
Ricardo J. Palabrica
Examiner (ID: 6884)
| Most Active Art Unit | 3663 |
| Art Unit(s) | 3663, 3641, 3646 |
| Total Applications | 599 |
| Issued Applications | 375 |
| Pending Applications | 14 |
| Abandoned Applications | 210 |
Applications
| Application number | Title of the application | Filing Date | Status |
|---|---|---|---|
Array
(
[id] => 5015348
[patent_doc_number] => 20070258556
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2007-11-08
[patent_title] => 'Annular nuclear fuel rod controllable in heat fluxes of inner and outer tubes'
[patent_app_type] => utility
[patent_app_number] => 11/606104
[patent_app_country] => US
[patent_app_date] => 2006-11-30
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 5
[patent_figures_cnt] => 5
[patent_no_of_words] => 4283
[patent_no_of_claims] => 12
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 0
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0258/20070258556.pdf
[firstpage_image] =>[orig_patent_app_number] => 11606104
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/606104 | Annular nuclear fuel rod controllable in heat fluxes of inner and outer tubes | Nov 29, 2006 | Abandoned |
Array
(
[id] => 4823811
[patent_doc_number] => 20080123794
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2008-05-29
[patent_title] => 'Systems and methods of predicting a critical effective k for a nuclear reactor'
[patent_app_type] => utility
[patent_app_number] => 11/606320
[patent_app_country] => US
[patent_app_date] => 2006-11-29
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 6
[patent_figures_cnt] => 6
[patent_no_of_words] => 9814
[patent_no_of_claims] => 28
[patent_no_of_ind_claims] => 5
[patent_words_short_claim] => 0
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0123/20080123794.pdf
[firstpage_image] =>[orig_patent_app_number] => 11606320
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/606320 | Systems and methods of predicting a critical effective k for a nuclear reactor | Nov 28, 2006 | Issued |
Array
(
[id] => 4466029
[patent_doc_number] => 07881421
[patent_country] => US
[patent_kind] => B2
[patent_issue_date] => 2011-02-01
[patent_title] => 'Accumulator'
[patent_app_type] => utility
[patent_app_number] => 11/564046
[patent_app_country] => US
[patent_app_date] => 2006-11-28
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 8
[patent_figures_cnt] => 15
[patent_no_of_words] => 5174
[patent_no_of_claims] => 3
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 202
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/07/881/07881421.pdf
[firstpage_image] =>[orig_patent_app_number] => 11564046
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/564046 | Accumulator | Nov 27, 2006 | Issued |
Array
(
[id] => 7594390
[patent_doc_number] => 07627074
[patent_country] => US
[patent_kind] => B2
[patent_issue_date] => 2009-12-01
[patent_title] => 'Vertical spring wedge'
[patent_app_type] => utility
[patent_app_number] => 11/585183
[patent_app_country] => US
[patent_app_date] => 2006-10-24
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 4
[patent_figures_cnt] => 8
[patent_no_of_words] => 1985
[patent_no_of_claims] => 10
[patent_no_of_ind_claims] => 2
[patent_words_short_claim] => 168
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/07/627/07627074.pdf
[firstpage_image] =>[orig_patent_app_number] => 11585183
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/585183 | Vertical spring wedge | Oct 23, 2006 | Issued |
Array
(
[id] => 4784466
[patent_doc_number] => 20080137795
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2008-06-12
[patent_title] => 'METHOD AND APPARATUS FOR REMOVING CORROSION PRODUCTS FROM A NUCLEAR REACTOR'
[patent_app_type] => utility
[patent_app_number] => 11/551325
[patent_app_country] => US
[patent_app_date] => 2006-10-20
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 5
[patent_figures_cnt] => 5
[patent_no_of_words] => 2561
[patent_no_of_claims] => 11
[patent_no_of_ind_claims] => 2
[patent_words_short_claim] => 0
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0137/20080137795.pdf
[firstpage_image] =>[orig_patent_app_number] => 11551325
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/551325 | METHOD AND APPARATUS FOR REMOVING CORROSION PRODUCTS FROM A NUCLEAR REACTOR | Oct 19, 2006 | Abandoned |
Array
(
[id] => 134622
[patent_doc_number] => 07702060
[patent_country] => US
[patent_kind] => B2
[patent_issue_date] => 2010-04-20
[patent_title] => 'Expanded nuclear fuel channel'
[patent_app_type] => utility
[patent_app_number] => 11/583789
[patent_app_country] => US
[patent_app_date] => 2006-10-20
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 4
[patent_figures_cnt] => 4
[patent_no_of_words] => 1318
[patent_no_of_claims] => 6
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 129
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/07/702/07702060.pdf
[firstpage_image] =>[orig_patent_app_number] => 11583789
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/583789 | Expanded nuclear fuel channel | Oct 19, 2006 | Issued |
Array
(
[id] => 4784469
[patent_doc_number] => 20080137798
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2008-06-12
[patent_title] => 'Tube-in-tube threaded dashpot end plug'
[patent_app_type] => utility
[patent_app_number] => 11/583466
[patent_app_country] => US
[patent_app_date] => 2006-10-18
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 5
[patent_figures_cnt] => 5
[patent_no_of_words] => 4349
[patent_no_of_claims] => 18
[patent_no_of_ind_claims] => 3
[patent_words_short_claim] => 0
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0137/20080137798.pdf
[firstpage_image] =>[orig_patent_app_number] => 11583466
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/583466 | Tube-in-tube threaded dashpot end plug | Oct 17, 2006 | Issued |
Array
(
[id] => 4692186
[patent_doc_number] => 20080084957
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2008-04-10
[patent_title] => 'Nuclear reactor fuel assemblies'
[patent_app_type] => utility
[patent_app_number] => 11/544697
[patent_app_country] => US
[patent_app_date] => 2006-10-06
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 7
[patent_figures_cnt] => 7
[patent_no_of_words] => 4523
[patent_no_of_claims] => 9
[patent_no_of_ind_claims] => 5
[patent_words_short_claim] => 0
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0084/20080084957.pdf
[firstpage_image] =>[orig_patent_app_number] => 11544697
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/544697 | Nuclear reactor fuel assemblies | Oct 5, 2006 | Abandoned |
Array
(
[id] => 4939638
[patent_doc_number] => 20080076957
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2008-03-27
[patent_title] => 'Method of producing europium-152 and uses therefor'
[patent_app_type] => utility
[patent_app_number] => 11/527288
[patent_app_country] => US
[patent_app_date] => 2006-09-26
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 4
[patent_figures_cnt] => 4
[patent_no_of_words] => 5467
[patent_no_of_claims] => 26
[patent_no_of_ind_claims] => 4
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[patent_maintenance] => 1
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[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0076/20080076957.pdf
[firstpage_image] =>[orig_patent_app_number] => 11527288
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/527288 | Method of producing europium-152 and uses therefor | Sep 25, 2006 | Abandoned |
Array
(
[id] => 6219293
[patent_doc_number] => 20100054388
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2010-03-04
[patent_title] => 'Sealing Means, Transfer Device Comprising Such a Sealing Means, Arrangement Comprising Such a Transfer Device and a Method for Producing Said Sealing Means'
[patent_app_type] => utility
[patent_app_number] => 11/992688
[patent_app_country] => US
[patent_app_date] => 2006-09-25
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 7
[patent_figures_cnt] => 7
[patent_no_of_words] => 3626
[patent_no_of_claims] => 9
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 0
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0054/20100054388.pdf
[firstpage_image] =>[orig_patent_app_number] => 11992688
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/992688 | Sealing means, transfer device comprising such a sealing means, arrangement comprising such a transfer device and a method for producing said sealing means | Sep 24, 2006 | Issued |
Array
(
[id] => 5373172
[patent_doc_number] => 20090310732
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2009-12-17
[patent_title] => 'Method for manufacturing a pressure vessel of a pressurized-water reactor of a nuclear power station a pressure vessel of a pressurized-water reactor of a nuclear power station and use of a multiwalled pressure vessel for the above purpose'
[patent_app_type] => utility
[patent_app_number] => 11/518847
[patent_app_country] => US
[patent_app_date] => 2006-09-11
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 5
[patent_figures_cnt] => 5
[patent_no_of_words] => 3734
[patent_no_of_claims] => 9
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[patent_current_assignee] =>[type] => publication
[pdf_file] => publications/A1/0310/20090310732.pdf
[firstpage_image] =>[orig_patent_app_number] => 11518847
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/518847 | Method for manufacturing a pressure vessel of a pressurized-water reactor of a nuclear power station a pressure vessel of a pressurized-water reactor of a nuclear power station and use of a multiwalled pressure vessel for the above purpose | Sep 10, 2006 | Abandoned |
Array
(
[id] => 331705
[patent_doc_number] => 07512206
[patent_country] => US
[patent_kind] => B2
[patent_issue_date] => 2009-03-31
[patent_title] => 'Batch target and method for producing radionuclide'
[patent_app_type] => utility
[patent_app_number] => 11/512654
[patent_app_country] => US
[patent_app_date] => 2006-08-29
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 4
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[patent_no_of_words] => 7651
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[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/07/512/07512206.pdf
[firstpage_image] =>[orig_patent_app_number] => 11512654
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/512654 | Batch target and method for producing radionuclide | Aug 28, 2006 | Issued |
Array
(
[id] => 6287835
[patent_doc_number] => 20100158185
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2010-06-24
[patent_title] => 'METHOD AND APPARATUS OF ESTIMATING DRYOUT PROPERTIES IN A NUCLEAR LIGHT WATER REACTOR'
[patent_app_type] => utility
[patent_app_number] => 11/512938
[patent_app_country] => US
[patent_app_date] => 2006-08-29
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 2
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[pdf_file] => publications/A1/0158/20100158185.pdf
[firstpage_image] =>[orig_patent_app_number] => 11512938
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/512938 | Method and apparatus of estimating dryout properties in a nuclear light water reactor | Aug 28, 2006 | Issued |
Array
(
[id] => 4601969
[patent_doc_number] => 07978808
[patent_country] => US
[patent_kind] => B1
[patent_issue_date] => 2011-07-12
[patent_title] => 'Method of providing a nuclear fuel and a fuel element provided by such a method'
[patent_app_type] => utility
[patent_app_number] => 11/507457
[patent_app_country] => US
[patent_app_date] => 2006-08-22
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 0
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[patent_no_of_words] => 2092
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[pdf_file] => patents/07/978/07978808.pdf
[firstpage_image] =>[orig_patent_app_number] => 11507457
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/507457 | Method of providing a nuclear fuel and a fuel element provided by such a method | Aug 21, 2006 | Issued |
Array
(
[id] => 5033591
[patent_doc_number] => 20070098130
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2007-05-03
[patent_title] => 'Production of thorium-229 from thorium-230'
[patent_app_type] => utility
[patent_app_number] => 11/507152
[patent_app_country] => US
[patent_app_date] => 2006-08-21
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 0
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[patent_no_of_words] => 2668
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[pdf_file] => publications/A1/0098/20070098130.pdf
[firstpage_image] =>[orig_patent_app_number] => 11507152
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/507152 | Production of thorium-229 from thorium-230 | Aug 20, 2006 | Abandoned |
| 11/506580 | Production of thorium-229 using helium nuclei | Aug 17, 2006 | Abandoned |
Array
(
[id] => 77187
[patent_doc_number] => 07751522
[patent_country] => US
[patent_kind] => B2
[patent_issue_date] => 2010-07-06
[patent_title] => 'Covering element for a reactor core of a nuclear installation, and nuclear reactor'
[patent_app_type] => utility
[patent_app_number] => 11/500035
[patent_app_country] => US
[patent_app_date] => 2006-08-07
[patent_effective_date] => 0000-00-00
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[pdf_file] => patents/07/751/07751522.pdf
[firstpage_image] =>[orig_patent_app_number] => 11500035
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/500035 | Covering element for a reactor core of a nuclear installation, and nuclear reactor | Aug 6, 2006 | Issued |
Array
(
[id] => 5530526
[patent_doc_number] => 20090230314
[patent_country] => US
[patent_kind] => A1
[patent_issue_date] => 2009-09-17
[patent_title] => 'GAMMA SOURCE FOR ACTIVE INTERROGATION'
[patent_app_type] => utility
[patent_app_number] => 11/462999
[patent_app_country] => US
[patent_app_date] => 2006-08-07
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[firstpage_image] =>[orig_patent_app_number] => 11462999
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/462999 | Gamma source for active interrogation | Aug 6, 2006 | Issued |
Array
(
[id] => 5396787
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[patent_kind] => A1
[patent_issue_date] => 2009-12-24
[patent_title] => 'Generating short-term criticality in a sub-critical reactor'
[patent_app_type] => utility
[patent_app_number] => 11/482327
[patent_app_country] => US
[patent_app_date] => 2006-07-07
[patent_effective_date] => 0000-00-00
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[firstpage_image] =>[orig_patent_app_number] => 11482327
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/482327 | Generating short-term criticality in a sub-critical reactor | Jul 6, 2006 | Abandoned |
Array
(
[id] => 7999763
[patent_doc_number] => 08081729
[patent_country] => US
[patent_kind] => B2
[patent_issue_date] => 2011-12-20
[patent_title] => 'Heat exchanger assembly, in particular for a high-temperature nuclear reactor'
[patent_app_type] => utility
[patent_app_number] => 11/993763
[patent_app_country] => US
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[pdf_file] => patents/08/081/08081729.pdf
[firstpage_image] =>[orig_patent_app_number] => 11993763
[rel_patent_id] =>[rel_patent_doc_number] =>) 11/993763 | Heat exchanger assembly, in particular for a high-temperature nuclear reactor | Jun 21, 2006 | Issued |