
Vishal R. Sahni
Examiner (ID: 12162)
| Most Active Art Unit | 3657 |
| Art Unit(s) | 3657, 3616 |
| Total Applications | 1118 |
| Issued Applications | 821 |
| Pending Applications | 86 |
| Abandoned Applications | 239 |
Applications
| Application number | Title of the application | Filing Date | Status |
|---|---|---|---|
Array
(
[id] => 4397115
[patent_doc_number] => 06278756
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-08-21
[patent_title] => 'Electrochemical corrosion potential sensor with increased lifetime'
[patent_app_type] => 1
[patent_app_number] => 9/708110
[patent_app_country] => US
[patent_app_date] => 2000-11-06
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[patent_words_short_claim] => 97
[patent_maintenance] => 1
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[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/06/278/06278756.pdf
[firstpage_image] =>[orig_patent_app_number] => 708110
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/708110 | Electrochemical corrosion potential sensor with increased lifetime | Nov 5, 2000 | Issued |
Array
(
[id] => 4319927
[patent_doc_number] => 06252922
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-06-26
[patent_title] => 'Method of handling a nuclear reactor and an apparatus used in the handling method'
[patent_app_type] => 1
[patent_app_number] => 9/655824
[patent_app_country] => US
[patent_app_date] => 2000-09-06
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 14
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[pdf_file] => patents/06/252/06252922.pdf
[firstpage_image] =>[orig_patent_app_number] => 655824
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/655824 | Method of handling a nuclear reactor and an apparatus used in the handling method | Sep 5, 2000 | Issued |
| 09/485113 | FUEL ASSEMBLY | Feb 3, 2000 | Abandoned |
Array
(
[id] => 4383000
[patent_doc_number] => 06275556
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-08-14
[patent_title] => 'Method and apparatus for preventing relative rotation of tube members in a control rod drive mechanism'
[patent_app_type] => 1
[patent_app_number] => 9/442283
[patent_app_country] => US
[patent_app_date] => 1999-11-19
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 4
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[pdf_file] => patents/06/275/06275556.pdf
[firstpage_image] =>[orig_patent_app_number] => 442283
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/442283 | Method and apparatus for preventing relative rotation of tube members in a control rod drive mechanism | Nov 18, 1999 | Issued |
Array
(
[id] => 4421288
[patent_doc_number] => 06266386
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-07-24
[patent_title] => 'Lower reactor internals up-ending device'
[patent_app_type] => 1
[patent_app_number] => 9/417350
[patent_app_country] => US
[patent_app_date] => 1999-10-13
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 14
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[patent_no_of_words] => 5954
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[pdf_file] => patents/06/266/06266386.pdf
[firstpage_image] =>[orig_patent_app_number] => 417350
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/417350 | Lower reactor internals up-ending device | Oct 12, 1999 | Issued |
Array
(
[id] => 4311434
[patent_doc_number] => 06181761
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-01-30
[patent_title] => 'Apparatus and method of monitoring reactor power of reactor at the time of startup thereof'
[patent_app_type] => 1
[patent_app_number] => 9/399004
[patent_app_country] => US
[patent_app_date] => 1999-09-20
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 6
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[patent_no_of_words] => 9356
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[pdf_file] => patents/06/181/06181761.pdf
[firstpage_image] =>[orig_patent_app_number] => 399004
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/399004 | Apparatus and method of monitoring reactor power of reactor at the time of startup thereof | Sep 19, 1999 | Issued |
Array
(
[id] => 4275325
[patent_doc_number] => 06259760
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-07-10
[patent_title] => 'Unitary, transportable, assembled nuclear steam supply system with life time fuel supply and method of operating same'
[patent_app_type] => 1
[patent_app_number] => 9/392011
[patent_app_country] => US
[patent_app_date] => 1999-09-08
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[pdf_file] => patents/06/259/06259760.pdf
[firstpage_image] =>[orig_patent_app_number] => 392011
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/392011 | Unitary, transportable, assembled nuclear steam supply system with life time fuel supply and method of operating same | Sep 7, 1999 | Issued |
Array
(
[id] => 4386231
[patent_doc_number] => 06289071
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-09-11
[patent_title] => 'Positron source, method of preparing the same and automated system for supplying the same'
[patent_app_type] => 1
[patent_app_number] => 9/388060
[patent_app_country] => US
[patent_app_date] => 1999-09-01
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 7
[patent_figures_cnt] => 8
[patent_no_of_words] => 5243
[patent_no_of_claims] => 2
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[pdf_file] => patents/06/289/06289071.pdf
[firstpage_image] =>[orig_patent_app_number] => 388060
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/388060 | Positron source, method of preparing the same and automated system for supplying the same | Aug 31, 1999 | Issued |
| 09/373174 | METHOD OF SLUDGE REMOVAL IN PRESSURIZED WATER NUCLEAR REACTORS | Aug 11, 1999 | Abandoned |
Array
(
[id] => 4319941
[patent_doc_number] => 06252923
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-06-26
[patent_title] => 'In-situ self-powered monitoring of stored spent nuclear fuel'
[patent_app_type] => 1
[patent_app_number] => 9/371720
[patent_app_country] => US
[patent_app_date] => 1999-08-10
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 6
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[patent_no_of_words] => 6412
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[pdf_file] => patents/06/252/06252923.pdf
[firstpage_image] =>[orig_patent_app_number] => 371720
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/371720 | In-situ self-powered monitoring of stored spent nuclear fuel | Aug 9, 1999 | Issued |
Array
(
[id] => 4425836
[patent_doc_number] => 06178219
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-01-23
[patent_title] => 'Holder for fuel elements and method for repairing such a holder'
[patent_app_type] => 1
[patent_app_number] => 9/363262
[patent_app_country] => US
[patent_app_date] => 1999-07-29
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 2
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[pdf_file] => patents/06/178/06178219.pdf
[firstpage_image] =>[orig_patent_app_number] => 363262
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/363262 | Holder for fuel elements and method for repairing such a holder | Jul 28, 1999 | Issued |
Array
(
[id] => 4203410
[patent_doc_number] => 06130926
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2000-10-10
[patent_title] => 'Method and machine for enhancing generation of nuclear particles and radionuclides'
[patent_app_type] => 1
[patent_app_number] => 9/361602
[patent_app_country] => US
[patent_app_date] => 1999-07-27
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 6
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[pdf_file] => patents/06/130/06130926.pdf
[firstpage_image] =>[orig_patent_app_number] => 361602
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/361602 | Method and machine for enhancing generation of nuclear particles and radionuclides | Jul 26, 1999 | Issued |
Array
(
[id] => 4275312
[patent_doc_number] => 06259759
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-07-10
[patent_title] => 'Incore piping section maintenance system of reactor'
[patent_app_type] => 1
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[patent_app_country] => US
[patent_app_date] => 1999-07-27
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[firstpage_image] =>[orig_patent_app_number] => 361620
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/361620 | Incore piping section maintenance system of reactor | Jul 26, 1999 | Issued |
Array
(
[id] => 4369708
[patent_doc_number] => 06175606
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-01-16
[patent_title] => 'Filter for a nuclear fuel assembly'
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[firstpage_image] =>[orig_patent_app_number] => 319364
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/319364 | Filter for a nuclear fuel assembly | Jul 25, 1999 | Issued |
Array
(
[id] => 4167264
[patent_doc_number] => 06125160
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2000-09-26
[patent_title] => 'Nuclear fuel bundle spacer envelope dimension measuring system and methods'
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[firstpage_image] =>[orig_patent_app_number] => 359665
[rel_patent_id] =>[rel_patent_doc_number] =>) 09/359665 | Nuclear fuel bundle spacer envelope dimension measuring system and methods | Jul 25, 1999 | Issued |
Array
(
[id] => 4311409
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[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 2001-01-30
[patent_title] => 'Method and apparatus for determining nearness to criticality of a nuclear fueled electric power generating unit'
[patent_app_type] => 1
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[patent_app_country] => US
[patent_app_date] => 1999-07-23
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[rel_patent_id] =>[rel_patent_doc_number] =>) 09/360089 | Method and apparatus for determining nearness to criticality of a nuclear fueled electric power generating unit | Jul 22, 1999 | Issued |
Array
(
[id] => 4310964
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Array
(
[id] => 4306703
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[rel_patent_id] =>[rel_patent_doc_number] =>) 09/319532 | Fuel assembly for a nuclear reactor | Jul 20, 1999 | Issued |
Array
(
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Array
(
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[rel_patent_id] =>[rel_patent_doc_number] =>) 09/354395 | Production of radioisotopes with a high specific activity by isotopic conversion | Jul 14, 1999 | Issued |