending passage for receiving a selectively insertable neutron detector adapted for movement along the length of said central passage.
Claim 20
Dependent Claim
25 words
The neutron detector assembly of claim 11 wherein said moderator-displacing member is formed of a material selected from the group zirconium and alloys of zirconium.
Claim 21
Dependent Claim
29 words
The neutron detector assembly of claim 11 wherein said moderator-displacing member is formed of a material selected from the group niobium, aluminum, zinc, zirconium, molybdenum, magnesium, and alloys thereof.
Claim 22
Dependent Claim
16 words
The neutron detector assembly of claim 11 including means for preventing moderator from entering said passage.
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USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1981-06-26 | 1981-12-26 | 1982-06-27 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1985-06-26 | 1985-12-26 | 1986-06-27 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1989-06-26 | 1989-12-26 | 1990-06-27 | $7700.00 | Window Closed / Lapsed |