
Daniel D Wasil
Examiner (ID: 11765, Phone: (571)272-4654 , Office: P/3646 )
| Most Active Art Unit | 2204 |
| Art Unit(s) | 3646, 3641, 2201, 1806, 3642, 2204, 3724 |
| Total Applications | 2259 |
| Issued Applications | 1925 |
| Pending Applications | 102 |
| Abandoned Applications | 253 |
Applications
| Application number | Title of the application | Filing Date | Status |
|---|---|---|---|
Array
(
[id] => 2470312
[patent_doc_number] => 04827953
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1989-05-09
[patent_title] => 'Flexible lance for steam generator secondary side sludge removable'
[patent_app_type] => 1
[patent_app_number] => 7/027810
[patent_app_country] => US
[patent_app_date] => 1987-03-18
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 6
[patent_figures_cnt] => 15
[patent_no_of_words] => 2663
[patent_no_of_claims] => 11
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 191
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/827/04827953.pdf
[firstpage_image] =>[orig_patent_app_number] => 027810
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/027810 | Flexible lance for steam generator secondary side sludge removable | Mar 17, 1987 | Issued |
Array
(
[id] => 2484199
[patent_doc_number] => 04801421
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1989-01-31
[patent_title] => 'On-line monitoring and analysis of reactor vessel integrity'
[patent_app_type] => 1
[patent_app_number] => 7/026501
[patent_app_country] => US
[patent_app_date] => 1987-03-16
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 9
[patent_figures_cnt] => 12
[patent_no_of_words] => 9140
[patent_no_of_claims] => 29
[patent_no_of_ind_claims] => 6
[patent_words_short_claim] => 139
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/801/04801421.pdf
[firstpage_image] =>[orig_patent_app_number] => 026501
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/026501 | On-line monitoring and analysis of reactor vessel integrity | Mar 15, 1987 | Issued |
Array
(
[id] => 2415837
[patent_doc_number] => 04747996
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-05-31
[patent_title] => 'Apparatus and method for adjusting the elevation of fuel rods in a nuclear reactor fuel assembly'
[patent_app_type] => 1
[patent_app_number] => 7/023496
[patent_app_country] => US
[patent_app_date] => 1987-03-09
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 1
[patent_figures_cnt] => 4
[patent_no_of_words] => 2946
[patent_no_of_claims] => 4
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 365
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/747/04747996.pdf
[firstpage_image] =>[orig_patent_app_number] => 023496
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/023496 | Apparatus and method for adjusting the elevation of fuel rods in a nuclear reactor fuel assembly | Mar 8, 1987 | Issued |
Array
(
[id] => 2510736
[patent_doc_number] => 04818473
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1989-04-04
[patent_title] => 'Fuel bundle'
[patent_app_type] => 1
[patent_app_number] => 7/020190
[patent_app_country] => US
[patent_app_date] => 1987-02-26
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 4
[patent_figures_cnt] => 14
[patent_no_of_words] => 2338
[patent_no_of_claims] => 11
[patent_no_of_ind_claims] => 5
[patent_words_short_claim] => 196
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/818/04818473.pdf
[firstpage_image] =>[orig_patent_app_number] => 020190
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/020190 | Fuel bundle | Feb 25, 1987 | Issued |
Array
(
[id] => 2381602
[patent_doc_number] => 04783308
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-11-08
[patent_title] => 'Boiling water reactor fuel rod'
[patent_app_type] => 1
[patent_app_number] => 7/020159
[patent_app_country] => US
[patent_app_date] => 1987-02-26
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 3
[patent_figures_cnt] => 6
[patent_no_of_words] => 3369
[patent_no_of_claims] => 8
[patent_no_of_ind_claims] => 2
[patent_words_short_claim] => 207
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/783/04783308.pdf
[firstpage_image] =>[orig_patent_app_number] => 020159
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/020159 | Boiling water reactor fuel rod | Feb 25, 1987 | Issued |
| 07/018406 | METHOD AND APPARATUS FOR LOADING A BALL-BED NUCLEAR REACTOR | Feb 24, 1987 | Abandoned |
Array
(
[id] => 2483939
[patent_doc_number] => 04800062
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1989-01-24
[patent_title] => 'On-site concrete cask storage system for spent nuclear fuel'
[patent_app_type] => 1
[patent_app_number] => 7/029097
[patent_app_country] => US
[patent_app_date] => 1987-02-23
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 3
[patent_figures_cnt] => 7
[patent_no_of_words] => 2968
[patent_no_of_claims] => 8
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 112
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/800/04800062.pdf
[firstpage_image] =>[orig_patent_app_number] => 029097
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/029097 | On-site concrete cask storage system for spent nuclear fuel | Feb 22, 1987 | Issued |
Array
(
[id] => 2449907
[patent_doc_number] => 04765944
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-08-23
[patent_title] => 'Device for the transverse retention of a movable tubular conduit in a pressurized water nuclear reactor'
[patent_app_type] => 1
[patent_app_number] => 7/010595
[patent_app_country] => US
[patent_app_date] => 1987-02-03
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 3
[patent_figures_cnt] => 4
[patent_no_of_words] => 2924
[patent_no_of_claims] => 4
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 281
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/765/04765944.pdf
[firstpage_image] =>[orig_patent_app_number] => 010595
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/010595 | Device for the transverse retention of a movable tubular conduit in a pressurized water nuclear reactor | Feb 2, 1987 | Issued |
Array
(
[id] => 2416970
[patent_doc_number] => 04734251
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-03-29
[patent_title] => 'Multi-gripper handling apparatus with individual force limiter'
[patent_app_type] => 1
[patent_app_number] => 7/005891
[patent_app_country] => US
[patent_app_date] => 1987-01-22
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 1
[patent_figures_cnt] => 1
[patent_no_of_words] => 3176
[patent_no_of_claims] => 4
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 266
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/734/04734251.pdf
[firstpage_image] =>[orig_patent_app_number] => 005891
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/005891 | Multi-gripper handling apparatus with individual force limiter | Jan 21, 1987 | Issued |
Array
(
[id] => 2441127
[patent_doc_number] => 04744940
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-05-17
[patent_title] => 'Apparatus for compacting nuclear reactor fuel rods'
[patent_app_type] => 1
[patent_app_number] => 7/004609
[patent_app_country] => US
[patent_app_date] => 1987-01-20
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 7
[patent_figures_cnt] => 17
[patent_no_of_words] => 5296
[patent_no_of_claims] => 5
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 120
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/744/04744940.pdf
[firstpage_image] =>[orig_patent_app_number] => 004609
[rel_patent_id] =>[rel_patent_doc_number] =>) 07/004609 | Apparatus for compacting nuclear reactor fuel rods | Jan 19, 1987 | Issued |
Array
(
[id] => 2415817
[patent_doc_number] => 04747995
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-05-31
[patent_title] => 'Velocity limiter shear for BWR control rods'
[patent_app_type] => 1
[patent_app_number] => 6/943824
[patent_app_country] => US
[patent_app_date] => 1986-12-29
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 2
[patent_figures_cnt] => 2
[patent_no_of_words] => 739
[patent_no_of_claims] => 4
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 188
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/747/04747995.pdf
[firstpage_image] =>[orig_patent_app_number] => 943824
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/943824 | Velocity limiter shear for BWR control rods | Dec 28, 1986 | Issued |
Array
(
[id] => 2537090
[patent_doc_number] => 04826654
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1989-05-02
[patent_title] => 'Fuel assembly'
[patent_app_type] => 1
[patent_app_number] => 6/946960
[patent_app_country] => US
[patent_app_date] => 1986-12-29
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 7
[patent_figures_cnt] => 12
[patent_no_of_words] => 4223
[patent_no_of_claims] => 13
[patent_no_of_ind_claims] => 3
[patent_words_short_claim] => 202
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/826/04826654.pdf
[firstpage_image] =>[orig_patent_app_number] => 946960
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/946960 | Fuel assembly | Dec 28, 1986 | Issued |
Array
(
[id] => 2484216
[patent_doc_number] => 04801422
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1989-01-31
[patent_title] => 'Apparatus for installing and removing a control rod drive in a nuclear reactor'
[patent_app_type] => 1
[patent_app_number] => 6/945842
[patent_app_country] => US
[patent_app_date] => 1986-12-23
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 8
[patent_figures_cnt] => 19
[patent_no_of_words] => 3562
[patent_no_of_claims] => 21
[patent_no_of_ind_claims] => 5
[patent_words_short_claim] => 186
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/801/04801422.pdf
[firstpage_image] =>[orig_patent_app_number] => 945842
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/945842 | Apparatus for installing and removing a control rod drive in a nuclear reactor | Dec 22, 1986 | Issued |
| 06/943675 | DRY STORAGE ARRANGEMENTS FOR NUCLEAR FUEL | Dec 16, 1986 | Abandoned |
Array
(
[id] => 2420180
[patent_doc_number] => 04762664
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-08-09
[patent_title] => 'Method and apparatus for compacting spent nuclear reactor fuel rods'
[patent_app_type] => 1
[patent_app_number] => 6/941155
[patent_app_country] => US
[patent_app_date] => 1986-12-12
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 7
[patent_figures_cnt] => 22
[patent_no_of_words] => 6436
[patent_no_of_claims] => 25
[patent_no_of_ind_claims] => 2
[patent_words_short_claim] => 187
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/762/04762664.pdf
[firstpage_image] =>[orig_patent_app_number] => 941155
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/941155 | Method and apparatus for compacting spent nuclear reactor fuel rods | Dec 11, 1986 | Issued |
Array
(
[id] => 2449963
[patent_doc_number] => 04765947
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-08-23
[patent_title] => 'Probe guide duct device for a nuclear reactor'
[patent_app_type] => 1
[patent_app_number] => 6/939833
[patent_app_country] => US
[patent_app_date] => 1986-12-09
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 3
[patent_figures_cnt] => 3
[patent_no_of_words] => 1457
[patent_no_of_claims] => 5
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 275
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/765/04765947.pdf
[firstpage_image] =>[orig_patent_app_number] => 939833
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/939833 | Probe guide duct device for a nuclear reactor | Dec 8, 1986 | Issued |
Array
(
[id] => 2543838
[patent_doc_number] => 04804514
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1989-02-14
[patent_title] => 'Method and apparatus for neutron dosimetry'
[patent_app_type] => 1
[patent_app_number] => 6/939834
[patent_app_country] => US
[patent_app_date] => 1986-12-09
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 4
[patent_figures_cnt] => 4
[patent_no_of_words] => 4169
[patent_no_of_claims] => 19
[patent_no_of_ind_claims] => 4
[patent_words_short_claim] => 88
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/804/04804514.pdf
[firstpage_image] =>[orig_patent_app_number] => 939834
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/939834 | Method and apparatus for neutron dosimetry | Dec 8, 1986 | Issued |
Array
(
[id] => 2448843
[patent_doc_number] => 04759912
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-07-26
[patent_title] => 'BWR fuel assembly having hybrid fuel design'
[patent_app_type] => 1
[patent_app_number] => 6/939929
[patent_app_country] => US
[patent_app_date] => 1986-12-09
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 5
[patent_figures_cnt] => 7
[patent_no_of_words] => 2820
[patent_no_of_claims] => 14
[patent_no_of_ind_claims] => 3
[patent_words_short_claim] => 87
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/759/04759912.pdf
[firstpage_image] =>[orig_patent_app_number] => 939929
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/939929 | BWR fuel assembly having hybrid fuel design | Dec 8, 1986 | Issued |
Array
(
[id] => 2409860
[patent_doc_number] => 04725398
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-02-16
[patent_title] => 'Cable reeving system'
[patent_app_type] => 1
[patent_app_number] => 6/939678
[patent_app_country] => US
[patent_app_date] => 1986-12-08
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 3
[patent_figures_cnt] => 5
[patent_no_of_words] => 2645
[patent_no_of_claims] => 4
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 421
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/725/04725398.pdf
[firstpage_image] =>[orig_patent_app_number] => 939678
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/939678 | Cable reeving system | Dec 7, 1986 | Issued |
Array
(
[id] => 2441604
[patent_doc_number] => 04749541
[patent_country] => US
[patent_kind] => NA
[patent_issue_date] => 1988-06-07
[patent_title] => 'Position sensing mechanism for a nuclear fuel transfer system'
[patent_app_type] => 1
[patent_app_number] => 6/938662
[patent_app_country] => US
[patent_app_date] => 1986-12-05
[patent_effective_date] => 0000-00-00
[patent_drawing_sheets_cnt] => 7
[patent_figures_cnt] => 8
[patent_no_of_words] => 4377
[patent_no_of_claims] => 20
[patent_no_of_ind_claims] => 1
[patent_words_short_claim] => 165
[patent_maintenance] => 1
[patent_no_of_assignments] => 0
[patent_current_assignee] =>[type] => patent
[pdf_file] => patents/04/749/04749541.pdf
[firstpage_image] =>[orig_patent_app_number] => 938662
[rel_patent_id] =>[rel_patent_doc_number] =>) 06/938662 | Position sensing mechanism for a nuclear fuel transfer system | Dec 4, 1986 | Issued |