Search

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 numberTitle of the applicationFiling DateStatus
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 [patent_words_short_claim] => 0 [patent_maintenance] => 1 [patent_no_of_assignments] => 0 [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 [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/A1/0310/20090310732.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 [patent_figures_cnt] => 4 [patent_no_of_words] => 7651 [patent_no_of_claims] => 13 [patent_no_of_ind_claims] => 2 [patent_words_short_claim] => 140 [patent_maintenance] => 1 [patent_no_of_assignments] => 0 [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 [patent_figures_cnt] => 2 [patent_no_of_words] => 8348 [patent_no_of_claims] => 30 [patent_no_of_ind_claims] => 4 [patent_words_short_claim] => 0 [patent_maintenance] => 1 [patent_no_of_assignments] => 0 [patent_current_assignee] =>[type] => publication [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 [patent_figures_cnt] => 0 [patent_no_of_words] => 2092 [patent_no_of_claims] => 18 [patent_no_of_ind_claims] => 2 [patent_words_short_claim] => 88 [patent_maintenance] => 1 [patent_no_of_assignments] => 0 [patent_current_assignee] =>[type] => patent [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 [patent_figures_cnt] => 0 [patent_no_of_words] => 2668 [patent_no_of_claims] => 7 [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/A1/0098/20070098130.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 [patent_drawing_sheets_cnt] => 3 [patent_figures_cnt] => 4 [patent_no_of_words] => 3189 [patent_no_of_claims] => 19 [patent_no_of_ind_claims] => 1 [patent_words_short_claim] => 110 [patent_maintenance] => 1 [patent_no_of_assignments] => 0 [patent_current_assignee] =>[type] => patent [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 [patent_effective_date] => 0000-00-00 [patent_drawing_sheets_cnt] => 7 [patent_figures_cnt] => 7 [patent_no_of_words] => 3100 [patent_no_of_claims] => 14 [patent_no_of_ind_claims] => 9 [patent_words_short_claim] => 0 [patent_maintenance] => 1 [patent_no_of_assignments] => 0 [patent_current_assignee] =>[type] => publication [pdf_file] => publications/A1/0230/20090230314.pdf [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 [patent_doc_number] => 20090316850 [patent_country] => US [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 [patent_drawing_sheets_cnt] => 3 [patent_figures_cnt] => 3 [patent_no_of_words] => 3241 [patent_no_of_claims] => 29 [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/A1/0316/20090316850.pdf [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 [patent_app_date] => 2006-06-22 [patent_effective_date] => 0000-00-00 [patent_drawing_sheets_cnt] => 11 [patent_figures_cnt] => 17 [patent_no_of_words] => 8362 [patent_no_of_claims] => 25 [patent_no_of_ind_claims] => 1 [patent_words_short_claim] => 240 [patent_maintenance] => 1 [patent_no_of_assignments] => 0 [patent_current_assignee] =>[type] => patent [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
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