National Library of Energy BETA

Sample records for 2051-55p year shipped

  1. LANL shatters records in first year of accelerated shipping effort

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    LANL shatters records in first year of accelerated shipping effort LANL shatters records in first year of accelerated shipping effort LANL set a record for transuranic waste shipments from the Lab to permanent disposal facilities. October 3, 2012 Los Alamos National Laboratory set a record for transuranic waste shipments from the Laboratory to permanent disposal facilities, sending nearly 60 more shipments than originally planned. Los Alamos National Laboratory set a record for transuranic waste

  2. LANL sets waste shipping record for fourth consecutive year

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    LANL Sets Waste Shipping Record Community Connections: Your link to news and opportunities from Los Alamos National Laboratory Latest Issue: September 1, 2016 all issues All Issues » submit LANL sets waste shipping record for fourth consecutive year The Laboratory has transported more than 1,000 shipments to WIPP since that facility opened in 1999. September 1, 2012 dummy image Read our archives Contacts Editor Linda Anderman Email Community Programs Office Kurt Steinhaus Email Our goal this

  3. LANL Sets Waste Shipping Record for Fourth Consecutive Year: Lab has sent

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    172 shipments so far this year; aiming for 200 by September 30 | Department of Energy Sets Waste Shipping Record for Fourth Consecutive Year: Lab has sent 172 shipments so far this year; aiming for 200 by September 30 LANL Sets Waste Shipping Record for Fourth Consecutive Year: Lab has sent 172 shipments so far this year; aiming for 200 by September 30 August 14, 2012 - 12:00pm Addthis Los Alamos National Laboratory has set another record for shipments of transuranic waste in a single fiscal

  4. LANL shatters records in first year of accelerated shipping effort

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    695-6167 Email "Our goal this fiscal year was to send 184 shipments to WIPP," said Lee Bishop, TRU waste manager at the U.S. DOE's NNSA Los Alamos Site Office, "and we finished the...

  5. Aging Study Of EPDM O-Ring Material For The H1616 Shipping Package - Three Year Status

    SciTech Connect (OSTI)

    Stefek, T.; Daugherty, W.; Skidmore, E.

    2015-11-05

    This is a 3-year status report for tasks carried out per Task Technical Plan SRNL-STI-2011-00506. A series of tasks/experiments were performed at the Savannah River National Laboratory (SRNL) to monitor the aging performance of ethylene propylene diene monomer (EPDM) O-rings used in the H1616 shipping package. The test data provide a technical basis to extend the annual maintenance of the H1616 shipping package to three years and to predict the life of the EPDM O-rings at the bounding service conditions.

  6. Shipping and Receiving

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shipping and Receiving Print On this page: Transport Policy Shipping to the ALS Shipping from the ALS Shipping Hazardous Materials Contacts: ALS Shipping & Receiving (small packages) LBNL Shipping & Receiving (large packages requiring forklift truck) Building 7 Hours: M-F, 7:30 am-4:30 pm Telephone: 510 486 4494 Building 69 Hours: M-F, 7:00 am-3:30 pm Telephone: 510 486 4935 Fax: 510 486 5668 Transport Policy - Getting Your Samples and Equipment to and from the ALS All Lab personnel,

  7. Shipping and Receiving

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shipping and Receiving Print On this page: Transport Policy Shipping to the ALS Shipping from the ALS Shipping Hazardous Materials Contacts: ALS Shipping & Receiving (small packages) LBNL Shipping & Receiving (large packages requiring forklift truck) Building 7 Hours: M-F, 7:30 am-4:30 pm Telephone: 510 486 4494 Building 69 Hours: M-F, 7:00 am-3:30 pm Telephone: 510 486 4935 Fax: 510 486 5668 Transport Policy - Getting Your Samples and Equipment to and from the ALS All Lab personnel,

  8. Shipping and Receiving

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shipping and Receiving Print On this page: Transport Policy Shipping to the ALS Shipping from the ALS Shipping Hazardous Materials Contacts: ALS Shipping & Receiving (small packages) LBNL Shipping & Receiving (large packages requiring forklift truck) Building 7 Hours: M-F, 7:30 am-4:30 pm Telephone: 510 486 4494 Building 69 Hours: M-F, 7:00 am-3:30 pm Telephone: 510 486 4935 Fax: 510 486 5668 Transport Policy - Getting Your Samples and Equipment to and from the ALS All Lab personnel,

  9. Shipping and Receiving

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shipping and Receiving Print On this page: Transport Policy Shipping to the ALS Shipping from the ALS Shipping Hazardous Materials Contacts: ALS Shipping & Receiving (small packages) LBNL Shipping & Receiving (large packages requiring forklift truck) Building 7 Hours: M-F, 7:30 am-4:30 pm Telephone: 510 486 4494 Building 69 Hours: M-F, 7:00 am-3:30 pm Telephone: 510 486 4935 Fax: 510 486 5668 Transport Policy - Getting Your Samples and Equipment to and from the ALS All Lab personnel,

  10. Shipping and Receiving

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... Shipping materials to Cuba, Iran, Libya, North Korea, Sudan, and Syria is prohibited; contact Berkeley Lab Procurement for more information. Arranging Transport Several independent ...

  11. Domestic Shipping with Portunus

    SciTech Connect (OSTI)

    Sutton, F. G.

    2015-08-18

    This report considers shipping options in the United States and presents a case study on ports in southern California to identify variables that might affect cost.

  12. Shipping - 88-Inch Cyclotron

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    To ship equipment to the BASE Facility, send it to the following address: To: Mike Johnson (3rd Party No PO) Lawrence Berkeley National Laboratory 1 Cyclotron Rd, Bldg 88...

  13. Shipping Materials | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shipping Materials General Users are not permitted to transport hazardous material on the Argonne site or to arrange for shipment directly to the CNM. Hazardous materials must be processed through Argonne's hazardous materials receiving area. Inbound Shipments Before you ship anything to the CNM, you must notify the User Office and your CNM contact. Nonhazardous Material To ensure that samples and equipment that you ship to the CNM gets here without unnecessary delays, address your shipments as

  14. Progress Update: TRU Waste Shipping

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14

    A progress update at the Savannah River Site. A continued effort on shipping TRU waste to WIPP in Carlsbad, New Mexico.

  15. YEAR

    National Nuclear Security Administration (NNSA)

    69 YEAR 2014 Males 34 Females 35 YEAR 2014 SES 5 EJEK 1 EN 05 8 EN 04 5 NN (Engineering) 27 NQ (ProfTechAdmin) 22 NU (TechAdmin Support) 1 YEAR 2014 American Indian Alaska...

  16. YEAR

    National Nuclear Security Administration (NNSA)

    42 YEAR 2014 Males 36 Females 6 PAY PLAN YEAR 2014 SES 2 EJEK 5 EN 05 7 EN 04 6 EN 03 1 NN (Engineering) 15 NQ (ProfTechAdmin) 6 YEAR 2014 American Indian Alaska Native Male...

  17. YEAR

    National Nuclear Security Administration (NNSA)

    4 YEAR 2012 Males 65 Females 29 YEAR 2012 SES 3 EJEK 5 EN 04 3 NN (Engineering) 21 NQ (ProfTechAdmin) 61 NU (TechAdmin Support) 1 YEAR 2012 American Indian Male 0 American...

  18. YEAR

    National Nuclear Security Administration (NNSA)

    4 YEAR 2011 Males 21 Females 23 YEAR 2011 SES 3 EJEK 1 EN 03 1 NN (Engineering) 3 NQ (ProfTechAdmin) 31 NU (TechAdmin Support) 5 YEAR 2011 American Indian Male 0 American...

  19. YEAR

    National Nuclear Security Administration (NNSA)

    92 YEAR 2012 Males 52 Females 40 YEAR 2012 SES 1 EJEK 7 EN 04 13 EN 03 1 NN (Engineering) 27 NQ (ProfTechAdmin) 38 NU (TechAdmin Support) 5 YEAR 2012 American Indian Male 0...

  20. YEAR

    National Nuclear Security Administration (NNSA)

    558 YEAR 2013 Males 512 Females 46 YEAR 2013 SES 2 EJEK 2 EN 04 1 NN (Engineering) 11 NQ (ProfTechAdmin) 220 NU (TechAdmin Support) 1 NV (Nuc Mat Courier) 321 YEAR 2013...

  1. YEAR

    National Nuclear Security Administration (NNSA)

    11 YEAR 2012 Males 78 Females 33 YEAR 2012 SES 2 EJEK 9 EN 05 1 EN 04 33 NN (Engineering) 32 NQ (ProfTechAdmin) 31 NU (TechAdmin Support) 3 YEAR 2012 American Indian Male 2...

  2. YEAR

    National Nuclear Security Administration (NNSA)

    300 YEAR 2011 Males 109 Females 191 YEAR 2011 SES 9 EJEK 1 NN (Engineering) 2 NQ (ProfTechAdmin) 203 NU (TechAdmin Support) 38 NF (Future Ldrs) 47 YEAR 2011 American Indian...

  3. YEAR

    National Nuclear Security Administration (NNSA)

    02 YEAR 2011 Males 48 Females 54 YEAR 2011 SES 5 EJEK 1 NN (Engineering) 13 NQ (ProfTechAdmin) 80 NU (TechAdmin Support) 3 YEAR 2011 American Indian Male 0 American Indian...

  4. YEAR

    National Nuclear Security Administration (NNSA)

    8 YEAR 2013 Males 27 Females 11 YEAR 2013 SES 1 EN 05 1 EN 04 11 NN (Engineering) 8 NQ (ProfTechAdmin) 15 NU (TechAdmin Support) 2 YEAR 2013 American Indian Alaska Native Male...

  5. YEAR

    National Nuclear Security Administration (NNSA)

    31 YEAR 2013 Males 20 Females 11 YEAR 2013 SES 2 EN 04 4 NN (Engineering) 12 NQ (ProfTechAdmin) 12 NU (TechAdmin Support) 1 YEAR 2013 American Indian Alaska Native Male (AIAN,...

  6. YEAR

    National Nuclear Security Administration (NNSA)

    16 YEAR 2012 Males 84 Females 32 YEAR 2012 SES 26 EJEK 2 EN 05 9 NN (Engineering) 39 NQ (ProfTechAdmin) 30 NU (TechAdmin Support) 10 YEAR 2012 American Indian Male 0 American...

  7. YEAR

    National Nuclear Security Administration (NNSA)

    34 YEAR 2012 Males 66 Females 68 YEAR 2012 SES 6 NN (Engineering) 15 NQ (ProfTechAdmin) 110 NU (TechAdmin Support) 3 YEAR 2012 American Indian Male 1 American Indian Female 2...

  8. YEAR

    National Nuclear Security Administration (NNSA)

    86 YEAR 2012 Males 103 Females 183 YEAR 2012 SES 7 EJEK 1 NN (Engineering) 1 NQ (ProfTechAdmin) 202 NU (TechAdmin Support) 30 NF (Future Ldrs) 45 YEAR 2012 American Indian Male...

  9. YEAR

    National Nuclear Security Administration (NNSA)

    80 YEAR 2012 Males 51 Females 29 YEAR 2012 SES 1 EJEK 22 EN 04 21 NN (Engineering) 14 NQ (ProfTechAdmin) 21 NU (TechAdmin Support) 1 YEAR 2012 American Indian Male 0 American...

  10. YEAR

    National Nuclear Security Administration (NNSA)

    1 YEAR 2012 Males 30 Females 11 YEAR 2012 SES 1 EN 05 1 EN 04 11 NN (Engineering) 9 NQ (ProfTechAdmin) 17 NU (TechAdmin Support) 2 YEAR 2012 American Indian Male 0 American...

  11. YEAR

    National Nuclear Security Administration (NNSA)

    96 YEAR 2013 Males 69 Females 27 YEAR 2013 SES 1 EJEK 9 EN 04 27 NN (Engineering) 26 NQ (ProfTechAdmin) 30 NU (TechAdmin Support) 3 YEAR 2013 American Indian Alaska Native Male...

  12. YEAR

    National Nuclear Security Administration (NNSA)

    31 YEAR 2012 Males 19 Females 12 YEAR 2012 SES 2 EN 04 4 NN (Engineering) 12 NQ (ProfTechAdmin) 12 NU (TechAdmin Support) 1 YEAR 2012 American Indian Male 0 American Indian...

  13. YEAR

    National Nuclear Security Administration (NNSA)

    0 YEAR 2013 Males 48 Females 32 YEAR 2013 SES 2 EJEK 7 EN 04 11 EN 03 1 NN (Engineering) 23 NQ (ProfTechAdmin) 33 NU (TechAdmin Support) 3 YEAR 2013 American Indian Alaska...

  14. YEAR

    National Nuclear Security Administration (NNSA)

    40 YEAR 2011 Males 68 Females 72 YEAR 2011 SES 5 EJEK 1 NN (Engineering) 16 NQ (ProfTechAdmin) 115 NU (TechAdmin Support) 3 YEAR 2011 American Indian Male 1 American Indian...

  15. YEAR

    National Nuclear Security Administration (NNSA)

    00 YEAR 2012 Males 48 Females 52 YEAR 2012 SES 5 EJEK 1 NN (Engineering) 11 NQ (ProfTechAdmin) 80 NU (TechAdmin Support) 3 YEAR 2012 American Indian Male 0 American Indian...

  16. YEAR

    National Nuclear Security Administration (NNSA)

    137 YEAR 2013 Males 90 Females 47 YEAR 2013 SES 2 SL 1 EJEK 30 EN 04 30 EN 03 2 NN (Engineering) 23 NQ (ProfTechAdmin) 45 NU (TechAdmin Support) 4 YEAR 2013 American Indian...

  17. YEAR

    National Nuclear Security Administration (NNSA)

    of Employees 14 GENDER YEAR 2012 Males 9 Females 5 YEAR 2012 SES 2 EJEK 2 NN (Engineering) 4 NQ (ProfTechAdmin) 6 YEAR 2012 American Indian Male 0 American Indian Female 0...

  18. YEAR

    National Nuclear Security Administration (NNSA)

    3 YEAR 2012 Males 21 Females 22 YEAR 2012 SES 3 EJEK 1 EN 03 1 NN (Engineering) 3 NQ (ProfTechAdmin) 30 NU (TechAdmin Support) 5 YEAR 2012 American Indian Male 0 American...

  19. YEAR

    National Nuclear Security Administration (NNSA)

    Males 139 Females 88 YEAR 2012 SES 13 EX 1 EJEK 8 EN 05 23 EN 04 20 EN 03 2 NN (Engineering) 91 NQ (ProfTechAdmin) 62 NU (TechAdmin Support) 7 YEAR 2012 American Indian...

  20. YEAR

    National Nuclear Security Administration (NNSA)

    26 YEAR 2014 Males 81 Females 45 PAY PLAN YEAR 2014 SES 1 SL1 EJEK 25 EN 04 26 EN 03 2 NN (Engineering) 23 NQ (ProfTechAdmin) 44 NU (TechAdmin Support) 4 YEAR 2014 American ...

  1. YEAR

    National Nuclear Security Administration (NNSA)

    563 YEAR 2012 Males 518 Females 45 YEAR 2012 SES 1 EJEK 2 EN 04 1 EN 03 1 NN (Engineering) 12 NQ (ProfTechAdmin) 209 NU (TechAdmin Support) 2 NV (Nuc Mat Courier) 335 YEAR 2012...

  2. YEAR

    National Nuclear Security Administration (NNSA)

    7 YEAR 2012 Males 64 Females 33 YEAR 2012 SES 2 EJEK 3 EN 05 1 EN 04 30 EN 03 1 NN (Engineering) 26 NQ (ProfTechAdmin) 32 NU (TechAdmin Support) 2 YEAR 2012 American Indian...

  3. YEAR

    National Nuclear Security Administration (NNSA)

    4 YEAR 2012 Males 37 Females 7 YEAR 2012 SES 1 EJEK 6 EN 05 5 EN 04 7 EN 03 1 NN (Engineering) 17 NQ (ProfTechAdmin) 6 NU (TechAdmin Support) 1 YEAR 2012 American Indian Male 2...

  4. YEAR

    National Nuclear Security Administration (NNSA)

    7 YEAR 2011 Males 38 Females 9 YEAR 2011 SES 1 EJEK 6 EN 05 5 EN 04 7 EN 03 1 NN (Engineering) 19 NQ (ProfTechAdmin) 7 NU (TechAdmin Support) 1 YEAR 2011 American Indian Male 2...

  5. YEAR

    National Nuclear Security Administration (NNSA)

    8 YEAR 2013 Males 62 Females 26 YEAR 2013 SES 1 EJEK 3 EN 05 1 EN 04 28 EN 03 1 NN (Engineering) 25 NQ (ProfTechAdmin) 27 NU (TechAdmin Support) 2 YEAR 2013 American Indian...

  6. YEAR

    National Nuclear Security Administration (NNSA)

    6 YEAR 2012 Males 64 Females 32 YEAR 2012 SES 1 EJEK 5 EN 05 3 EN 04 23 EN 03 9 NN (Engineering) 18 NQ (ProfTechAdmin) 33 NU (TechAdmin Support) 4 YEAR 2012 American Indian...

  7. YEAR

    National Nuclear Security Administration (NNSA)

    5 YEAR 2013 Males 58 Females 27 YEAR 2013 SES 1 EJEK 4 EN 05 3 EN 04 21 EN 03 8 NN (Engineering) 16 NQ (ProfTechAdmin) 28 NU (TechAdmin Support) 4 YEAR 2013 American Indian...

  8. YEAR

    National Nuclear Security Administration (NNSA)

    78 YEAR 2012 Males 57 Females 21 YEAR 2012 SES 2 SL 1 EJEK 12 EN 04 21 EN 03 2 NN (Engineering) 12 NQ (ProfTechAdmin) 24 NU (TechAdmin Support) 4 YEAR 2012 American Indian Male...

  9. YEAR

    National Nuclear Security Administration (NNSA)

    2012 Males 149 Females 115 YEAR 2012 SES 17 EX 1 EJEK 7 EN 05 2 EN 04 9 EN 03 2 NN (Engineering) 56 NQ (ProfTechAdmin) 165 NU (TechAdmin Support) 4 GS 13 1 YEAR 2012 American...

  10. YEAR

    National Nuclear Security Administration (NNSA)

    5 YEAR 2014 Males 61 Females 24 PAY PLAN YEAR 2014 SES 1 EJ/EK 8 EN 04 22 NN (Engineering) 23 NQ (Prof/Tech/Admin) 28 NU (Tech/Admin Support) 3 YEAR 2014 American Indian Alaska Native Male (AIAN M) 2 American Indian Alaskan Native Female (AIAN F) 3 African American Male (AA M) 0 African American Female (AA F) 0 Asian American Pacific Islander Male (AAPI M) 3 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 13 Hispanic Female (H F) 10 White Male (W M) 43 White Female (W F) 11

  11. YEAR

    National Nuclear Security Administration (NNSA)

    2 YEAR 2014 Males 57 Females 25 PAY PLAN YEAR 2014 SES 3 EJ/EK 4 EN 04 2 NN (Engineering) 20 NQ (Prof/Tech/Admin) 53 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 0 African American Male (AA M) 9 African American Female (AA F) 9 Asian American Pacific Islander Male (AAPI M) 2 Asian American Pacific Islander Female (AAPI F) 1 Hispanic Male (H M) 3 Hispanic Female (H F) 5 White Male (W M) 43 White Female (W F) 10 DIVERSITY TOTAL WORKFORCE

  12. YEAR

    National Nuclear Security Administration (NNSA)

    93 YEAR 2014 Males 50 Females 43 PAY PLAN YEAR 2014 EJ/EK 3 NN (Engineering) 13 NQ (Prof/Tech/Admin) 74 NU (Tech/Admin Support) 3 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 2 African American Male (AA M) 5 African American Female (AA F) 6 Asian American Pacific Islander Male (AAPI M) 0 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 6 Hispanic Female (H F) 14 White Male (W M) 39 White Female (W F) 21 DIVERSITY

  13. YEAR

    National Nuclear Security Administration (NNSA)

    YEAR 2014 Males 11 Females 2 PAY PLAN YEAR 2014 SES 2 EJ/EK 1 EN 04 1 NN (Engineering) 5 NQ (Prof/Tech/Admin) 4 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 0 African American Male (AA M) 0 African American Female (AA F) 0 Asian American Pacific Islander Male (AAPI M) 1 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 0 Hispanic Female (H F) 0 White Male (W M) 10 White Female (W F) 2 DIVERSITY TOTAL WORKFORCE GENDER

  14. YEAR

    National Nuclear Security Administration (NNSA)

    9 YEAR 2014 Males 9 Females 10 YEAR 2014 SES 7 ED 1 EJ/EK 1 EN 05 1 NQ (Prof/Tech/Admin) 8 NU (Tech/Admin Support) 1 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 1 African American Female (AA F) 5 Asian American Pacific Islander Male (AAPI M) 1 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 0 Hispanic Female (H F) 3 White Male (W M) 7 White Female (W F) 1 PAY PLAN DIVERSITY TOTAL

  15. YEAR

    National Nuclear Security Administration (NNSA)

    5 YEAR 2014 Males 92 Females 43 YEAR 2014 SES 8 EX 1 EJ/EK 4 EN 05 9 EN 04 12 EN 03 2 NN (Engineering) 57 NQ (Prof/Tech/Admin) 42 YEAR 2014 American Indian Alaska Native Male (AIAN M) 1 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 9 African American Female (AA F) 11 Asian American Pacific Islander Male (AAPI M) 4 Asian American Pacific Islander Female (AAPI F) 2 Hispanic Male (H M) 12 Hispanic Female (H F) 7 White Male (W M) 66 White Female (W F) 22 PAY PLAN

  16. YEAR

    National Nuclear Security Administration (NNSA)

    563 YEAR 2014 Males 517 Females 46 PAY PLAN YEAR 2014 SES 2 EJ/EK 2 EN 04 1 NN (Engineering) 11 NQ (Prof/Tech/Admin) 218 NU (Tech/Admin Support) 2 NV (Nuc Mat Courier) 327 YEAR 2014 American Indian Alaska Native Male (AIAN M) 14 American Indian Alaskan Native Female (AIAN F) 2 African American Male (AA M) 18 African American Female (AA F) 1 Asian American Pacific Islander Male (AAPI M) 8 Asian American Pacific Islander Female (AAPI F) 2 Hispanic Male (H M) 76 Hispanic Female (H F) 21 White Male

  17. YEAR

    National Nuclear Security Administration (NNSA)

    89 YEAR 2014 Males 98 Females 91 PAY PLAN YEAR 2014 SES 14 EX 1 EJ/EK 3 EN 05 1 EN 04 4 EN 03 1 NN (Engineering) 32 NQ (Prof/Tech/Admin) 130 NU (Tech/Admin Support) 2 GS 15 1 YEAR 2014 American Indian Alaska Native Male (AIAN M) 1 American Indian Alaskan Native Female (AIAN F) 0 African American Male (AA M) 5 African American Female (AA F) 14 Asian American Pacific Islander Male (AAPI M) 3 Asian American Pacific Islander Female (AAPI F) 7 Hispanic Male (H M) 7 Hispanic Female (H F) 10 White Male

  18. YEAR

    National Nuclear Security Administration (NNSA)

    3 YEAR 2014 Males 162 Females 81 PAY PLAN YEAR 2014 SES 26 EJ/EK 3 EN 05 7 NN (Engineering) 77 NQ (Prof/Tech/Admin) 108 NU (Tech/Admin Support) 22 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 5 African American Female (AA F) 9 Asian American Pacific Islander Male (AAPI M) 1 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 2 Hispanic Female (H F) 0 White Male (W M) 154 White Female (W F)

  19. YEAR

    National Nuclear Security Administration (NNSA)

    74 YEAR 2014 Males 96 Females 78 PAY PLAN YEAR 2014 SES 8 EJ/EK 4 EN 04 11 EN 03 1 NN (Engineering) 34 NQ (Prof/Tech/Admin) 113 NU (Tech/Admin Support) 3 YEAR 2014 American Indian Alaska Native Male (AIAN M) 2 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 3 African American Female (AA F) 11 Asian American Pacific Islander Male (AAPI M) 5 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 25 Hispanic Female (H F) 25 White Male (W M) 61 White

  20. YEAR

    National Nuclear Security Administration (NNSA)

    4 YEAR 2014 Males 7 Females 7 PAY PLAN YEAR 2014 SES 1 NQ (Prof/Tech/Admin) 7 GS 15 1 GS 14 2 GS 13 2 GS 10 1 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 0 African American Male (AA M) 3 African American Female (AA F) 2 Asian American Pacific Islander Male (AAPI M) 0 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 0 Hispanic Female (H F) 0 White Male (W M) 4 White Female (W F) 5 DIVERSITY TOTAL WORKFORCE GENDER

  1. YEAR

    National Nuclear Security Administration (NNSA)

    16 YEAR 2014 Males 72 Females 144 PAY PLAN YEAR 2014 SES 8 EJ/EK 1 NQ (Prof/Tech/Admin) 198 NU (Tech/Admin Support) 9 YEAR 2014 American Indian Alaska Native Male (AIAN M) 2 American Indian Alaskan Native Female (AIAN F) 2 African American Male (AA M) 10 African American Female (AA F) 38 Asian American Pacific Islander Male (AAPI M) 1 Asian American Pacific Islander Female (AAPI F) 3 Hispanic Male (H M) 15 Hispanic Female (H F) 33 White Male (W M) 44 White Female (W F) 68 DIVERSITY TOTAL

  2. YEAR

    National Nuclear Security Administration (NNSA)

    26 YEAR 2014 Males 81 Females 45 PAY PLAN YEAR 2014 SES 1 SL 1 EJ/EK 25 EN 04 26 EN 03 2 NN (Engineering) 23 NQ (Prof/Tech/Admin) 44 NU (Tech/Admin Support) 4 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 3 African American Female (AA F) 7 Asian American Pacific Islander Male (AAPI M) 4 Asian American Pacific Islander Female (AAPI F) 1 Hispanic Male (H M) 6 Hispanic Female (H F) 6 White Male (W M) 68 White

  3. YEAR

    National Nuclear Security Administration (NNSA)

    446 YEAR 2014 Males 1626 Females 820 YEAR 2014 SES 97 EX 2 ED 1 SL 1 EJ/EK 84 EN 05 38 EN 04 162 EN 03 18 NN (Engineering) 427 NQ (Prof/Tech/Admin) 1216 NU (Tech/Admin Support) 66 NV (Nuc Mat Courier) 327 GS 15 2 GS 14 2 GS 13 2 GS 10 1 YEAR 2014 American Indian Alaska Native Male (AIAN M) 27 American Indian Alaskan Native Female (AIAN F) 24 African American Male (AA M) 90 African American Female (AA F) 141 Asian American Pacific Islander Male (AAPI M) 63 Asian American Pacific Islander Female

  4. YEAR

    National Nuclear Security Administration (NNSA)

    1 YEAR 2014 Males 48 Females 33 PAY PLAN YEAR 2014 SES 1 EJ/EK 8 EN 04 10 EN 03 1 NN (Engineering) 27 NQ (Prof/Tech/Admin) 29 NU (Tech/Admin Support) 5 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 3 African American Male (AA M) 0 African American Female (AA F) 2 Asian American Pacific Islander Male (AAPI M) 2 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 12 Hispanic Female (H F) 12 White Male (W M) 34 White Female

  5. YEAR

    National Nuclear Security Administration (NNSA)

    8 YEAR 2014 Males 18 Females 10 PAY PLAN YEAR 2014 SES 1 EN 05 1 EN 04 4 NN (Engineering) 12 NQ (Prof/Tech/Admin) 9 NU (Tech/Admin Support) 1 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 4 African American Female (AA F) 4 Asian American Pacific Islander Male (AAPI M) 1 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 0 Hispanic Female (H F) 0 White Male (W M) 13 White Female (W F) 5

  6. YEAR

    National Nuclear Security Administration (NNSA)

    8 YEAR 2014 Males 18 Females 20 PAY PLAN YEAR 2014 SES 3 EJ/EK 1 EN 03 1 NN (Engineering) 3 NQ (Prof/Tech/Admin) 28 NU (Tech/Admin Support) 2 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 0 African American Male (AA M) 1 African American Female (AA F) 1 Asian American Pacific Islander Male (AAPI M) 0 Asian American Pacific Islander Female (AAPI F) 1 Hispanic Male (H M) 4 Hispanic Female (H F) 7 White Male (W M) 13 White Female (W F) 11

  7. YEAR

    National Nuclear Security Administration (NNSA)

    White Male (W M) 26 White Female (W F) 16 DIVERSITY TOTAL WORKFORCE GENDER Livermore Field ... YEARS OF FEDERAL SERVICE SUPERVISOR RATIO AGE Livermore Field Office As of March 22, 2014 ...

  8. YEAR

    National Nuclear Security Administration (NNSA)

    25 Females 10 YEAR 2014 SES 1 EN 04 11 NN (Engineering) 8 NQ (Prof/Tech/Admin) 13 NU (Tech/Admin Support) 2 YEAR 2014 American Indian Alaska Native Male (AIAN M) 0 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 1 African American Female (AA F) 3 Asian American Pacific Islander Male (AAPI M) 0 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 0 Hispanic Female (H F) 0 White Male (W M) 24 White Female (W F) 6 TOTAL WORKFORCE GENDER Kansas City

  9. YEAR

    National Nuclear Security Administration (NNSA)

    9 Females 24 PAY PLAN YEAR 2014 SES 1 EJ/EK 4 EN 05 3 EN 04 22 EN 03 8 NN (Engineering) 15 NQ (Prof/Tech/Admin) 27 NU (Tech/Admin Support) 3 YEAR 2014 American Indian Alaska Native Male (AIAN M) 2 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 5 African American Female (AA F) 2 Asian American Pacific Islander Male (AAPI M) 21 Asian American Pacific Islander Female (AAPI F) 2 Hispanic Male (H M) 5 Hispanic Female (H F) 3 White Male (W M) 26 White Female (W F) 16

  10. YEAR

    National Nuclear Security Administration (NNSA)

    17 Females 18 PAY PLAN YEAR 2014 SES 1 EJ/EK 3 NQ (Prof/Tech/Admin) 30 NU (Tech/Admin Support) 1 YEAR 2014 American Indian Alaska Native Male (AIAN M) 1 American Indian Alaskan Native Female (AIAN F) 2 African American Male (AA M) 3 African American Female (AA F) 7 Asian American Pacific Islander Male (AAPI M) 1 Asian American Pacific Islander Female (AAPI F) 0 Hispanic Male (H M) 2 Hispanic Female (H F) 6 White Male (W M) 10 White Female (W F) 3 DIVERSITY TOTAL WORKFORCE GENDER Associate

  11. YEAR

    National Nuclear Security Administration (NNSA)

    8 Females 25 PAY PLAN YEAR 2014 SES 1 EJ/EK 3 EN 05 1 EN 04 25 EN 03 1 NN (Engineering) 25 NQ (Prof/Tech/Admin) 25 NU (Tech/Admin Support) 2 YEAR 2014 American Indian Alaska Native Male (AIAN M) 1 American Indian Alaskan Native Female (AIAN F) 1 African American Male (AA M) 3 African American Female (AA F) 3 Asian American Pacific Islander Male (AAPI M) 2 Asian American Pacific Islander Female (AAPI F) 2 Hispanic Male (H M) 6 Hispanic Female (H F) 6 White Male (W M) 46 White Female (W F) 13

  12. YEAR

    National Nuclear Security Administration (NNSA)

    -9.09% YEAR 2012 2013 SES 1 1 0.00% EN 05 1 1 0.00% EN 04 11 11 0.00% NN (Engineering) 8 8 0.00% NQ (ProfTechAdmin) 17 14 -17.65% NU (TechAdmin Support) 2 2...

  13. YEAR

    National Nuclear Security Administration (NNSA)

    Females 863 YEAR 2013 SES 102 EX 3 SL 1 EJEK 89 EN 05 41 EN 04 170 EN 03 18 NN (Engineering) 448 NQ (ProfTechAdmin) 1249 NU (TechAdmin Support) 76 NV (Nuc Mat Courier) 321...

  14. YEAR

    National Nuclear Security Administration (NNSA)

    Females 942 YEAR 2012 SES 108 EX 4 SL 1 EJEK 96 EN 05 45 EN 04 196 EN 03 20 NN (Engineering) 452 NQ (ProfTechAdmin) 1291 NU (TechAdmin Support) 106 NV (Nuc Mat Courier) 335...

  15. YEAR

    National Nuclear Security Administration (NNSA)

    YEAR 2012 2013 SES 2 1 -50.00% EN 05 0 1 100.00% EN 04 4 4 0.00% NN (Engineering) 13 12 -7.69% NQ (ProfTechAdmin) 13 9 -30.77% NU (TechAdmin Support) 1 1...

  16. ADAPTING A CERTIFIED SHIPPING PACKAGE FOR STORAGE APPLICATIONS

    SciTech Connect (OSTI)

    Loftin, B.; Abramczyk, G.

    2012-06-05

    For years shipping packages have been used to store radioactive materials at many DOE sites. Recently, the K-Area Material Storage facility at the Savannah River Site became interested in and approved the Model 9977 Shipping Package for use as a storage package. In order to allow the 9977 to be stored in the facility, there were a number of evaluations and modifications that were required. There were additional suggested modifications to improve the performance of the package as a storage container that were discussed but not incorporated in the design that is currently in use. This paper will discuss the design being utilized for shipping and storage, suggested modifications that have improved the storage configuration but were not used, as well as modifications that have merit for future adaptations for both the 9977 and for other shipping packages to be used as storage packages.

  17. MODEL 9975 SHIPPING PACKAGE FABRICATION PROBLEMS AND SOLUTIONS

    SciTech Connect (OSTI)

    May, C; Allen Smith, A

    2008-05-07

    The Model 9975 Shipping Package is the latest in a series (9965, 9968, etc.) of radioactive material shipping packages that have been the mainstay for shipping radioactive materials for several years. The double containment vessels are relatively simple designs using pipe and pipe cap in conjunction with the Chalfont closure to provide a leak-tight vessel. The fabrication appears simple in nature, but the history of fabrication tells us there are pitfalls in the different fabrication methods and sequences. This paper will review the problems that have arisen during fabrication and precautions that should be taken to meet specifications and tolerances. The problems and precautions can also be applied to the Models 9977 and 9978 Shipping Packages.

  18. Shipping container for fissile material

    DOE Patents [OSTI]

    Crowder, H.E.

    1984-12-17

    The present invention is directed to a shipping container for the interstate transportation of enriched uranium materials. The shipping container is comprised of a rigid, high-strength, cylindrical-shaped outer vessel lined with thermal insulation. Disposed inside the thermal insulation and spaced apart from the inner walls of the outer vessel is a rigid, high-strength, cylindrical inner vessel impervious to liquid and gaseous substances and having the inner surfaces coated with a layer of cadmium to prevent nuclear criticality. The cadmium is, in turn, lined with a protective shield of high-density urethane for corrosion and wear protection. 2 figs.

  19. LNG demand, shipping will expand through 2010

    SciTech Connect (OSTI)

    True, W.R.

    1998-02-09

    The 1990s, especially the middle years, have witnessed a dramatic turnaround in the growth of liquefied-natural-gas demand which has tracked equally strong natural-gas demand growth. This trend was underscored late last year by several annual studies of world LNG demand and shipping. As 1998 began, however, economic turmoil in Asian financial markets has clouded near-term prospects for LNG in particular and all energy in general. But the extent of damage to energy markets is so far unclear. A study by US-based Institute of Gas Technology, Des Plaines, IL, reveals that LNG imports worldwide have climbed nearly 8%/year since 1980 and account for 25% of all natural gas traded internationally. In the mid-1970s, the share was only 5%. In 1996, the most recent year for which complete data are available, world LNG trade rose 7.7% to a record 92 billion cu m, outpacing the overall consumption for natural gas which increased 4.7% in 1996. By 2015, says the IGT study, natural-gas use would surpass coal as the world`s second most widely used fuel, after petroleum. Much of this growth will occur in the developing countries of Asia where gas use, before the current economic crisis began, was projected to grow 8%/year through 2015. Similar trends are reflected in another study of LNG trade released at year end 1997, this from Ocean Shipping Consultants Ltd., Surrey, U.K. The study was done too early, however, to consider the effects of the financial problems roiling Asia.

  20. ARM: Ship navigational location and attitude: Position and Heading...

    Office of Scientific and Technical Information (OSTI)

    Ship navigational location and attitude: Position and Heading Data Title: ARM: Ship navigational location and attitude: Position and Heading Data Ship navigational location and ...

  1. Shipping Radioactive Waste by Rail from Brookhaven National Laboratory...

    Office of Environmental Management (EM)

    Shipping Radioactive Waste by Rail from Brookhaven National Laboratory Shipping Radioactive Waste by Rail from Brookhaven National Laboratory Shipping Radioactive Waste by Rail ...

  2. Shipping and Receiving Services | The Ames Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shipping and Receiving Services General Information: Shipping and Receiving services are provided for Ames Laboratory personnel. The warehouse facility on Kooser Dr. is operated by the Materials and Transportation group. Daily on-site deliveries are made of gases, inbound express mail, credit card and purchase order packages. Shipping Address for ALL packages to Ames Laboratory: Ames Lab. DOE Warehouse % (your name)/building/room ISU Campus, 2416 Pammel Dr. Ames, IA 50011-2416 Services: Shipping

  3. SHIPPING CONTAINER FOR RADIOACTIVE MATERIAL

    DOE Patents [OSTI]

    Nachbar, H.D.; Biggs, B.B.; Tariello, P.J.; George, K.O.

    1963-01-15

    A shipping container is described for transponting a large number of radioactive nuclear fuel element modules which produce a substantial amount of heat. The container comprises a primary pressure vessel and shield, and a rotatable head having an access port that can be indexed with module holders in the container. In order to remove heat generated in the fuel eleme nts, a heat exchanger is arranged within the container and in contact with a heat exchange fluid therein. The heat exchanger communicates with additional external heat exchangers, which dissipate heat to the atmosphere. (AEC)

  4. Los Alamos National Laboratory ships

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ships last of high-activity drums to WIPP November 25, 2008 LOS ALAMOS, New Mexico, November 25, 2008- The last group of unvented high- activity drums left Los Alamos National Laboratory for the Waste Isolation Pilot Plant (WIPP) near Carlsbad earlier this month. "This is a significant achievement for the Laboratory," said Mark Shepard of Los Alamos's Waste Disposition Project. "It closes a chapter on the February 2007 commitment to the Defense Nuclear Facilities Safety Board to

  5. Shipping Cask Design Review Analysis.

    Energy Science and Technology Software Center (OSTI)

    1998-01-04

    Version 01 SCANS (Shipping Cask ANalysis System) is a microcomputer based system of computer programs and databases for evaluating safety analysis reports on spent fuel shipping casks. SCANS calculates the global response to impact loads, pressure loads, and thermal conditions, providing reviewers with an independent check on analyses submitted by licensees. Analysis options are based on regulatory cases described in the Code of Federal Regulations (1983) and Regulatory Guides published by the NRC in 1977more » and 1978. The system is composed of a series of menus and input entry cask analysis, and output display programs. An analysis is performed by preparing the necessary input data and then selecting the appropriate analysis: impact, thermal (heat transfer), thermally-induced stress, or pressure-induced stress. All data are entered through input screens with descriptive data requests, and, where possible, default values are provided. Output (i.e., impact force, moment and sheer time histories; impact animation; thermal/stress geometry and thermal/stress element outlines; temperature distributions as isocontours or profiles; and temperature time histories) is displayed graphically and can also be printed.« less

  6. Los Alamos exceeds waste shipping goal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped more than 3,000 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste headed to the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste headed to the Waste Isolation Pilot Plant in southeastern New Mexico.

  7. Los Alamos exceeds waste shipping goal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot

  8. Los Alamos exceeds waste shipping goal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot

  9. SNF shipping cask shielding analysis

    SciTech Connect (OSTI)

    Johnson, J.O.; Pace, J.V. III

    1996-01-01

    The Waste Management and Remedial Action Division has planned a modification sequence for storage facility 7827 in the Solid Waste Storage Area (SWSA). The modification cycle is: (1) modify an empty caisson, (2) transfer the spent nuclear fuel (SNF) of an occupied caisson to a hot cell in building 3525 for inspection and possible repackaging, and (3) return the package to the modified caisson in the SWSA. Although the SNF to be moved is in the solid form, it has different levels of activity. Thus, the following 5 shipping casks will be available for the task: the Loop Transport Carrier, the In- Pile Loop LITR HB-2 Carrier, the 6.5-inch HRLEL Carrier, the HFIR Hot Scrap Carrier, and the 10-inch ORR Experiment Removal Shield Cask. This report describes the shielding tasks for the 5 casks: determination of shielding characteristics, any streaming avenues, estimation of thermal limits, and shielding calculational uncertainty for use in the transportation plan.

  10. BALLISTICS TESTING OF THE 9977 SHIPPING PACKAGE FOR STORAGE APPLICATIONS

    SciTech Connect (OSTI)

    Loftin, B.; Abramczyk, G.; Koenig, R.

    2012-06-06

    Radioactive materials are stored in a variety of locations throughout the DOE complex. At the Savannah River Site (SRS), materials are stored within dedicated facilities. Each of those facilities has a documented safety analysis (DSA) that describes accidents that the facility and the materials within it may encounter. Facilities at the SRS are planning on utilizing the certified Model 9977 Shipping Package as a long term storage package and one of these facilities required ballistics testing. Specifically, in order to meet the facility DSA, the radioactive materials (RAM) must be contained within the storage package after impact by a .223 caliber round. In order to qualify the Model 9977 Shipping Package for storage in this location, the package had to be tested under these conditions. Over the past two years, the Model 9977 Shipping Package has been subjected to a series of ballistics tests. The purpose of the testing was to determine if the 9977 would be suitable for use as a storage package at a Savannah River Site facility. The facility requirements are that the package must not release any of its contents following the impact in its most vulnerable location by a .223 caliber round. A package, assembled to meet all of the design requirements for a certified 9977 shipping configuration and using simulated contents, was tested at the Savannah River Site in March of 2011. The testing was completed and the package was examined. The results of the testing and examination are presented in this paper.

  11. Express Package Shipping Services | The Ames Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Express Package Shipping Services General Information: The materials handling office's express package shipping service offers overnight domestic letter and parcel service for official business only. Express international shipments are also offered. Many hazardous and non-hazardous materials may be shipped by express. This service is provided to Ames Laboratory personnel. Hours: Monday through Friday - 7:30 a.m. to 11:50 a.m. - 12:30 p.m. through 4:00 p.m. Cutoff: for 10:30 a.m. next day

  12. Chongqing Shipping Construction Development Co Ltd | Open Energy...

    Open Energy Info (EERE)

    Shipping Construction Development Co Ltd Jump to: navigation, search Name: Chongqing Shipping Construction Development Co., Ltd. Place: Chongqing, Chongqing Municipality, China...

  13. New facility boosts Lab's ability to ship transuranic waste

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Lab's ability to ship transuranic waste New facility boosts Lab's ability to ship transuranic waste Construction has begun on a new facility that will help Los Alamos accelerate ...

  14. LANL sets waste shipping record for fourth consecutive year

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    184 shipments and we are on track to surpass that by a substantial margin," said Lee Bishop, TRU waste manager at the Department of Energy's Los Alamos Site Office. "We expect to...

  15. Ship dynamics for maritime ISAR imaging.

    SciTech Connect (OSTI)

    Doerry, Armin Walter

    2008-02-01

    Demand is increasing for imaging ships at sea. Conventional SAR fails because the ships are usually in motion, both with a forward velocity, and other linear and angular motions that accompany sea travel. Because the target itself is moving, this becomes an Inverse- SAR, or ISAR problem. Developing useful ISAR techniques and algorithms is considerably aided by first understanding the nature and characteristics of ship motion. Consequently, a brief study of some principles of naval architecture sheds useful light on this problem. We attempt to do so here. Ship motions are analyzed for their impact on range-Doppler imaging using Inverse Synthetic Aperture Radar (ISAR). A framework for analysis is developed, and limitations of simple ISAR systems are discussed.

  16. Global Volunteer Observing Ship (VOS) Program Data

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    CDIAC provides data management support for the Global Volunteer Observing Ship (VOS) Program. The VOS project is coordinated by the UNESCO International Ocean Carbon Coordination Project (IOCCP). The international groups from 14 countries have been outfitting research ships and commercial vessels with automated CO2 sampling equipment to analyze the carbon exchange between the ocean and atmosphere. [copied from http://cdiac.ornl.gov/oceans/genInfo.html] CDIAC provides a map interface with the shipping routes of the 14 countries involved marked in different colors. Clicking on the ship's name on that route brings up information about the vessel, the kinds of measurements collected and the timeframe, links to project pages, and, most important, the links to the data files themselves. The 14 countries are: United States, United Kingdom, Japan, France, Germany, Australia, Canada, Spain, Norway, New Zealand, China (including Taiwan), Iceland, and the Netherlands. Both archived and current, underway data can be accessed from the CDIAC VOS page.

  17. Radioactive materials shipping cask anticontamination enclosure

    DOE Patents [OSTI]

    Belmonte, Mark S.; Davis, James H.; Williams, David A.

    1982-01-01

    An anticontamination device for use in storing shipping casks for radioactive materials comprising (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

  18. Structural health monitoring for ship structures

    SciTech Connect (OSTI)

    Farrar, Charles; Park, Gyuhae; Angel, Marian; Bement, Matthew; Salvino, Liming

    2009-01-01

    Currently the Office of Naval Research is supporting the development of structural health monitoring (SHM) technology for U.S. Navy ship structures. This application is particularly challenging because of the physical size of these structures, the widely varying and often extreme operational and environmental conditions associated with these ships missions, lack of data from known damage conditions, limited sensing that was not designed specifically for SHM, and the management of the vast amounts of data that can be collected during a mission. This paper will first define a statistical pattern recognition paradigm for SHM by describing the four steps of (1) Operational Evaluation, (2) Data Acquisition, (3) Feature Extraction, and (4) Statistical Classification of Features as they apply to ship structures. Note that inherent in the last three steps of this process are additional tasks of data cleansing, compression, normalization and fusion. The presentation will discuss ship structure SHM challenges in the context of applying various SHM approaches to sea trials data measured on an aluminum multi-hull high-speed ship, the HSV-2 Swift. To conclude, the paper will discuss several outstanding issues that need to be addressed before SHM can make the transition from a research topic to actual field applications on ship structures and suggest approaches for addressing these issues.

  19. 9975 SHIPPING PACKAGE LIFE EXTENSION SURVEILLANCE PROGRAM RESULTS SUMMARY

    SciTech Connect (OSTI)

    Daugherty, W.; Dunn, K.; Hackney, B.; Hoffman, E.; Skidmore, E.

    2011-01-06

    Results from the 9975 Surveillance Program at the Savannah River Site (SRS) are summarized for justification to extend the life of the 9975 packages currently stored in the K-Area Materials Storage (KAMS) facility from 10 years to 15 years. This justification is established with the stipulation that surveillance activities will continue throughout this extended time to ensure the continued integrity of the 9975 materials of construction and to further understand the currently identified degradation mechanisms. The current 10 year storage life was developed prior to storage. A subsequent report was later used to extend the qualification of the 9975 shipping packages for 2 years for shipping plus 10 years for storage. However the qualification for the storage period was provided by the monitoring requirements of the Storage and Surveillance Program. This report summarizes efforts to determine a new safe storage limit for the 9975 shipping package based on the surveillance data collected since 2005 when the surveillance program began. KAMS is a zero-release facility that depends upon containment by the 9975 to meet design basis storage requirements. Therefore, to confirm the continued integrity of the 9975 packages while stored in KAMS, a 9975 Storage and Surveillance Program was implemented alongside the DOE required Integrated Surveillance Program (ISP) for 3013 plutonium-bearing containers. The 9975 Storage and Surveillance Program performs field surveillance as well as accelerated aging tests to ensure any degradation due to aging, to the extent that could affect packaging performance, is detected in advance of such degradation occurring in the field. The Program has demonstrated that the 9975 package has a robust design that can perform under a variety of conditions. As such the primary emphasis of the on-going 9975 Surveillance Program is an aging study of the 9975 Viton(reg.sign) GLT containment vessel O-rings and the Celotex(reg.sign) fiberboard thermal

  20. Microsoft Word - Shipping Info_2016.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shipping Information and Display Setup Prior to the Career Fair: Your displays and materials can be shipped to the following address; you should arrange for your packages to arrive no later than August 18th so there is no issue with receiving your shipment by the Career Fair: LANL Attn: Betsy Coronado/Mary Anne With Bikini Atoll Road, SM-30 MS M714 TA-00, Bldg. 199 Los Alamos, NM 87545-0001 Questions: Contact Mary Anne With at (505) 665-5306 or postdocprogram@lanl.gov. The displays and materials

  1. In Archive} Re: Number of ships at JBC

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Re: Number of ships at JBC Jeffrey Galan to: Maxcine Maxted 07/31/2015 06:02 PM Cc: Michael Dunsmuir History: This message has been forwarded. Archive: This message is being viewed in an archive. Hey Maxine, I spoke to my Joint Base Charleston contact and he told me that JBC gets an average of 8-10 vessels a year at Wharf Alpha and 35-45 vessels base wide. Jeff Galan Program Manager U.S.-Origin Nuclear Material Removal Program Office of Material Management and Minimization National Nuclear

  2. LEVERAGING AGING MATERIALS DATA TO SUPPORT EXTENSION OF TRANSPORTATION SHIPPING PACKAGES SERVICE LIFE

    SciTech Connect (OSTI)

    Dunn, K.; Bellamy, S.; Daugherty, W.; Sindelar, R.; Skidmore, E.

    2013-08-18

    Nuclear material inventories are increasingly being transferred to interim storage locations where they may reside for extended periods of time. Use of a shipping package to store nuclear materials after the transfer has become more common for a variety of reasons. Shipping packages are robust and have a qualified pedigree for performance in normal operation and accident conditions but are only certified over an approved transportation window. The continued use of shipping packages to contain nuclear material during interim storage will result in reduced overall costs and reduced exposure to workers. However, the shipping package materials of construction must maintain integrity as specified by the safety basis of the storage facility throughout the storage period, which is typically well beyond the certified transportation window. In many ways, the certification processes required for interim storage of nuclear materials in shipping packages is similar to life extension programs required for dry cask storage systems for commercial nuclear fuels. The storage of spent nuclear fuel in dry cask storage systems is federally-regulated, and over 1500 individual dry casks have been in successful service up to 20 years in the US. The uncertainty in final disposition will likely require extended storage of this fuel well beyond initial license periods and perhaps multiple re-licenses may be needed. Thus, both the shipping packages and the dry cask storage systems require materials integrity assessments and assurance of continued satisfactory materials performance over times not considered in the original evaluation processes. Test programs for the shipping packages have been established to obtain aging data on materials of construction to demonstrate continued system integrity. The collective data may be coupled with similar data for the dry cask storage systems and used to support extending the service life of shipping packages in both transportation and storage.

  3. Functions and requirements for K Basin SNF characterization shipping

    SciTech Connect (OSTI)

    Bergmann, D.W.

    1994-11-10

    This document details the plan for the shipping of fuel samples from the K Basins to the 300 Area for characterization. The fuel characterization project will evaluate the Hanford defense production fuel (N-Reactor and Single Pass Reactor) to support interim storage, transportation and final disposition. A limited number of fuel samples will be transported to a laboratory for analysis. It is currently estimated that 20 shipments of fuel per year for approximately 3 years (could be as long as 5 years) will be transported to the laboratory for analysis. Based on the NRC certificate of compliance each shipment is limited to 500 equivalent grams of {sup 235}U. In practical terms this will limit shipments to three outer elements or two assemblies of any type of N-Reactor or SPR fuel. Case by case determination of broken fuel will be made based on the type of fuel and maximum potential fissile content.

  4. Internal Corrosion Analysis of Model 9975 Packaging Containing Pu or PuO{sub 2} During Shipping and Storage

    SciTech Connect (OSTI)

    Vormelker, P.

    1999-03-23

    The Materials Consultation Group of SRTC has completed an internal corrosion analysis of the Model 9975 packaging assembly containing either Pu or PuO2 for storage in K Reactor under ambient conditions for a period of 12 years. The 12-year storage period includes two years for shipping and up to ten years for storage.

  5. Xergy Ships First Breakthrough Water Heater Compressor to GE...

    Energy Savers [EERE]

    Xergy Ships First Breakthrough Water Heater Compressor to GE Xergy Ships First Breakthrough Water Heater Compressor to GE September 15, 2015 - 3:41pm Addthis Xergy Inc. and GE...

  6. Technique for ship/wake detection

    DOE Patents [OSTI]

    Roskovensky, John K.

    2012-05-01

    An automated ship detection technique includes accessing data associated with an image of a portion of Earth. The data includes reflectance values. A first portion of pixels within the image are masked with a cloud and land mask based on spectral flatness of the reflectance values associated with the pixels. A given pixel selected from the first portion of pixels is unmasked when a threshold number of localized pixels surrounding the given pixel are not masked by the cloud and land mask. A spatial variability image is generated based on spatial derivatives of the reflectance values of the pixels which remain unmasked by the cloud and land mask. The spatial variability image is thresholded to identify one or more regions within the image as possible ship detection regions.

  7. DEPLOYMENT OF THE BULK TRITIUM SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Blanton, P.

    2013-10-10

    A new Bulk Tritium Shipping Package (BTSP) was designed by the Savannah River National Laboratory to be a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The BTSP was certified by the National Nuclear Safety Administration in 2011 for shipments of up to 150 grams of Tritium. Thirty packages were procured and are being delivered to various DOE sites for operational use. This paper summarizes the design features of the BTSP, as well as associated engineered material improvements. Fabrication challenges encountered during production are discussed as well as fielding requirements. Current approved tritium content forms (gas and tritium hydrides), are reviewed, as well as, a new content, tritium contaminated water on molecular sieves. Issues associated with gas generation will also be discussed.

  8. Los Alamos National Laboratory ships last of high-activity drums to WIPP

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ships last ff high-activity drums to WIPP Los Alamos National Laboratory ships last of high-activity drums to WIPP The November shipment was the final delivery this year to the Carlsbad plant, which is scheduled to undergo facility maintenance through mid-January. November 25, 2008 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy

  9. DEVELOPMENT OF THE BULK TRITIUM SHIPPING PACKAGING

    SciTech Connect (OSTI)

    Blanton, P.; Eberl, K.

    2008-09-14

    A new radioactive shipping packaging for transporting bulk quantities of tritium, the Bulk Tritium Shipping Package (BTSP), has been designed for the Department of Energy (DOE) as a replacement for a package designed in the early 1970s. This paper summarizes significant design features and describes how the design satisfies the regulatory safety requirements of the Code of Federal Regulations and the International Atomic Energy Agency. The BTSP design incorporates many improvements over its predecessor by implementing improved testing, handling, and maintenance capabilities, while improving manufacturability and incorporating new engineered materials. This paper also discusses the results from testing of the BTSP to 10 CFR 71 Normal Conditions of Transport and Hypothetical Accident Condition events. The programmatic need of the Department of Energy (DOE) to ship bulk quantities of tritium has been satisfied since the late 1970s by the UC-609 shipping package. The current Certificate of Conformance for the UC-609, USA/9932/B(U) (DOE), will expire in late 2011. Since the UC-609 was not designed to meet current regulatory requirements, it will not be recertified and thereby necessitates a replacement Type B shipping package for continued DOE tritium shipments in the future. A replacement tritium packaging called the Bulk Tritium Shipping Package (BTSP) is currently being designed and tested by Savannah River National Laboratory (SRNL). The BTSP consists of two primary assemblies, an outer Drum Assembly and an inner Containment Vessel Assembly (CV), both designed to mitigate damage and to protect the tritium contents from leaking during the regulatory Hypothetical Accident Condition (HAC) events and during Normal Conditions of Transport (NCT). During transport, the CV rests on a silicone pad within the Drum Liner and is covered with a thermal insulating disk within the insulated Drum Assembly. The BTSP packaging weighs approximately 500 lbs without contents and is 50

  10. DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-03431

    SciTech Connect (OSTI)

    Daugherty, W.

    2012-05-30

    Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-03431. For those attributes that were also measured during the field surveillance, no significant changes were observed. All observations and test results met identified criteria, or were collected for information and trending purposes. Except for modest corrosion of the lead shield (which is typical of these packages following several years service), no evidence of a degraded condition was found in this package. The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the KArea Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) credits the Model 9975 package to perform several safety functions, including criticality prevention, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program, destructive examination of package 9975-03431 was performed following field surveillance in accordance with Reference. Field surveillance of the Model 9975 package in KAC included nondestructive examination of the drum, fiberboard, lead shield and containment vessels. Results of the field surveillance are provided in Attachment 1.

  11. Radar imagery from the 1994 Lock Linnhe ship wake experiment

    SciTech Connect (OSTI)

    Mullenhoff, C.J.; Lehman, S.K.; Jones, H.

    1994-11-15

    The 1994 Loch Linnhe radar ocean imaging trials were held from September 4 through September 17. Two ships were used: the R.V. Colonel Templer, and the RMAS Collie. Thorn EMI, Inc., fielded a dual band, dual polarization radar on a hillside overlooking the loch. A primary purpose of the experiment was to obtain highly visible images of ship generated internal waves. Presented here is imagery for a few of the good ship runs, as well as a study of the environment of the visibility of ship generated internal waves.

  12. ANNUAL MAINTENANCE AND LEAK TESTING FOR THE 9975 SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Trapp, D.

    2014-08-25

    The purpose of this document is to provide step-by-step instructions for the annual helium leak test certification and maintenance of the 9975 Shipping Package.

  13. DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-02168

    SciTech Connect (OSTI)

    Daugherty, W.

    2010-11-18

    The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the K-Area Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) credits the Model 9975 package to perform several safety functions, including criticality prevention, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program, destructive examination of package 9975-02028 was performed following field surveillance in accordance with Reference. Field surveillance of the Model 9975 package in KAC included nondestructive examination of the drum, fiberboard, lead shield and containment vessels. Results of the field surveillance are provided in Attachment 1. Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-02168. For those attributes that were also measured during the field surveillance, no significant changes were observed. Two conditions were identified that do not meet inspection criteria. These conditions are subject to additional investigation and disposition by the Surveillance Program Authority. The conditions include: (1) The lead shield was covered with a white corrosion layer, and (2) Fiberboard thermal conductivity in the axial direction exceeded the specified range. The Surveillance Program Authority was notified of these conditions and will document the findings

  14. DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-02028

    SciTech Connect (OSTI)

    Daugherty, W.; Stefek, T.

    2009-12-30

    Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-02028. For those attributes that were also measured during the field surveillance, no significant changes were observed. Four conditions were identified that do not meet inspection criteria. These conditions are subject to additional investigation and disposition by the Surveillance Program Authority. The conditions include: (1) The lead shield was covered with a white corrosion layer; (2) The lead shield height exceeds drawing requirements; (3) Mold was observed on the lower fiberboard subassembly; and (4) Fiberboard thermal conductivity in the axial direction exceeded the specified range. The Surveillance Program Authority was notified of these conditions and will document the disposition by surveillance report. All other observations and test results met identified criteria, or were collected for information and trending purposes. The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the K-Area Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) credits the Model 9975 package to perform several safety functions, including criticality prevention, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program, destructive examination of package 9975-02028 was performed

  15. EXAMINATION OF SHIPPING PACKAGE 9975-05050

    SciTech Connect (OSTI)

    Daugherty, W.

    2014-11-06

    Shipping package 9975-05050 was examined in K-Area following its identification as a high wattage package. Elevated temperature and fiberboard moisture content are key parameters that impact the degradation rate of fiberboard within 9975 packages in a storage environment. The high wattage of this package contributes significantly to component temperatures. After examination in K-Area, the package was provided to SRNL for further examination of the fiberboard assembly. The moisture content of the fiberboard was relatively low (compared to packages examined previously), but the moisture gradient (between fiberboard ID and OD surfaces) was relatively high, as would be expected for the high heat load. The cane fiberboard appeared intact and displayed no apparent change in integrity relative to a new package.

  16. Ship-in-a-bottle catalysts

    DOE Patents [OSTI]

    Haw, James F.; Song, Weiguo

    2006-07-18

    In accordance with the present invention there is provided a novel catalyst system in which the catalytic structure is tailormade at the nanometer scale using the invention's novel ship-in-a-bottle synthesis techniques. The invention describes modified forms of solid catalysts for use in heterogeneous catalysis that have a microporous structure defined by nanocages. Examples include zeolites, SAPOs, and analogous materials that have the controlled pore dimensions and hydrothermal stability required for many industrial processes. The invention provides for modification of these catalysts using reagents that are small enough to pass through the windows used to access the cages. The small reagents are then reacted to form larger molecules in the cages.

  17. DEVELOPMENT OF THE H1700 SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Abramczyk, G.; Loftin, B.; Mann, P.

    2009-06-05

    The H1700 Package is based on the DOE-EM Certified 9977 Packaging. The H1700 will be certified by the Packaging Certification Division of the National Nuclear Security Administration for the shipment of plutonium by air by the United Stated Military both within the United States and internationally. The H1700 is designed to ship radioactive contents in assemblies of Radioisotope Thermoelectric Generators (RTGs) or arrangements of nested food-pack cans. The RTG containers are designed and tested to remain leaktight during transport, handling, and storage; however, their ability to remain leaktight during transport in the H1700 is not credited. This paper discusses the design and special operation of the H1700.

  18. Shipping device for heater unit assembly

    DOE Patents [OSTI]

    Blaushild, Ronald M.; Abbott, Stephan L.; Miller, Phillip E.; Shaffer, Robert

    1991-01-01

    A shipping device for a heater unit assembly (23), the heater unit assembly (23) including a cylindrical wall (25) and a top plate (31) secured to the cylindrical wall (25) and having a flange portion which projects radially beyond the outer surface of the cylindrical wall (25), and the shipping device including: a cylindrical container (3) having a closed bottom (13); a support member (47) secured to the container (3) and having an inwardly directed flange for supporting the flange portion of the top plate (31); a supplemental supporting system (1) for positioning the heater unit assembly (23) in the container (3) at a spaced relation from the inner surface and bottom wall (13) of the container (3); a cover (15) for closing the top of the container (3); and a container supporting structure (5,7,8) supporting the container (3) in a manner to permit the container (3) to be moved, relative to the supporting structure (5,7,8 ), between a vertical position for loading and unloading the assembly (23) and a horizontal position for transport of the assembly (23). A seal (57) is interposed between the container (3) and the cover (15) for sealing the interior of the container (3) from the environment. An abutment member (41) is mounted on the container supporting structure (5,7,8) for supporting the container bottom (13), when the container (3) is in the vertical position, to prevent the container (3) from moving past the vertical position in the direction away from the horizontal position, and a retainer member (55) is secured within the cover (15) for retaining the assembly top plate (31) in contact with the support member (47) when the cover (15) closes the top of the container (3).

  19. Hydrogen fuel cells could power ships at port

    SciTech Connect (OSTI)

    Pratt, Joe

    2013-06-27

    Sandia National Laboratories researcher Joe Pratt conducted a study on the use of hydrogen fuel cells to power docked ships at major ports. He found the potential environmental and cost benefits to be substantial. Here, he discusses the study and explains how hydrogen fuel cells can provide efficient, pollution-free energy to ships at port.

  20. Hydrogen fuel cells could power ships at port

    ScienceCinema (OSTI)

    Pratt, Joe

    2013-11-22

    Sandia National Laboratories researcher Joe Pratt conducted a study on the use of hydrogen fuel cells to power docked ships at major ports. He found the potential environmental and cost benefits to be substantial. Here, he discusses the study and explains how hydrogen fuel cells can provide efficient, pollution-free energy to ships at port.

  1. Thermal evaluation of alternative shipping cask for irradiated experiments

    SciTech Connect (OSTI)

    Guillen, Donna Post

    2015-06-01

    Results of a thermal evaluation are provided for a new shipping cask under consideration for transporting irradiated experiments between the test reactor and post-irradiation examination (PIE) facilities. Most of the experiments will be irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL), then later shipped to the Hot Fuel Examination Facility (HFEF) located at the Materials and Fuels Complex for PIE. To date, the General Electric (GE)-2000 cask has been used to transport experiment payloads between these facilities. However, the availability of the GE-2000 cask to support future experiment shipping is uncertain. In addition, the internal cavity of the GE-2000 cask is too short to accommodate shipping the larger payloads. Therefore, an alternate shipping capability is being pursued. The Battelle Energy Alliance, LLC, Research Reactor (BRR) cask has been determined to be the best alternative to the GE-2000 cask. An evaluation of the thermal performance of the BRR cask is necessary before proceeding with fabrication of the newly designed cask hardware and the development of handling, shipping and transport procedures. This paper presents the results of the thermal evaluation of the BRR cask loaded with a representative set of fueled and non-fueled payloads. When analyzed with identical payloads, experiment temperatures were found to be lower with the BRR cask than with the GE-2000 cask. Furthermore, from a thermal standpoint, the BRR cask was found to be a suitable alternate to the GE-2000 cask for shipping irradiated experiment payloads.

  2. THERMAL EVALUATION OF ALTERNATE SHIPPING CASK FOR IRRADIATED EXPERIMENTS

    SciTech Connect (OSTI)

    Donna Post Guillen

    2015-06-01

    Results of a thermal evaluation are provided for a new shipping cask under consideration for transporting irradiated experiments between the test reactor and post-irradiation examination (PIE) facilities. Most of the experiments will be irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL), then later shipped to the Hot Fuel Examination Facility (HFEF) located at the Materials and Fuels Complex for PIE. To date, the General Electric (GE)-2000 cask has been used to transport experiment payloads between these facilities. However, the availability of the GE-2000 cask to support future experiment shipping is uncertain. In addition, the internal cavity of the GE-2000 cask is too short to accommodate shipping the larger payloads. Therefore, an alternate shipping capability is being pursued. The Battelle Energy Alliance, LLC, Research Reactor (BRR) cask has been determined to be the best alternative to the GE-2000 cask. An evaluation of the thermal performance of the BRR cask is necessary before proceeding with fabrication of the newly designed cask hardware and the development of handling, shipping and transport procedures. This paper presents the results of the thermal evaluation of the BRR cask loaded with a representative set of fueled and non-fueled payloads. When analyzed with identical payloads, experiment temperatures were found to be lower with the BRR cask than with the GE-2000 cask. From a thermal standpoint, the BRR cask was found to be a suitable alternate to the GE-2000 cask for shipping irradiated experiment payloads.

  3. Motion correction for passive radiation imaging of small vessels in ship-to-ship inspections

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Ziock, Klaus -Peter; Boehnen, Chris Bensing; Ernst, Joseph M.; Fabris, Lorenzo; Hayward, Jason P.; Karnowski, Thomas Paul; Paquit, Vincent C.; Patlolla, Dilip Reddy; Trombino, David

    2015-09-05

    Passive radiation detection remains one of the most acceptable means of ascertaining the presence of illicit nuclear materials. In maritime applications it is most effective against small to moderately sized vessels, where attenuation in the target vessel is of less concern. Unfortunately, imaging methods that can remove source confusion, localize a source, and avoid other systematic detection issues cannot be easily applied in ship-to-ship inspections because relative motion of the vessels blurs the results over many pixels, significantly reducing system sensitivity. This is particularly true for the smaller watercraft, where passive inspections are most valuable. We have developed a combinedmore » gamma-ray, stereo visible-light imaging system that addresses this problem. Data from the stereo imager are used to track the relative location and orientation of the target vessel in the field of view of a coded-aperture gamma-ray imager. Using this information, short-exposure gamma-ray images are projected onto the target vessel using simple tomographic back-projection techniques, revealing the location of any sources within the target. Here,the complex autonomous tracking and image reconstruction system runs in real time on a 48-core workstation that deploys with the system.« less

  4. "Ship-in-a-Bottle" Synthesis of Designer Nanocatalysts | The...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    A new "ship-in-a-bottle" approach to making nano-sized intermetallic compound catalysts (materials that increase how fast chemicals can be made) offers more control over stability, ...

  5. ARM - Evaluation Product - MWACR Corrected for Ship Motion (MWACRSHIPC...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    MAGIC and ACAPEX campaigns. The MWACR is installed on a stable table, so only the mean Doppler velocity must be corrected for the heave of the ship. A source variable indicates...

  6. ARM - Evaluation Product - KAZR Corrected for Ship Motion (KAZRSHIPCOR...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    evaluation product for the MAGIC and ACAPEX campaigns. Reflectivity, spectral width, and signal to noise ratio are corrected to account for the pitch and roll of the ship. Mean...

  7. Design and Control of a Ship Motion Simulation Platform from...

    Office of Scientific and Technical Information (OSTI)

    Citation Details In-Document Search Title: Design and Control of a Ship Motion Simulation ... Pumps are selected based upon required peak power demands, valves are chosen primarily for ...

  8. Fireproof impact limiter aggregate packaging inside shipping containers

    DOE Patents [OSTI]

    Byington, Gerald A.; Oakes, Jr., Raymon Edgar; Feldman, Matthew Rookes

    2001-01-01

    The invention is a product and a process for making a fireproof, impact limiter, homogeneous aggregate material for casting inside a hazardous material shipping container, or a double-contained Type-B nuclear shipping container. The homogeneous aggregate material is prepared by mixing inorganic compounds with water, pouring the mixture into the void spaces between an inner storage containment vessel and an outer shipping container, vibrating the mixture inside the shipping container, with subsequent curing, baking, and cooling of the mixture to form a solidified material which encapsulates an inner storage containment vessel inside an outer shipping container. The solidified material forms a protective enclosure around an inner storage containment vessel which may store hazardous, toxic, or radioactive material. The solidified material forms a homogeneous fire-resistant material that does not readily transfer heat, and provides general shock and specific point-impact protection, providing protection to the interior storage containment vessel. The material is low cost, may contain neutron absorbing compounds, and is easily formed into a variety of shapes to fill the interior void spaces of shipping containers.

  9. PORTSMOUTH 2015 YEAR IN REVIEW

    Office of Environmental Management (EM)

    PORTSMOUTH 2015 YEAR IN REVIEW At the Portsmouth site this year, it was critical to have alignment among regulatory decisions and agreements, deactivation, shipping, and preliminary work on the on-site waste disposal facility. In 2015, we made significant progress in all of those areas. Our workforce performed admirably in 2015 and we look forward to continuing our momentum in 2016." - Dr. Vincent Adams, Portsmouth Site Director, DOE Portsmouth/Paducah Project Office KEY ACCOMPLISHMENTS 

  10. Team China Transforms Shipping Containers into a Solar-Powered House

    Office of Energy Efficiency and Renewable Energy (EERE)

    Team China is turning shipping containers into their 2011 Solar Deacthlon home design. Check it out!

  11. Thermal evaluation of alternative shipping cask for irradiated experiments

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Guillen, Donna Post

    2015-06-01

    Results of a thermal evaluation are provided for a new shipping cask under consideration for transporting irradiated experiments between the test reactor and post-irradiation examination (PIE) facilities. Most of the experiments will be irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL), then later shipped to the Hot Fuel Examination Facility (HFEF) located at the Materials and Fuels Complex for PIE. To date, the General Electric (GE)-2000 cask has been used to transport experiment payloads between these facilities. However, the availability of the GE-2000 cask to support future experiment shipping is uncertain. In addition, the internal cavitymore » of the GE-2000 cask is too short to accommodate shipping the larger payloads. Therefore, an alternate shipping capability is being pursued. The Battelle Energy Alliance, LLC, Research Reactor (BRR) cask has been determined to be the best alternative to the GE-2000 cask. An evaluation of the thermal performance of the BRR cask is necessary before proceeding with fabrication of the newly designed cask hardware and the development of handling, shipping and transport procedures. This paper presents the results of the thermal evaluation of the BRR cask loaded with a representative set of fueled and non-fueled payloads. When analyzed with identical payloads, experiment temperatures were found to be lower with the BRR cask than with the GE-2000 cask. Furthermore, from a thermal standpoint, the BRR cask was found to be a suitable alternate to the GE-2000 cask for shipping irradiated experiment payloads.« less

  12. Maritime shipping as a high reliability industry: A qualitative analysis

    SciTech Connect (OSTI)

    Mannarelli, T.; Roberts, K.; Bea, R.

    1994-10-01

    The maritime oil shipping industry has great public demands for safe and reliable organizational performance. Researchers have identified a set of organizations and industries that operate at extremely high levels of reliability, and have labelled them High Reliability Organizations (HRO). Following the Exxon Valdez oil spill disaster of 1989, public demands for HRO-level operations were placed on the oil industry. It will be demonstrated that, despite enormous improvements in safety and reliability, maritime shipping is not operating as an HRO industry. An analysis of the organizational, environmental, and cultural history of the oil industry will help to provide justification and explanation. The oil industry will be contrasted with other HRO industries and the differences will inform the shortfalls maritime shipping experiences with regard to maximizing reliability. Finally, possible solutions for the achievement of HRO status will be offered.

  13. Ship Effect Measurements With Fiber Optic Neutron Detector

    SciTech Connect (OSTI)

    King, Kenneth L.; Dean, Rashe A.; Akbar, Shahzad; Kouzes, Richard T.; Woodring, Mitchell L.

    2010-08-10

    The main objectives of this research project was to assemble, operate, test and characterize an innovatively designed scintillating fiber optic neutron radiation detector manufactured by Innovative American Technology with possible application to the Department of Homeland Security screening for potential radiological and nuclear threats at US borders (Kouzes 2004). One goal of this project was to make measurements of the neutron ship effect for several materials. The Virginia State University DOE FaST/NSF summer student-faculty team made measurements with the fiber optic radiation detector at PNNL above ground to characterize the ship effect from cosmic neutrons, and underground to characterize the muon contribution.

  14. Aging Behavior of the EPDM O-Rings in the H1616 Shipping Package

    SciTech Connect (OSTI)

    Daugherty, W.; Stefek, T.; Skidmore, E.

    2015-06-09

    The H1616 shipping package is used within the DOE complex for shipping tritium reservoirs. The annual recertification frequency can create logistical difficulties with other constraints on the timing of shipments; thus, a longer re-certification period is desirable. The ethylene propylene diene monomer (EPDM) O-rings used in the H1616 shipping package are being aged and tested at the Savannah River National Laboratory (SRNL) to provide a technical basis for extending the annual maintenance of the H1616 shipping package. H1616 EPDM O-rings are being aged at elevated temperature, and tested for degradation in mechanical properties, compression stress relaxation (CSR) behavior, and leak performance. Mechanical properties of aged O-rings show significant degradation can occur, but an inert atmosphere (argon backfill) greatly reduces the rate of degradation. The CSR behavior of O-rings was evaluated in air at 79 to 177 °C. These collective data were used to develop a predictive model for extrapolation of CSR behavior to relevant service temperatures (<67 °C). O-rings were also aged in H1616 Containment Vessels (CV) in an inert atmosphere at 71 to 149 °C. The vessels are helium leak tested periodically to determine if they continue to remain leak-tight. The vessel tests provide a solid demonstration that the H1616 O-rings will remain leak-tight at temperatures up to 113 °C for up to approximately 2.3 years. Significantly longer periods of leak-tight service are expected at the lower temperatures actually experienced in service. The predictive model developed from the CSR data conservatively indicates a service life of ~5 years at 67 °C. Although the relationship between CSR behavior and leak-tight performance has not been established for this design, the CSR predictions for this O-ring are conservative relative to leak-tight performance. Based on the collective data developed to date, SRNL has recommended that the maintenance interval for the H1616 package be

  15. REVIEW OF AGING DATA ON EPDM O-RINGS IN THE H1616 SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Skidmore, E.

    2012-03-27

    Currently, all H1616 shipping package containers undergo annual re-verification testing, including containment vessel leak testing to verify leak-tightness (<1 x 10{sup -7} ref cc/sec air) as per ANSI N14.5. The purpose of this literature review is to supplement aging studies currently being performed by SRNL on the EPDM O-rings to provide the technical basis for extending annual re-verification testing for the H1616 shipping package and to predict the life of the seals at bounding service conditions. The available data suggest that the EPDM O-rings can retain significant mechanical properties and sealing force at or below bounding service temperatures (169 F or 76 C) beyond the 1 year maintenance period. Interpretation of available data suggests that a service life of at least 2 years and potentially 4-6 years may be possible at bounding temperatures. Seal lifetimes at lower, more realistic temperatures will likely be longer. Being a hydrocarbon elastomer, EPDM O-rings may exhibit an inhibition period due to the presence of antioxidants. Once antioxidants are consumed, mechanical properties and seal performance could decline at a faster rate. Testing is being performed to validate the assumptions outlined in this report and to assess the long-term performance of O-ring seals under actual service conditions.

  16. Separator assembly for use in spent nuclear fuel shipping cask

    DOE Patents [OSTI]

    Bucholz, James A.

    1983-01-01

    A separator assembly for use in a spent nuclear fuel shipping cask has a honeycomb-type wall structure defining parallel cavities for holding nuclear fuel assemblies. Tubes formed of an effective neutron-absorbing material are embedded in the wall structure around each of the cavities and provide neutron flux traps when filled with water.

  17. Posters Ship-Based Measurements of Cloud Optical Properties

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    7 Posters Ship-Based Measurements of Cloud Optical Properties During the Atlantic Stratocumulus Transition Experiment A. B. White Cooperative Institute for Research in Environmental Sciences University of Colorado at Boulder National Oceanic and Atmospheric Administration Boulder, Colorado C. W. Fairall National Oceanic and Atmospheric Administration Environmental Research Laboratories Environmental Technology Laboratory Boulder, Colorado Introduction The Atlantic Stratocumulus Transition

  18. Mooring system optimization with application to a weather vane ship

    SciTech Connect (OSTI)

    Martins, C.A.; Aranha, J.A.P.; Leite, A.

    1995-12-31

    This paper introduces a software that allows one to choose the optimal mooring line system of a weather vane ship. It uses a frequency domain analysis of the ship motion in the horizontal plane employing recently developed analytic expressions for the low frequency sea spectrum, the related wave damping factor and an algebraic approximation for the dynamic tension in the line due to the first order ship motion. The dampings due to the ship hull and mooring lines are incorporated in the model and the only hydrodynamic information needed are the standard ones, namely: the force coefficients for unitary wind and ocean current velocities, the surge added mass at zero frequency, the RAO of the floating system in a certain range of frequencies together with the drift force coefficients for regular waves. Selecting the pre-tension in a specified line as a control parameter, one can determine the total offset of the ocean unit (steady and quasi-steady) together with the maximum tension in all lines, as a function of this control parameters. It has been observed then that the offset of the unit decreases monotonically, as expected, with the pre-tension but the maximum tension in the most loaded line does not increase steadily; this result has been explained with the help of a simplified model and it opens the possibility for one to choose the best pre-tension to fit some design criteria.

  19. THERMAL EVALUATION OF ALTERNATE SHIPPING CASK FOR GTRI EXPERIMENTS

    SciTech Connect (OSTI)

    Donna Post Guillen

    2014-06-01

    The Global Threat Reduction Initiative (GTRI) has many experiments yet to be irradiated in support of the High Performance Research Reactor fuels development program. Most of the experiments will be irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL), then later shipped to the Hot Fuel Examination Facility (HFEF) located at the Materials and Fuels Complex for post irradiation examination. To date, the General Electric (GE)-2000 cask has been used to transport GTRI experiments between these facilities. However, the availability of the GE-2000 cask to support future GTRI experiments is at risk. In addition, the internal cavity of the GE-2000 cask is too short to accommodate shipping the larger GTRI experiments. Therefore, an alternate shipping capability is being pursued. The Battelle Energy Alliance, LLC, Research Reactor (BRR) cask has been determined to be the best alternative to the GE-2000 cask. An evaluation of the thermal performance of the BRR cask is necessary before proceeding with fabrication of the newly designed cask hardware and the development of handling, shipping, and transport procedures. This paper presents the results of the thermal evaluation of the BRR cask loaded with a representative set of fueled and non-fueled experiments. When analyzed with identical payloads, experiment temperatures were found to be lower with the BRR cask than with the GE-2000 cask. From a thermal standpoint, the BRR cask was found to be a suitable alternate to the GE-2000 cask.

  20. Final load of debris shipped from K-25 Building demolition project...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    load of debris shipped from K-25 Building demolition project Final load of debris shipped from K-25 Building demolition project March 11, 2014 - 3:00pm Addthis The last shipment of ...

  1. Stress analysis of closure bolts for shipping casks

    SciTech Connect (OSTI)

    Mok, G.C.; Fischer, L.E. ); Hsu, S.T. )

    1993-01-01

    This report specifies the requirements and criteria for stress analysis of closure bolts for shipping casks containing nuclear spent fuels or high level radioactive materials. The specification is based on existing information conceming the structural behavior, analysis, and design of bolted joints. The approach taken was to extend the ASME Boiler and Pressure Vessel Code requirements and criteria for bolting analysis of nuclear piping and pressure vessels to include the appropriate design and load characteristics of the shipping cask. The characteristics considered are large, flat, closure lids with metal-to-metal contact within the bolted joint; significant temperature and impact loads; and possible prying and bending effects. Specific formulas and procedures developed apply to the bolt stress analysis of a circular, flat, bolted closure. The report also includes critical load cases and desirable design practices for the bolted closure, an in-depth review of the structural behavior of bolted joints, and a comprehensive bibliography of current information on bolted joints.

  2. Cryogenic and Fire Damage Analysis on Liquefied Natural Gas Ships

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Fire Damage Analysis on Liquefied Natural Gas Ships - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste

  3. West Valley facility spent fuel handling, storage, and shipping experience

    SciTech Connect (OSTI)

    Bailey, W.J.

    1990-11-01

    The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs.

  4. EFFECTS OF MOISTURE IN THE 9975 SHIPPING PACKAGE FIBERBOARD ASSEMBLY

    SciTech Connect (OSTI)

    Daugherty, W.; Dunn, K.; Murphy, J.; Hackney, B.

    2010-02-11

    The fiberboard assembly used in 9975 shipping packages as an impact-absorption and insulation component has the capacity to absorb moisture, with an accompanying change to its properties. While package fabrication requirements generally maintain the fiberboard moisture content within manufacturing range, there is the potential during use or storage for atypical handling or storage practices which result in the absorption of additional moisture. In addition to performing a transportation function, the 9975 shipping packages are used as a facility storage system for special nuclear materials at the Savannah River Site. A small number of packages after extended storage have been found to contain elevated moisture levels. Typically, this condition is accompanied by an axial compaction of the bottom fiberboard layers, and the growth of mold. In addition to potential atypical practices, fiberboard can exchange moisture with the surrounding air, depending on the ambient humidity. Laboratory data have been generated to correlate the equilibrium moisture content of cane fiberboard with the humidity of the surrounding air. These data are compared to measurements taken within shipping packages. With a reasonable measurement of the fiberboard moisture content, an estimate of the fiberboard properties can be made. Over time, elevated moisture levels will negatively impact performance properties, and promote fiberboard mold growth and resultant degradation.

  5. Aging Behavior of the Viton® Fluoroelastomer O-Rings in the 9975 Shipping Package

    SciTech Connect (OSTI)

    Daugherty, W.; Mcwilliams, A.; Skidmore, E.

    2015-06-09

    The 9975 Type B shipping package is used within the DOE complex for shipping special nuclear materials. This package is re-certified annually in accordance with Safety Analysis Report requirements. The package is also used at the Savannah River Site as part of the long-term storage configuration of special nuclear materials. As such, the packages do not undergo annual recertification during storage, with uncertainty as to how long some of the package components will meet their functional requirements in the storage environment. The packages are currently approved for up to 15 years storage, and work continues to provide a technical basis to extend that period. This paper describes efforts by the Savannah River National Laboratory (SRNL) to extend the service life estimate of Viton® GLT and GLT-S fluoroelastomer O-rings used in the 9975 shipping package. O-rings of both compositions are undergoing accelerated aging at elevated temperature, and are periodically tested for compression stress relaxation (CSR) behavior and leak performance. The CSR behavior of O-rings was evaluated at temperatures from 79 °C to 177 °C. These collective data were used to develop predictive models for extrapolation of CSR behavior to relevant service temperatures (< 75 °C). O-rings were also aged in Primary Containment Vessel (PCV) fixtures at temperatures ranging from 79 °C to 232 °C. The fixtures are helium leak tested periodically to determine if they remain leak-tight. The PCV fixture tests demonstrate that the 9975 O-rings will remain leak-tight at temperatures up to 149 °C for 3 years or more, and no leak failures have been observed with up to 8 years aging at 93 °C. Significantly longer periods of leak-tight service are expected at the lower temperatures actually experienced in the storage environment. The predictive model developed from the CSR data conservatively indicates a service life of more than 20 years at the bounding temperature of 75 °C. Although the

  6. ES-3100: A New Generation Shipping Container for Bulk Highly Enriched Uranium and Other Fissile Materials

    SciTech Connect (OSTI)

    Arbital, J.G.; Byington, G.A.; Tousley, D.R.

    2004-07-01

    The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA) is shipping bulk quantities of surplus fissile materials, primarily highly enriched uranium (HEU), over the next 15 to 20 years for disposition purposes. The U.S. Department of Transportation (DOT) specification 6M container is the package of choice for most of these shipments. However, the 6M does not conform to the Type B packaging requirements in the ''Code of Federal Regulations'' (10CFR71) and, for that reason, is being phased out for use in the secure transportation system of DOE. BWXT Y-12 is currently developing a package to replace the DOT 6M container for HEU disposition shipping campaigns. The new package is based on state-of-the-art, proven, and patented insulation technologies that have been successfully applied in the design of other packages. The new package, designated the ES-3100, will have a 50% greater capacity for HEU than the 6M and will be easier to use. Engineering analysis on the new package includes detailed dynamic impact finite element analysis (FEA). This analysis gives the ES-3100 a high probability of complying with regulatory requirements.

  7. Analysis of Real Ship Rolling Dynamics under Wave Excitement Force Composed of Sums of Cosine Functions

    SciTech Connect (OSTI)

    Zhang, Y. S. [Department of Scientific Research, Dalian Naval Academy, Dalian 116018 (China); Cai, F. [Department of Navigation, Dalian Naval Academy, Dalian 116018 (China); Xu, W. M. [Department of Hydrography and Cartography, Dalian Naval Academy, Dalian 116018 (China)

    2011-09-28

    The ship motion equation with a cosine wave excitement force describes the slip moments in regular waves. A new kind of wave excitement force model, with the form as sums of cosine functions was proposed to describe ship rolling in irregular waves. Ship rolling time series were obtained by solving the ship motion equation with the fourth-order-Runger-Kutta method. These rolling time series were synthetically analyzed with methods of phase-space track, power spectrum, primary component analysis, and the largest Lyapunove exponent. Simulation results show that ship rolling presents some chaotic characteristic when the wave excitement force was applied by sums of cosine functions. The result well explains the course of ship rolling's chaotic mechanism and is useful for ship hydrodynamic study.

  8. Design and Criticality Considerations for 9977 and 9978 Shipping Packages

    SciTech Connect (OSTI)

    Reed, R; Biswas, D; Abramczyk, G

    2008-11-25

    Savannah River National Laboratory (SRNL) has developed two new, Type B, state-of-the-art, general purpose, fissile material Shipping Packages, designated 9977 and 9978, as replacements for the U.S. DOT specification 6M container, phased out in September 30, 2008 due to non-compliance with current requirements 10CFR71 regulation. The packages accommodate plutonium, uranium and other special nuclear materials in bulk quantities and in many forms with capabilities exceeding those of the 6M. These packages provide a high degree of single containment and comply with 10CFR71, Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10CFR20 (As Low As Reasonably Achievable (ALARA)). Allowed package contents were determined accounting for nuclear criticality, radiation shielding, and decay heat rate. The Criticality Safety Index (CSI) for the package is 1.0. The package utilizes passive cooling to maintain internal temperatures within limits. Radiation shielding analyses have established the contents for which the packages can be shipped under non-exclusive use in the Safe-Secure Trailer or under exclusive use. The packages are designed to ship radioactive contents in several configurations; Radioisotope Thermoelectric Generators (RTGs), nested food-pack cans, site specific containers, and DOE-STD-3013 containers. Each shipping package includes a 35-gallon stainless steel outer drum, insulation, a drum liner, and a single containment vessel (CV). The 9977 includes a 6-inch ID CV while the 9978 includes a 5-inch ID CV. One inch of Fiberfrax{reg_sign} insulation is wrapped around and attached to the sides and bottom of the liner. The volume between the Fiberfrax{reg_sign} and the drum wall is filled with polyurethane foam. Top and bottom aluminum Load Distribution Fixtures (LDFs) within the drum liner cavity, above and below the CV, center the CV in the liner, stiffen the package radially, and distribute loads away from the CV. The 6CV fits directly into the LDFs while

  9. Experiments on Nuclear Structure and Synthesis of Superheavy Elements at SHIP

    SciTech Connect (OSTI)

    Hessberger, F. P.

    2007-02-26

    Experiments to synthesize isotopes of heaviest elements and to investigate as well their production mechanisms as their nuclear properties have been performed during the past three decades at the velocty filter SHIP. Isotopes of six so far unknown elements with atomic numbers Z = 107-112 have been identified, excitation functions for production of transactinide isotopes in so-called 'cold' fusion reactions, using Pb- or Bi- targets and 'medium' heavy projectiles from 50Ti to 64Ni have been measured. In recent years experiments also concentrated on nuclear structure investigations by means of evaporation residue (ER)-{gamma}- or {alpha}-{gamma}-decay spectroscopy resulting in systematic studies of low lying Nilsson levels in odd mass nuclei and identification of high lying (E* > 1 MeV) isomeric states in neutron deficient nobelium isotopes.

  10. Analysis of International Commodity Shipping Data and the Shipment of NORM to the United States

    SciTech Connect (OSTI)

    Baciak, James E.; Ely, James H.; Schweppe, John E.; Sandness, Gerald A.; Robinson, Sean M.

    2011-10-01

    As part of the Spreader Bar Radiation Detector project, PNNL analyzed US import data shipped through US ports collected over the 12 months of 2006 (over 4.5 million containers). Using these data, we extracted a variety of distributions that are of interest to modelers and developers of active and passive detection systems used to 'scan' IMCCs for potential contraband. This report expands on some of the analysis presented in an earlier report from LLNL, by investigation the foreign port distribution of commodities shipped to the US. The majority of containers shipped to the United States are 40 ft containers ({approx}70%); about 25% are 20 ft; and about 3.6% are 45 ft containers. A small fraction (<1%) of containers are of other more specialized sizes, and very few ports actually ship these unique size containers (a full distribution for all foreign ports is shown in Appendix A below). The primary foreign ports that ship the largest fraction of each container are shown in the table below. Given that 45 ft containers comprise 1 of out every 27 containers shipped to the US, and given the foreign ports from which they are shipped, they should not be ignored in screening; further testing and analysis of radiation measurements for national security with this size container is warranted. While a large amount of NORM is shipped in IMCCs, only a few specific commodities are shipped with enough frequency to present potential issues in screening IMCCs at ports. The majority of containers with NORM will contain fertilizers (5,700 containers), granite (59,000 containers), or ceramic (225,000 containers) materials. Fertilizers were generally shipping in either 20- or 40 ft containers with equal frequency. While granite is mostly shipped in 20 ft containers, ceramic materials can be shipped in either 20- or 40 ft containers. The size of container depended on the specific use of the ceramic or porcelain material. General construction ceramics (such as floor and roofing tiles) tend

  11. Diesel fueled ship propulsion fuel cell demonstration project

    SciTech Connect (OSTI)

    Kumm, W.H.

    1996-12-31

    The paper describes the work underway to adapt a former US Navy diesel electric drive ship as a 2.4 Megawatt fuel cell powered, US Coast Guard operated, demonstrator. The Project will design the new configuration, and then remove the four 600 kW diesel electric generators and auxiliaries. It will design, build and install fourteen or more nominal 180 kW diesel fueled molten carbonate internal reforming direct fuel cells (DFCs). The USCG cutter VINDICATOR has been chosen. The adaptation will be carried out at the USCG shipyard at Curtis Bay, MD. A multi-agency (state and federal) cooperative project is now underway. The USCG prime contractor, AEL, is performing the work under a Phase III Small Business Innovation Research (SBIR) award. This follows their successful completion of Phases I and II under contract to the US Naval Sea Systems (NAVSEA) from 1989 through 1993 which successfully demonstrated the feasibility of diesel fueled DFCs. The demonstrated marine propulsion of a USCG cutter will lead to commercial, naval ship and submarine applications as well as on-land applications such as diesel fueled locomotives.

  12. 70 Years of Innovations

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... Detecting dying stars x x 1974 First medical isotope Los Alamos produced and shipped our first radioisotope. Today, we continue to supply international medical and research ...

  13. Microsoft Word - SSRL_LCLS_User_Shipping_Request_Form_nonhaz_1-25-2011

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Non-Hazardous Material) Will this be shipped to a location outside of the U.S.? No ___ Yes ___ If yes, user must complete Power of Attorney and certify concurrence with terms and conditions. Confirm with Cathy Knotts or Lisa Dunn that this has been completed. _______ * It can take several days to process shipping requests through SLAC. Missing or insufficient information will delay shipments further. * Hazardous Materials Shipments must be declared on the Hazardous Material Shipping Form and

  14. FINITE ELEMENT ANALYSIS OF BULK TRITIUM SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Jordan, J.

    2010-06-02

    The Bulk Tritium Shipping Package was designed by Savannah River National Laboratory. This package will be used to transport tritium. As part of the requirements for certification, the package must be shown to meet the scenarios of the Hypothetical Accident Conditions (HAC) defined in Code of Federal Regulations Title 10 Part 71 (10CFR71). The conditions include a sequential 30-foot drop event, 30-foot dynamic crush event, and a 40-inch puncture event. Finite Element analyses were performed to support and expand upon prototype testing. Cases similar to the tests were evaluated. Additional temperatures and orientations were also examined to determine their impact on the results. The peak stress on the package was shown to be acceptable. In addition, the strain on the outer drum as well as the inner containment boundary was shown to be acceptable. In conjunction with the prototype tests, the package was shown to meet its confinement requirements.

  15. Shipping container response to three severe railway accident scenarios

    SciTech Connect (OSTI)

    Mok, G.C.; Fischer, L.E.; Murty, S.S.; Witte, M.C.

    1998-04-01

    The probability of damage and the potential resulting hazards are analyzed for a representative rail shipping container for three severe rail accident scenarios. The scenarios are: (1) the rupture of closure bolts and resulting opening of closure lid due to a severe impact, (2) the puncture of container by an impacting rail-car coupler, and (3) the yielding of container due to side impact on a rigid uneven surface. The analysis results indicate that scenario 2 is a physically unreasonable event while the probabilities of a significant loss of containment in scenarios 1 and 3 are extremely small. Before assessing the potential risk for the last two scenarios, the uncertainties in predicting complex phenomena for rare, high- consequence hazards needs to be addressed using a rigorous methodology.

  16. Crashworthiness of the AT-400A shipping container

    SciTech Connect (OSTI)

    Gruda, J.D.; York, A.R. II

    1996-05-01

    Shipping containers used for transporting radioactive material must be certified using federal regulations. These regulations require the container be tested or evaluated in severe mechanical and thermal environments which represent hypothetical accident scenarios. The containers are certified if the inner container remains leaktight. This paper presents results from finite element simulations of the accidents which include subjecting the AT-400A (for Pu from dismantled nuclear weapons) to a 30-foot (9 m) drop onto an unyielding target and crushing the container with an 1100 lb (500 kg) steel plate dropped from 30 feet. The nonlinear PRONTO3D finite element results were validated using test results. The simulations of the various impacts and crushes identified trends and worst-case orientations. They also showed that there is a significant margin of safety based on the failure of the containment vessel.

  17. DEVELOPMENT AND USE OF A BULK TRITIUM SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Blanton, P.

    2010-09-30

    A shipping package for transporting tritium has been developed for use by the National Nuclear Safety Administration as a replacement for the DOE Model UC-609, a tritium package developed and used by the DOE and NRC since the early 1970s. This paper presents the major design features and highlights the improvements made over its predecessor by incorporating new engineered materials and implementing improved testing, handling, and maintenance capabilities, while improving manufacturability. A discussion will be provided demonstrating how the BTSP complies with the regulatory safety requirements of the Nuclear Regulatory Commission. The paper further summarizes the results of testing to 10 CFR 71 Normal Conditions of Transport and Hypothetical Accident Conditions events. Planned and possible future missions for this packaging will be addressed.

  18. Radioluminescent emergency egress lighting for US Navy surface ships

    SciTech Connect (OSTI)

    Adrian, D.K.; Pusey, H.C.; Jensen, G.A.; Traub, R.J.

    1988-12-01

    This very limited study examines only one of a number of shipboard applications to which (RL) might be applied. A detailed analysis is needed to fully explore the potential for use of state-of-the-art RL systems in the Navy. A more comprehensive study is highly recommended. It was also not possible to assess the implications of emerging RL technologies such as solid matrix light development and advanced gas techniques; it is strongly recommended that continued research level efforts do this. Nonetheless, for the emergency egress application, enough conclusive evidence was developed and critical questions answered to indicate that the RL option using current technology can economically improve emergency egress and crew safety significantly on Navy ships. 18 refs., 9 figs., 7 tabs.

  19. Flammability Analysis For Actinide Oxides Packaged In 9975 Shipping Containers

    SciTech Connect (OSTI)

    Laurinat, James E.; Askew, Neal M.; Hensel, Steve J.

    2013-03-21

    Packaging options are evaluated for compliance with safety requirements for shipment of mixed actinide oxides packaged in a 9975 Primary Containment Vessel (PCV). Radiolytic gas generation rates, PCV internal gas pressures, and shipping windows (times to reach unacceptable gas compositions or pressures after closure of the PCV) are calculated for shipment of a 9975 PCV containing a plastic bottle filled with plutonium and uranium oxides with a selected isotopic composition. G-values for radiolytic hydrogen generation from adsorbed moisture are estimated from the results of gas generation tests for plutonium oxide and uranium oxide doped with curium-244. The radiolytic generation of hydrogen from the plastic bottle is calculated using a geometric model for alpha particle deposition in the bottle wall. The temperature of the PCV during shipment is estimated from the results of finite element heat transfer analyses.

  20. CSR behavior and aging model for the Viton© Fluorelastomer O-rings in the 9975 shipping package

    SciTech Connect (OSTI)

    Mcwilliams, A. J.; Daugherty, W. L.; Skidmore, T. E.

    2015-12-01

    The 9975 Type B shipping package is used within the DOE complex for shipping special nuclear materials. This package is re-certified annually in accordance with Safety Analysis Report for Packaging (SARP) requirements. The package is also used at the Savannah River Site as part of the long-term storage configuration of special nuclear materials. As such, the packages do not undergo annual recertification during storage, with uncertainty as to how long some of the package components will meet their functional requirements in the storage environment. The packages are currently approved for up to 15 years storage, and work continues to provide a technical basis to extend that period. This report describes efforts by the Savannah River National Laboratory (SRNL) to extend the service life estimate of Viton® GLT and GLT-S fluoroelastomer O-rings used in the 9975 shipping package. O-rings of both GLT and GLT-S compositions are undergoing accelerated aging at elevated temperature, and are periodically tested for compression stress relaxation (CSR) behavior. The CSR behavior of O-rings was evaluated at temperatures from 175 to 400 °F. These collective data were used to develop predictive models for extrapolation of CSR behavior to relevant service temperatures (< 156 °F). The predictive model developed from the CSR data conservatively indicates a service life of approximately 37 years for Viton GLT O-rings at the maximum effective service temperature of 156 °F. The estimated service life for Viton GLT-S O-rings is significantly longer.

  1. Calendar Year 2000 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    0 Calendar Year 2000 November 28, 2000 Special Report: IG-0491 Management Challenges at the Department of Energy November 28, 2000 Audit Report: IG-0489 Americium/Curium Vitrification Project At The Savannah River Site November 28, 2000 Audit Report: IG-0490 Containers Suitable for Shipping Fissile Material November 20, 2000 Inspection Report: IG-0488 Inspection of Selected Aspects of the Department of Energy's Classified Document Transmittal Process November 6, 2000 Inspection Report:

  2. DYNA3D analysis of the DT-20 shipping container

    SciTech Connect (OSTI)

    Logan, R.W.; Lovejoy, S.C.

    1991-08-22

    A DYNA3D model of the DT-20 shipping container was constructed. Impact onto a rigid steel surface at a velocity of 44 ft/sec (30 foot gravity drop) was studied. The orientation of most interest was a side-drop, but end and corner drops were also studied briefly. The assembly for the baseline side impact contained a 150 lb. payload. During this drop, the outer drum sustains plastic strains of up to 0.15, with most the deformation near the rim. The plywood/Celotex packing is crushed about 3 inches. The inner sealed can sees significant stresses, but barely reaches the onset of yielding in some local areas. Based on hand calculations, the bolts joining the can halves could see stresses near 50 ksi. It is felt that overall, the container should survive this drop. However, detailed modeling of the rim closure and the center bolted joint was not possible due to time constraints. Furthermore, better material models and properties are needed for the Celotex, plywood, and honeycomb in particular. 39 figs., 1 tab.

  3. DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-06100

    SciTech Connect (OSTI)

    Daugherty, W.

    2014-11-07

    Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-06100. This package was selected for examination based on several characteristics: - This was the first destructively examined package in which the fiberboard assembly was fabricated from softwood fiberboard. - The package contained a relatively high heat load to contribute to internal temperature, which is a key environmental factor for fiberboard degradation. - The package has been stored in the middle or top of a storage array since its receipt in K- Area, positions that would contribute to increased service temperatures. No significant changes were observed for attributes that were measured during both field surveillance and destructive examination. Except for the axial gap, all observations and test results met identified criteria, or were collected for information and trending purposes. The axial gap met the 1 inch maximum criterion during field surveillance, but was just over the criterion during SRNL measurements. When re-measured at a later date, it again met the criterion. The bottom of the lower fiberboard assembly and the drum interior had two small stains at matching locations, suggestive of water intrusion. However, the fiberboard assembly did not contain any current evidence of excess moisture. No evidence of a degraded condition was found in this package. Despite exposure to the elevated temperatures of this higher-then-average wattage package, properties of the fiberboard and O-rings are consistent with those of new packages.

  4. Results from the Solar Hidden Photon Search (SHIPS)

    SciTech Connect (OSTI)

    Schwarz, Matthias; Knabbe, Ernst-Axel; Lindner, Axel; Redondo, Javier; Ringwald, Andreas; Schneide, Magnus; Susol, Jaroslaw; Wiedemann, Günter

    2015-08-07

    We present the results of a search for transversely polarised hidden photons (HPs) with ∼3 eV energies emitted from the Sun. These hypothetical particles, known also as paraphotons or dark sector photons, are theoretically well motivated for example by string theory inspired extensions of the Standard Model. Solar HPs of sub-eV mass can convert into photons of the same energy (photon ↔ HP oscillations are similar to neutrino flavour oscillations). At SHIPS this would take place inside a long light-tight high-vacuum tube, which tracks the Sun. The generated photons would then be focused into a low-noise photomultiplier at the far end of the tube. Our analysis of 330 h of data (and 330 h of background characterisation) reveals no signal of photons from solar hidden photon conversion. We estimate the rate of newly generated photons due to this conversion to be smaller than 25 mHz/m{sup 2} at the 95% C.L. Using this and a recent model of solar HP emission, we set stringent constraints on χ, the coupling constant between HPs and photons, as a function of the HP mass.

  5. An Analysis of Dual Zone Loading for Shipping Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Allen, William Christopher; Yim, Man-Sung

    2007-07-01

    The bumps current fuel assembly designs can achieve exceeds the fuel assembly burnups the current fleet of shipping casks can ship. One method of handling this situation which has been proposed is regionalized loading. This concept involves administratively separating the fuel basket of a shipping cask into two or more regions and loading fuel with different burnup, cooling times and enrichments into these regions. To evaluate how regionalized loading patterns might affect shipping spent nuclear fuel in comparison to uniform loading, a test case study was performed using fuel assemblies discharged from an actual nuclear plant and a shipping cask licensed by the NRC. Using the same fuel assemblies and shipping cask, results were obtained assuming a uniform loading pattern and compared to the results obtained assuming a dual zone loading pattern. Source terms for the analysis were generated using SAS2 and the dose levels were calculated using MCNPS. The analysis showed that the dual zone loading reduced the amount of time required to ship the given quantity of fuel by roughly thirty percent compared to the uniform loading. The average dose rate to the transportation workers and the public due to the implementation of dual zone loading increased. Implications of these increases are discussed. (authors)

  6. Safety analysis report for packaging for the Idaho National Engineering Laboratory TRA Type 1 Shipping Container and TRA Type 2 Shipping Capsule

    SciTech Connect (OSTI)

    Havlovick, B.J.

    1992-07-27

    The TRA Type I Shipping Container and TRA Type II Shipping Capsule were designed and fabricated at the Idaho National Engineering Laboratory as special form containers for the transport of non-fissile radioisotopes and fissile radioisotopes in exempt quantities. The Type I container measures 0.75 in. outside diameter and 3.000 in long. The Type II capsule is 0.495 in. outside diameter 2.000 in. long. The container and capsule were tested and evaluated to determine their compliance with Title 49 Code of Federal Regulations 173, which governs packages for special form radioactive material. This report is based upon those tests and evaluations. The results of those tests and evaluations demonstrate the container and capsule are in full compliance with the special form shipping container regulations of 49 CFR 173.

  7. EIA cites importance of key world shipping routes

    SciTech Connect (OSTI)

    Not Available

    1994-03-07

    A disruption of crude oil or products shipments through any of six world chokepoints would cause a spike in oil prices, the US Energy Information Administration (EIA) warns. The strategic importance of each major shipping lane varies because of differing oil volumes and access to other transportation routes. But nearly half of the 66 million b/d of oil consumed worldwide flows through one or more of these key tanker routes, involving: 14 million b/d through the Strait of Hormuz from the Persian Gulf to the Gulf of Oman and Arabian Sea; 7 million b/d through the Strait of Malacca from the northern Indian Ocean into the South China Sea and Pacific Ocean; 1.6 million b/d through the Bosporus from the Black Sea to the Mediterranean Sea; 900,000 b/d through the Suez Canal from the Red Sea to the Mediterranean Sea; 600,000 b/d through Rotterdam Harbor from the North Sea to Dutch and German refineries on or near the Rhine River; and 500,000 b/d through the Panama Canal from the Pacific Ocean to the Caribbean Sea. In today's highly interdependent oil markets, the mere perception of less secure oil supplies is enough to boost oil prices, EIA said. Growing oil and product tanker traffic is increasing the likelihood of supply disruptions through oil arteries because of bad weather, tanker collisions, or acts of piracy, terrorism, or war. What's more, the increasing age of the world tanker fleet and dependability of navigational equipment could increase chances of accidents and, therefore, oil supply disruptions.

  8. FATE Unified Modeling Method for Spent Nuclear Fuel and Sludge Processing, Shipping and Storage - 13405

    SciTech Connect (OSTI)

    Plys, Martin; Burelbach, James; Lee, Sung Jin; Apthorpe, Robert

    2013-07-01

    A unified modeling method applicable to the processing, shipping, and storage of spent nuclear fuel and sludge has been incrementally developed, validated, and applied over a period of about 15 years at the US DOE Hanford site. The software, FATE{sup TM}, provides a consistent framework for a wide dynamic range of common DOE and commercial fuel and waste applications. It has been used during the design phase, for safety and licensing calculations, and offers a graded approach to complex modeling problems encountered at DOE facilities and abroad (e.g., Sellafield). FATE has also been used for commercial power plant evaluations including reactor building fire modeling for fire PRA, evaluation of hydrogen release, transport, and flammability for post-Fukushima vulnerability assessment, and drying of commercial oxide fuel. FATE comprises an integrated set of models for fluid flow, aerosol and contamination release, transport, and deposition, thermal response including chemical reactions, and evaluation of fire and explosion hazards. It is one of few software tools that combine both source term and thermal-hydraulic capability. Practical examples are described below, with consideration of appropriate model complexity and validation. (authors)

  9. Department of Energy Spent Fuel Shipping Campaigns: Comparisons of Transportation Plans and Lessons Learned

    SciTech Connect (OSTI)

    Holm, Judith A.; Thrower, Alex W.; Antizzo, Karen

    2003-02-27

    Over the last 30 years, the U.S. Department of Energy (DOE) has successfully and safely transported shipments of spent nuclear fuel over America's highways and railroads. During that time, an exemplary safety record has been established with no identifiable fatalities, injuries, or environmental damage caused by the radioactive nature of the shipments. This paper evaluates some rail and truck shipping campaigns, planning processes, and selected transportation plans to identify lessons learned in terms of planning and programmatic activities. The intent of this evaluation is to document best practices from current processes and previous plans for DOE programs preparing or considering future plans. DOE's National Transportation Program (NTP) reviewed 13 plans, beginning with core debris shipments from Three Mile Island to current, ongoing fuel campaigns. This paper describes lessons learned in the areas of: emergency planning, planning information, security, shipment prenotification, emergency notification/response, terrorism/sabotage risk, and recovery and cleanup, as well as routing, security, carrier/driver requirements, transportation operational contingencies, tracking, inspections and safe parking.

  10. Y YEAR

    National Nuclear Security Administration (NNSA)

    2 40 -4.76% YEAR 2013 2014 Males 37 35 -5.41% Females 5 5 0% YEAR 2013 2014 SES 2 2 0% EJEK 5 4 -20.00% EN 05 5 7 40.00% EN 04 6 6 0% EN 03 1 1 0% NN...

  11. Y YEAR

    National Nuclear Security Administration (NNSA)

    79 67 -15.19% YEAR 2013 2014 Males 44 34 -22.73% Females 35 33 -5.71% YEAR 2013 2014 SES 6 4 -33.33% EJEK 1 1 0% EN 05 9 8 -11.11% EN 04 6 5 -16.67% NN...

  12. Using Transportation Technology to Increase Efficiencies in Shipping: Real Life Experience in Oak Ridge

    Broader source: Energy.gov [DOE]

    RFITS has enabled DOE ORO to establish a complex-wide initiative, supporting on-site electronic shipping and transportation of waste while utilizing industry best practices to develop and maintain...

  13. Microsoft Word - SSRL_LCLS_User_Shipping_Request_Form_hazmat_1-25-2011

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Hazardous Material) Will this be shipped to a location outside of the U.S.? No ___ Yes ___ If yes, user must complete Power of Attorney and certify concurrence with terms and conditions. Confirm with Cathy Knotts or Lisa Dunn that this has been completed. _______ * HAZARDOUS MATERIALS MUST BE DECLARED AND MUST BE APPROVED BY ES&H REPRESENTATIVE. (see reverse side of this form) * A Separate form must be submitted for each hazmat declared. * It can take several days to process shipping

  14. "Ship-in-a-Bottle" Synthesis of Designer Nanocatalysts | The Ames

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Laboratory "Ship-in-a-Bottle" Synthesis of Designer Nanocatalysts A new "ship-in-a-bottle" approach to making nano-sized intermetallic compound catalysts (materials that increase how fast chemicals can be made) offers more control over stability, activity, product selectivity, and conversion efficiency than possible before. The approach involves encapsulating the catalyst inside a "glass-bottle" made from porous silica (a.k.a. sand), and the ordered compound

  15. Aging Behavior of Viton{sup R} O-Ring Seals in the 9975 Shipping Package - 12594

    SciTech Connect (OSTI)

    Skidmore, T. Eric; Daugherty, William L.; Hoffman, Elizabeth N.; Dunn, Kerry A.; Stephen Bellamy, J.; Shuler, James M.

    2012-07-01

    The Savannah River Site (SRS) is storing plutonium (Pu) materials in the K-Area Materials Storage (KAMS) facility. The Pu materials were packaged according to the DOE-STD-3013 standard and shipped to the SRS in Type B 9975 packages. The robust 9975 shipping package was not designed for long-term product storage, but it is a specified part of the storage configuration and the KAMS facility safety basis credits the 9975 design with containment. Within the 9975 package, nested stainless steel containment vessels are closed with dual O-ring seals based on Viton{sup R} GLT or GLT-S fluoro-elastomer. The aging behavior of the O-ring compounds is being studied to provide the facility with advanced notice of nonconformance and to develop life prediction models. A combination of field surveillance, leak testing of surrogate fixtures aged at bounding service temperatures, and accelerated-aging methodologies based on compression stress-relaxation and oxygen consumption analysis is being used to evaluate seal performance. A summary of the surveillance program relative to seal aging behavior is presented. The aging behavior of fluoro-elastomer seals based on Viton{sup R} GLT and GLT-S is being studied to develop life prediction models in support of long-term storage of plutonium materials in the 9975 shipping packages at the Savannah River Site. Field surveillance data in combination with accelerated-aging data suggest a significant lifetime for the seals. Typical storage conditions are not anticipated to challenge the leak-tightness of the seals for many years. Early life prediction models based on compression stress relaxation indicate a seal lifetime of ?12 years at the maximum service temperature predicted (93 deg. C). Seal lifetimes at lower, more realistic conditions are likely significantly longer. Service life predictions based on CSR data are thus far conservative relative to predictions based on time to leakage failure. Surveillance data on packages examined after 6

  16. Y YEAR

    National Nuclear Security Administration (NNSA)

    7 35 -5.41% ↓ YEAR 2013 2014 Males 27 25 -7.41% ↓ Females 10 10 0% / YEAR 2013 2014 SES 1 1 0% / EN 05 1 1 0% / EN 04 11 10 -9.09% ↓ NN (Engineering) 8 8 0% / NQ (Prof/Tech/Admin) 14 15 7.14% ↑ NU (Tech/Admin Support) 2 0 -100% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 1 1 0% / African American Male (AA,M) 1 1 0% / African American Female (AA,F) 3 3 0% / Asian American Pacific Islander Male (AAPI,M) 0 0 0% /

  17. Y YEAR

    National Nuclear Security Administration (NNSA)

    5 79 -7.06% ↓ YEAR 2013 2014 Males 59 57 -3.39% ↓ Females 26 22 -15.38% ↓ YEAR 2013 2014 SES 1 0 -100% ↓ EJ/EK 4 3 -25.00% ↓ EN 05 3 2 -33.33% ↓ EN 04 22 22 0% / EN 03 8 8 0% / NN (Engineering) 16 15 -6.25% ↓ NQ (Prof/Tech/Admin) 28 26 -7.14% ↓ NU (Tech/Admin Support) 3 3 0% / YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 2 2 0% / American Indian Alaskan Native Female (AIAN,F) 1 1 0% / African American Male (AA,M) 5 4 -20.00% ↓ African American Female (AA,F) 3 2

  18. Y YEAR

    National Nuclear Security Administration (NNSA)

    91 81 -10.99% ↓ YEAR 2013 2014 Males 67 56 -16.42% ↓ Females 24 25 4.17% ↑ YEAR 2013 2014 SES 1 2 100% ↑ EJ/EK 9 8 -11.11% ↓ EN 04 25 22 -12.00% ↓ NN (Engineering) 24 20 -16.67% ↓ NQ (Prof/Tech/Admin) 29 26 -10.34% ↓ NU (Tech/Admin Support) 3 3 0% / YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 2 2 0% / American Indian Alaskan Native Female (AIAN,F) 3 3 0% / African American Male (AA,M) 0 0 0% / African American Female (AA,F) 0 0 0% / Asian American Pacific Islander

  19. Y YEAR

    National Nuclear Security Administration (NNSA)

    21 -4.55% ↓ YEAR 2013 2014 Males 10 8 -20.00% ↓ Females 12 13 8.33% ↑ YEAR 2013 2014 SES 10 7 -30.00% ↓ EX 0 2 100% ↑ EJ/EK 1 1 0% / EN 05 0 1 100% ↑ EN 04 0 1 100% ↑ NQ (Prof/Tech/Admin) 9 8 -11.11% ↓ NU (Tech/Admin Support) 1 1 0% / ED 00 1 0 -100% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 2 1 -50.00% ↓ African American Male (AA,M) 1 1 0% / African American Female (AA,F) 5 4 -20.00% ↓ Asian

  20. Y YEAR

    National Nuclear Security Administration (NNSA)

    41 155 9.93% ↑ YEAR 2013 2014 Males 92 106 15.22% ↑ Females 49 49 0% / YEAR 2013 2014 SES 8 8 0% / EX 1 1 0% / EJ/EK 4 4 0% / EN 05 11 10 -9.09% ↓ EN 04 11 14 27.27% ↑ EN 03 2 5 150% ↑ NN (Engineering) 60 63 5.00% ↑ NQ (Prof/Tech/Admin) 44 50 13.64% ↑ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 1 1 0% / American Indian Alaskan Native Female (AIAN,F) 1 1 0% / African American Male (AA,M) 7 10 42.86% ↑ African American Female (AA,F) 13 11 -15.38% ↓ Asian American

  1. Y YEAR

    National Nuclear Security Administration (NNSA)

    563 560 -0.53% ↓ YEAR 2013 2014 Males 518 514 -0.77% ↓ Females 45 46 2.22% ↑ YEAR 2013 2014 SES 2 2 0% / EJ/EK 2 2 0% / EN 04 1 1 0% / NN (Engineering) 11 11 0% / NQ (Prof/Tech/Admin) 218 221 1.38% ↑ NU (Tech/Admin Support) 1 2 100% ↑ NV (Nuc Mat Courier) 328 321 -2.13% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 15 15 0% / American Indian Alaskan Native Female (AIAN,F) 2 2 0% / African American Male (AA,M) 19 18 -5.26% ↓ African American Female (AA,F) 1 1 0% /

  2. Y YEAR

    National Nuclear Security Administration (NNSA)

    97 180 -8.63% ↓ YEAR 2013 2014 Males 105 89 -15.24% ↓ Females 92 91 -1.09% ↓ YEAR 2013 2014 SES 14 13 -7.14% ↓ EX 1 1 0% / EJ/EK 3 3 0% / EN 05 1 1 0% / EN 04 4 2 -50.00% ↓ EN 03 1 1 0% / EN 00 0 3 100% ↑ NN (Engineering) 35 27 -22.86% ↓ NQ (Prof/Tech/Admin) 135 126 -6.67% ↓ NU (Tech/Admin Support) 2 2 0% / GS 15 0 1 100% ↑ GS 13 1 0 -100% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 2 1 -50.00% ↓ American Indian Alaskan Native Female (AIAN,F) 0 0 0% /

  3. Y YEAR

    National Nuclear Security Administration (NNSA)

    *Total number of Employees 122 112 -8.20% ↓ YEAR 2013 2014 Males 90 84 -6.67% ↓ Females 32 28 -12.50% ↓ YEAR 2013 2014 SES 26 24 -7.69% ↓ EJ/EK 3 3 0% / EN 05 8 9 12.50% ↑ NN (Engineering) 48 47 -2.08% ↓ NQ (Prof/Tech/Admin) 30 26 -13.33% ↓ NU (Tech/Admin Support) 7 3 -57.14% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 1 1 0% / African American Male (AA,M) 3 3 0% / African American Female (AA,F) 7 6 -14.29%

  4. Y YEAR

    National Nuclear Security Administration (NNSA)

    4 79 -5.95% ↓ YEAR 2013 2014 Males 59 55 -6.78% ↓ Females 25 24 -4.00% ↓ YEAR 2013 2014 SES 3 3 0% / EJ/EK 4 4 0% / EN 04 2 1 -50.00% ↓ NN (Engineering) 20 20 0% / NQ (Prof/Tech/Admin) 55 51 -7.27% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 0 0 0% / African American Male (AA,M) 10 10 0% / African American Female (AA,F) 9 8 -11.11% ↓ Asian American Pacific Islander Male (AAPI,M) 2 2 0% / Asian American Pacific

  5. Y YEAR

    National Nuclear Security Administration (NNSA)

    8 87 -1.14% ↓ YEAR 2013 2014 Males 46 46 0% / Females 42 41 -2.38% ↓ YEAR 2013 2014 SES 1 0 -100% ↓ EJ/EK 4 2 -50.00% ↓ NN (Engineering) 12 12 0% / NQ (Prof/Tech/Admin) 68 70 2.94% ↑ NU (Tech/Admin Support) 3 3 0% / YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 2 2 0% / African American Male (AA,M) 5 5 0% / African American Female (AA,F) 5 6 20.00% ↑ Asian American Pacific Islander Male (AAPI,M) 0 0 0% / Asian

  6. Y YEAR

    National Nuclear Security Administration (NNSA)

    1 14 27.27% ↑ YEAR 2013 2014 Males 9 12 33.33% ↑ Females 2 2 0% / YEAR 2013 2014 SES 2 2 0% / EJ/EK 1 1 0% / EN 04 0 1 100% ↑ EN 00 0 1 100% ↑ NN (Engineering) 5 5 0% / NQ (Prof/Tech/Admin) 3 4 33.33% ↑ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 0 0 0% / African American Male (AA,M) 0 0 0% / African American Female (AA,F) 0 0 0% / Asian American Pacific Islander Male (AAPI,M) 1 1 0% / Asian American Pacific

  7. Y YEAR

    National Nuclear Security Administration (NNSA)

    79 164 -8.38% ↓ YEAR 2013 2014 Males 100 92 -8.00% ↓ Females 79 72 -8.86% ↓ YEAR 2013 2014 SES 8 8 0% / EJ/EK 4 3 -25.00% ↓ EN 04 11 11 0% / EN 03 1 1 0% / EN 00 0 2 100% ↑ NN (Engineering) 39 32 -17.95% ↓ NQ (Prof/Tech/Admin) 111 104 -6.31% ↓ NU (Tech/Admin Support) 5 3 -40.00% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 1 2 100% ↑ American Indian Alaskan Native Female (AIAN,F) 2 1 -50.00% ↓ African American Male (AA,M) 4 3 -25.00% ↓ African American

  8. Y YEAR

    National Nuclear Security Administration (NNSA)

    40 36 -10.00% ↓ YEAR 2013 2014 Males 18 18 0% / Females 22 18 -18.18% ↓ YEAR 2013 2014 SES 3 2 -33.33% ↓ EJ/EK 1 1 0% / EN 03 1 1 0% / NN (Engineering) 3 3 0% / NQ (Prof/Tech/Admin) 30 27 -10.00% ↓ NU (Tech/Admin Support) 2 2 0% / YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 0 0 0% / African American Male (AA,M) 1 1 0% / African American Female (AA,F) 1 1 0% / Asian American Pacific Islander Male (AAPI,M) 0 0 0% /

  9. Y YEAR

    National Nuclear Security Administration (NNSA)

    4 30 -11.76% ↓ YEAR 2013 2014 Males 16 14 -12.50% ↓ Females 18 16 -11.11% ↓ YEAR 2013 2014 SES 1 1 0% / EJ/EK 3 1 -66.67% ↓ NQ (Prof/Tech/Admin) 29 27 -6.90% ↓ NU (Tech/Admin Support) 1 1 0% / YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 1 1 0% / American Indian Alaskan Native Female (AIAN,F) 2 2 0% / African American Male (AA,M) 3 3 0% / African American Female (AA,F) 7 6 -14.29% ↓ Asian American Pacific Islander Male (AAPI,M) 1 1 0% / Asian American Pacific Islander

  10. Y YEAR

    National Nuclear Security Administration (NNSA)

    9 209 -8.73% ↓ YEAR 2013 2014 Males 76 76 0% / Females 153 133 -13.07% ↓ YEAR 2013 2014 SES 9 6 -33.33% ↓ EJ/EK 1 1 0% / NQ (Prof/Tech/Admin) 208 194 -6.73% ↓ NU (Tech/Admin Support) 11 8 -27.27% ↓ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 2 2 0% / American Indian Alaskan Native Female (AIAN,F) 3 2 -33.33% ↓ African American Male (AA,M) 10 10 0% / African American Female (AA,F) 39 36 -7.69% ↓ Asian American Pacific Islander Male (AAPI,M) 1 1 0% / Asian American

  11. Y YEAR

    National Nuclear Security Administration (NNSA)

    7 80 -8.05% ↓ YEAR 2013 2014 Males 62 57 -8.06% ↓ Females 25 23 -8.00% ↓ YEAR 2013 2014 SES 1 1 0% / EJ/EK 3 3 0% / EN 05 1 1 0% / EN 04 27 24 -11.11% ↓ EN 03 1 0 -100% ↓ NN (Engineering) 26 25 -3.85% ↓ NQ (Prof/Tech/Admin) 26 24 -7.69% ↓ NU (Tech/Admin Support) 2 2 0% / YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 1 1 0% / American Indian Alaskan Native Female (AIAN,F) 1 1 0% / African American Male (AA,M) 3 2 -33.33% ↓ African American Female (AA,F) 3 3 0% / Asian

  12. Y YEAR

    National Nuclear Security Administration (NNSA)

    502 2381 -4.84% ↓ YEAR 2013 2014 Males 1663 1593 -4.21% ↓ Females 839 788 -6.08% ↓ YEAR 2013 2014 SES 104 90 -13.46% ↓ EX 2 4 100% ↑ SL 1 0 -100% ↓ EJ/EK 88 73 -17.05% ↓ EN 05 40 41 2.50% ↑ EN 04 169 157 -7.10% ↓ EN 03 18 21 100% ↑ EN 00 0 6 100% ↑ NN (Engineering) 441 416 -5.67% ↓ NQ (Prof/Tech/Admin) 1239 1190 -3.95% ↓ NU (Tech/Admin Support) 66 57 -13.64% ↓ NV (Nuc Mat Courier) 328 321 -2.13% ↓ GS 15 1 2 100% ↑ GS 13 2 2 0% / GS 10 3 1 -66.67% ↓ YEAR 2013

  13. Y YEAR

    National Nuclear Security Administration (NNSA)

    80 83 3.75% ↑ YEAR 2013 2014 Males 48 50 4.17% ↑ Females 32 33 3.13% ↑ YEAR 2013 2014 SES 2 1 -50.00% ↓ EJ/EK 8 7 -12.50% ↓ EN 04 11 9 -18.18% ↓ EN 03 1 1 0% / NN (Engineering) 24 27 12.50% ↑ NQ (Prof/Tech/Admin) 32 33 3.13% ↑ NU (Tech/Admin Support) 2 5 150% ↑ YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 3 3 0% / African American Male (AA,M) 0 0 0% / African American Female (AA,F) 2 2 0% / Asian American

  14. Y YEAR

    National Nuclear Security Administration (NNSA)

    8 27 -3.57% ↓ YEAR 2013 2014 Males 18 17 -5.56% ↓ Females 10 10 0% / YEAR 2013 2014 SES 1 1 0% / EN 05 1 1 0% / EN 04 4 3 -25.00% ↓ NN (Engineering) 12 12 0% / NQ (Prof/Tech/Admin) 9 9 0% / NU (Tech/Admin Support) 1 1 0% / YEAR 2013 2014 American Indian Alaska Native Male (AIAN,M) 0 0 0% / American Indian Alaskan Native Female (AIAN,F) 1 1 0% / African American Male (AA,M) 4 4 0% / African American Female (AA,F) 3 4 33.33% ↑ Asian American Pacific Islander Male (AAPI,M) 1 1 0% / Asian

  15. Truck and rail charges for shipping spent fuel and nuclear waste

    SciTech Connect (OSTI)

    McNair, G.W.; Cole, B.M.; Cross, R.E.; Votaw, E.F.

    1986-06-01

    The Pacific Northwest Laboratory developed techniques for calculating estimates of nuclear-waste shipping costs and compiled a listing of representative data that facilitate incorporation of reference shipping costs into varius logistics analyses. The formulas that were developed can be used to estimate costs that will be incurred for shipping spent fuel or nuclear waste by either legal-weight truck or general-freight rail. The basic data for this study were obtained from tariffs of a truck carrier licensed to serve the 48 contiguous states and from various rail freight tariff guides. Also, current transportation regulations as issued by the US Department of Transportation and the Nuclear Regulatory Commission were investigated. The costs that will be incurred for shipping spent fuel and/or nuclear waste, as addressed by the tariff guides, are based on a complex set of conditions involving the shipment origin, route, destination, weight, size, and volume and the frequency of shipments, existing competition, and the length of contracts. While the complexity of these conditions is an important factor in arriving at a ''correct'' cost, deregulation of the transportation industry means that costs are much more subject to negotiation and, thus, the actual fee that will be charged will not be determined until a shipping contract is actually signed. This study is designed to provide the baseline data necessary for making comparisons of the estimated costs of shipping spent fuel and/or nuclear wastes by truck and rail transportation modes. The scope of the work presented in this document is limited to the costs incurred for shipping, and does not include packaging, cask purchase/lease costs, or local fees placed on shipments of radioactive materials.

  16. A West Valley Demonstration Project Milestone - Achieving Certification to Ship Waste to the Nevada Test Site

    SciTech Connect (OSTI)

    Jackson, J. P.; Pastor, R. S.

    2002-02-28

    The West Valley Demonstration Project (WVDP) has successfully pretreated and vitrified nearly all of the 600,000 gallons of liquid high-level radioactive waste that was generated at the site of the only commercial nuclear fuel reprocessing plant to have operated in the United States. Low-level waste (LLW) generated during the course of the cleanup effort now requires disposal. Currently the WVDP only ships Class A LLW for off-site disposal. It has been shipping Class A wastes to Envirocare of Utah, Inc. since 1997. However, the WVDP may also have a future need to ship Class B and Class C waste, which Envirocare is not currently authorized to accept. The Nevada Test Site (NTS), a U.S. Department of Energy (DOE) facility, can accept all three waste classifications. The WVDP set a goal to receive certification to begin shipping Class A wastes to NTS by 2001. Formal certification/approval was granted by the DOE Nevada Operations Office on July 12, 2001. This paper discusses how the WVDP contractor, West Valley Nuclear Services Company (WVNSCO), completed the activities required to achieve NTS certification in 2001 to ship waste to its facility. The information and lessons learned provided are significant because the WVDP is the only new generator receiving certification based on an NTS audit in January 2001 that resulted in no findings and only two observations--a rating that is unparalleled in the DOE Complex.

  17. Year Modules

    U.S. Energy Information Administration (EIA) Indexed Site

    Annual photovoltaic module shipments, 2004-2014 (peak kilowatts) Year Modules 2004 143,274 2005 204,996 2006 320,208 2007 494,148 2008 920,693 2009 1,188,879 2010 2,644,498 2011 3,772,075 2012 4,655,005 2013 4,984,881 2014 6,237,524 Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report.' Note: Includes both U.S. Shipments and Exports.

  18. Year Modules

    U.S. Energy Information Administration (EIA) Indexed Site

    dollars per peak watt) Year Modules 2004 $2.99 2005 $3.19 2006 $3.50 2007 $3.37 2008 $3.49 2009 $2.79 2010 $1.96 2011 $1.59 2012 $1.15 2013 $0.75 2014 $0.87 Table 4. Average value of photovoltaic modules, 2004-2014 Source: U.S. Energy Information Administration, Form EIA-63B, 'Annual Photovoltaic Cell/Module Shipments Report.' Note: Dollars are not adjusted for inflation.

  19. State of Nevada comments on the OCRWM from-reactor spent fuel shipping cask preliminary design reports

    SciTech Connect (OSTI)

    Halstead, R.J.; Audin, L.; Hoskins, R.E.; Snedeker, D.F.

    1990-12-01

    The design of spent fuels shipping casks is described. Two casks from two different contractors are presented. The design needs are based on the OCRWM'S program specifications. (CBS)

  20. Microsoft Word - Los Alamos National Laboratory ships remote-handled transuranic waste to WIPP

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Los Alamos National Laboratory Ships Remote-Handled Transuranic Waste to WIPP CARLSBAD, N.M., June 3, 2009 - Cleanup of the nation's defense-related transuranic (TRU) waste has reached an important milestone. Today, the first shipment of remote-handled (RH) TRU waste from Los Alamos National Laboratory (LANL) in New Mexico arrived safely at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) in the southeast corner of the state. "Shipping this waste to WIPP is important

  1. [Ship-Source Oil Pollution Fund (Canada)]. Annual report, 1997--1998

    SciTech Connect (OSTI)

    1998-12-31

    This paper is the annual report of the Fund, established by amendment to the Canada Shipping Act in April 1989. This report presents information on new legislation, contributions to the International Oil Pollution Compensation Fund, and summaries of oil spill incidents.

  2. Hanford Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Shipped Four Months Ahead of Schedule

    Broader source: Energy.gov [DOE]

    RICHLAND, WASH. – The U.S. Department of Energy (DOE) at Hanford surpassed a Tri-Party Agreement Milestone by four months in shipping 1,000 cubic meters of transuranic waste off the Hanford Site in route to the Waste Isolation Pilot Plant (WIPP) in New Mexico before September 30, 2011.

  3. STATUS REPORT FOR AGING STUDIES OF EPDM O-RING MATERIAL FOR THE H1616 SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Stefek, T.; Daugherty, W.; Skidmore, E.

    2012-08-31

    This is an interim status report for tasks carried out per Task Technical Plan SRNL-STI-2011-00506. A series of tasks/experiments are being performed at the Savannah River National Laboratory to monitor the aging performance of ethylene propylene diene monomer (EPDM) Orings used in the H1616 shipping package. The data will support the technical basis to extend the annual maintenance of the EPDM O-rings in the H1616 shipping package and to predict the life of the seals at bounding service conditions. Current expectations are that the O-rings will maintain a seal at bounding normal temperatures in service (152 F) for at least 12 months. The baseline aging data review suggests that the EPDM O-rings are likely to retain significant mechanical properties and sealing force at bounding service temperatures to provide a service life of at least 2 years. At lower, more realistic temperatures, longer service life is likely. Parallel compression stress relaxation and vessel leak test efforts are in progress to further validate this assessment and quantify a more realistic service life prediction. The H1616 shipping package O-rings were evaluated for baseline property data as part of this test program. This was done to provide a basis for comparison of changes in material properties and performance parameters as a function of aging. This initial characterization was limited to physical and mechanical properties, namely hardness, thickness and tensile strength. These properties appear to be consistent with O-ring specifications. Three H1616-1 Containment Vessels were placed in test conditions and are aging at temperatures ranging from 160 to 300 F. The vessels were Helium leak-tested initially and have been tested at periodic intervals after cooling to room temperature to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97 (< 1E-07 std cc air/sec at room temperature). To date, no leak test failures have occurred. The cumulative time at

  4. Multi-tiered sensing and data processing for monitoring ship structures

    SciTech Connect (OSTI)

    Farrar, Charles; Salvino, Liming; Lynch, Jerome; Brady, Thomas

    2009-01-01

    A comprehensive structural health monitoring (SHM) system is a critical mechanism to ensure hull integrity and evaluate structural performance over the life of a ship, especially for lightweight high-speed ships. One of the most important functions of a SHM system is to provide real-time performance guidance and reduce the risk of structural damage during operations at sea. This is done by continuous feedback from onboard sensors providing measurements of seaway loads and structural responses. Applications of SHM should also include diagnostic capabilities such as identifying the presence of damage, assessing the location and extent of damage when it does occur in order to plan for future inspection and maintenance. The development of such SHM systems is extremely challenging because of the physical size of these structures, the widely varying and often extreme operational and environmental conditions associated with the missions of high performance ships, the lack of data from known damage conditions, the limited sensing that was not designed specifically for SHM, the management of the vast amounts of data, and the need for continued, real-time data processing. This paper will discuss some of these challenges and several outstanding issues that need to be addressed in the context of applying various SHM approaches to sea trials data measured on an aluminum high-speed catamaran, the HSV-2 Swift. A multi-tiered approach for sensing and data processing will be discussed as potential SHM architecture for future shipboard application. This approach will involve application of low cost and dense sensor arrays such as wireless communications in selected areas of the ship hull in addition to conventional sensors measuring global structural response of the ship. A recent wireless hull monitoring demo on FSF-I SeaFighter will be discussed as an example to show how this proposed architecture is a viable approach for long-term and real-time hull monitoring.

  5. EXAMINATION OF FIBERBOARD FROM SHIPPING PACKAGE 9975-01819

    SciTech Connect (OSTI)

    Daugherty, W

    2009-04-14

    Upon opening package 9975-01819 following approximately 5.5 years storage in KAMS, it was observed that the fiberboard was moldy, and the total height of the fiberboard assemblies was less than normal. Observations and measurements have since been made on three subsequent occasions. The available information indicates that the package contained approximately 2.5 liters of water in excess of what would normally exist within the fiberboard. This excess moisture led to a significant loss of fiberboard strength, the subsequent compression of the bottom layers, and the growth of mold observed on both the upper and lower fiberboard assemblies. In its current state, the fiberboard from this package retains a density (related to the criticality control function) within the range measured in other packages. The amount of excess moisture present is modest throughout most of the fiberboard, and its effect on thermal conductivity should be small. The thermal conductivity should increase significantly only near the bottom of the lower fiberboard assembly where the majority of excess moisture was found. The impact absorption capability is affected, and the ability of the fiberboard to perform this function in the current state must be evaluated. The longer such a condition persists, the greater the impact on fiberboard mechanical properties.

  6. Code System to Calculate Radiation Dose Rates Relative to Spent Fuel Shipping Casks.

    Energy Science and Technology Software Center (OSTI)

    1993-05-20

    Version 00 QBF calculates and plots in a short running time, three dimensional radiation dose rate distributions in the form of contour maps on specified planes resulting from cylindrical sources loaded into vehicles or ships. Shielding effects by steel walls and shielding material layers are taken into account in addition to the shadow effect among casks. This code system identifies the critical points on which to focus when designing the radiation shielding structure and wheremore » each of the spent fuel shipping casks should be stored. The code GRAPH reads the output data file of QBF and plots it using the HGX graphics library. QBF unifies the functions of the SMART and MANYCASK codes included in CCC-482.« less

  7. USING A CONTAINMENT VESSEL LIFTING APPARATUS FOR REMOTE OPERATIONS OF SHIPPING PACKAGES

    SciTech Connect (OSTI)

    Loftin, Bradley; Koenig, Richard

    2013-08-08

    The 9977 and the 9975 shipping packages are used in various nuclear facilities within the Department of Energy. These shipping packages are often loaded in designated areas with designs using overhead cranes or A-frames with lifting winches. However, there are cases where loading operations must be performed in remote locations where these facility infrastructures do not exist. For these locations, a lifting apparatus has been designed to lift the containment vessels partially out of the package for unloading operations to take place. Additionally, the apparatus allows for loading and closure of the containment vessel and subsequent pre-shipment testing. This paper will address the design of the apparatus and the challenges associated with the design, and it will describe the use of the apparatus.

  8. 9975 SHIPPING PACKAGE PERFORMANCE OF ALTERNATE MATERIALS FOR LONG-TERM STORAGE APPLICATION

    SciTech Connect (OSTI)

    Skidmore, E.; Hoffman, E.; Daugherty, W.

    2010-02-24

    The Model 9975 shipping package specifies the materials of construction for its various components. With the loss of availability of material for two components (cane fiberboard overpack and Viton{reg_sign} GLT O-rings), alternate materials of construction were identified and approved for use for transport (softwood fiberboard and Viton{reg_sign} GLT-S O-rings). As these shipping packages are part of a long-term storage configuration at the Savannah River Site, additional testing is in progress to verify satisfactory long-term performance of the alternate materials under storage conditions. The test results to date can be compared to comparable results on the original materials of construction to draw preliminary conclusions on the performance of the replacement materials.

  9. Conceptual design of the Clinch River Breeder Reactor spent-fuel shipping cask

    SciTech Connect (OSTI)

    Pope, R B; Diggs, J M [eds.

    1982-04-01

    Details of a baseline conceptual design of a spent fuel shipping cask for the Clinch River Breeder Reactor (CRBR) are presented including an assessment of shielding, structural, thermal, fabrication and cask/plant interfacing problems. A basis for continued cask development and for new technological development is established. Alternates to the baseline design are briefly presented. Estimates of development schedules, cask utilization and cost schedules, and of personnel dose commitments during CRBR in-plant handling of the cask are also presented.

  10. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container

    SciTech Connect (OSTI)

    Box, W.D.; Shappert, L.B.; Seagren, R.D.; Klima, B.B.; Jurgensen, M.C.; Hammond, C.R.; Watson, C.D.

    1980-01-01

    An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable regulations.

  11. Study on structural damage of ships due to collision and grounding

    SciTech Connect (OSTI)

    Kuroiwa, T.; Nakamura, T.; Kawamoto, Y.; Kondo, M.; Kusuba, S.

    1994-12-31

    In this paper, structural failure of tankers due to collisions and groundings is studied. To investigate failure mechanism and energy absorption capacity of ship structures. Experiments and numerical simulations are carried out. In the numerical simulations, failure of fillet welds and rupture of plates are taken into account. To investigate structural integrity of Mid-Deck Tanker, which was newly developed to reduce accidental oil outflow, numerical simulations of grounding of the tanker are performed.

  12. EM Delivers in Deactivation, Regulatory Milestones, Shipping Progress at Portsmouth Site

    Broader source: Energy.gov [DOE]

    PIKETON, Ohio – EM’s Portsmouth/Paducah Project Office (PPPO) made significant strides in the Portsmouth site’s decontamination and decommissioning (D&D) project in 2014, including deactivation progress in one of the plant’s three main uranium enrichment process buildings, the issuance of two proposed plans for the two Records of Decision (RODs) that will drive D&D work, and a rigorous shipping campaign.

  13. Test plan/procedure for the SPM-1 shipping container system. Revision 0

    SciTech Connect (OSTI)

    Flanagan, B.D.

    1995-07-01

    The 49 CFR 173.465 Type A packaging tests will verify that SPM-1 will provide adequate protection and pass as a Type A package. Test will determine that the handle of the Pig will not penetrate through the plywood spacer and rupture the shipping container. Test plan/procedure provides planning, pre-test, setup, testing, and post-testing guidelines and procedures for conducting the {open_quotes}Free Drop Test{close_quotes} procedure for the SPM-1 package.

  14. Maintenance manual for the Beneficial Uses Shipping System cask. Revision 1

    SciTech Connect (OSTI)

    Bronowski, D.R.; Yoshimura, H.R.

    1993-05-01

    This document is the Maintenance Manual for the Beneficial Uses Shipping System (BUSS) cask. These instructions address requirements for maintenance, inspection, testing, and repair, supplementing general information found in the BUSS Safety Analysis Report for Packaging (SARP), SAND 83-0698. Use of the BUSS cask is authorized by the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC) for the shipment of special form cesium chloride or strontium flouride capsules.

  15. Feasibility study on the verification of fresh fuel assemblies in shipping containers

    SciTech Connect (OSTI)

    Swinth, K.L.; Tanner, J.E.

    1990-09-01

    The purpose of this study was to examine the feasibility of using various nondestructive measurement techniques to determine the presence of fuel assemblies inside shipping containers and to examine the feasibility of measuring the fissile content of the containers. Passive and active techniques based on both gamma and neutron assay were examined. In addition, some experiments and calculations were performed to evaluate neutron techniques. Passive counting of the 186 keV gamma from {sup 235}U is recommended for use as an attributes measurement technique. Experiments and studies indicated that a bismuth germanate (BGO) scintillator is the preferred detector. A properly designed system based on this detector will provide a compact detector that can selectively verify fuel assemblies within a shipping container while the container is in a stack of similarly loaded containers. Missing fuel assemblies will be readily detected, but gamma counting of assemblies cannot detect changes in the fissile content of the inner rods in an assembly. If a variables technique is required, it is recommended that more extensive calculations be performed and removal of the outer shipping container be considered. Marking (sealing) of the assemblies with a uniquely identifiable transponder was also considered. This would require the development of procedures that would assure proper application and removal of the seal. When change to a metal outer container occurs, the technique will no longer be useful unless a radiolucent window is included in the container. 20 refs., 7 figs., 2 tabs.

  16. DEMONSTRATION OF EQUIVALENCY OF CANE AND SOFTWOOD BASED CELOTEX FOR MODEL 9975 SHIPPING PACKAGES

    SciTech Connect (OSTI)

    Watkins, R; Jason Varble, J

    2008-05-27

    Cane-based Celotex{trademark} has been used extensively in various Department of Energy (DOE) packages as a thermal insulator and impact absorber. Cane-based Celotex{trademark} fiberboard was only manufactured by Knight-Celotex Fiberboard at their Marrero Plant in Louisiana. However, Knight-Celotex Fiberboard shut down their Marrero Plant in early 2007 due to impacts from hurricane Katrina and other economic factors. Therefore, cane-based Celotex{trademark} fiberboard is no longer available for use in the manufacture of new shipping packages requiring the material as a component. Current consolidation plans for the DOE Complex require the procurement of several thousand new Model 9975 shipping packages requiring cane-based Celotex{trademark} fiberboard. Therefore, an alternative to cane-based Celotex{trademark} fiberboard is needed. Knight-Celotex currently manufactures Celotex{trademark} fiberboard from other cellulosic materials, such as hardwood and softwood. A review of the relevant literature has shown that softwood-based Celotex{trademark} meets all parameters important to the Model 9975 shipping package.

  17. Solar UV radiation exposure of seamen - Measurements, calibration and model calculations of erythemal irradiance along ship routes

    SciTech Connect (OSTI)

    Feister, Uwe; Meyer, Gabriele; Kirst, Ulrich

    2013-05-10

    Seamen working on vessels that go along tropical and subtropical routes are at risk to receive high doses of solar erythemal radiation. Due to small solar zenith angles and low ozone values, UV index and erythemal dose are much higher than at mid-and high latitudes. UV index values at tropical and subtropical Oceans can exceed UVI = 20, which is more than double of typical mid-latitude UV index values. Daily erythemal dose can exceed the 30-fold of typical midlatitude winter values. Measurements of erythemal exposure of different body parts on seamen have been performed along 4 routes of merchant vessels. The data base has been extended by two years of continuous solar irradiance measurements taken on the mast top of RV METEOR. Radiative transfer model calculations for clear sky along the ship routes have been performed that use satellite-based input for ozone and aerosols to provide maximum erythemal irradiance and dose. The whole data base is intended to be used to derive individual erythemal exposure of seamen during work-time.

  18. State of Nevada comments on the OCRWM from-reactor spent fuel shipping cask preliminary design reports

    SciTech Connect (OSTI)

    Halstead, R.J.; Audin, L.; Hoskins, R.E.; Snedeker, D.F.

    1990-12-01

    The design of spent fuels shipping casks is described. Two casks from two different contractors are presented. The design needs are based on the OCRWM`S program specifications. (CBS)

  19. Compensation of Wave-Induced Motion and Force Phenomena for Ship-Based High Performance Robotic and Human Amplifying Systems

    SciTech Connect (OSTI)

    Love, LJL

    2003-09-24

    The decrease in manpower and increase in material handling needs on many Naval vessels provides the motivation to explore the modeling and control of Naval robotic and robotic assistive devices. This report addresses the design, modeling, control and analysis of position and force controlled robotic systems operating on the deck of a moving ship. First we provide background information that quantifies the motion of the ship, both in terms of frequency and amplitude. We then formulate the motion of the ship in terms of homogeneous transforms. This transformation provides a link between the motion of the ship and the base of a manipulator. We model the kinematics of a manipulator as a serial extension of the ship motion. We then show how to use these transforms to formulate the kinetic and potential energy of a general, multi-degree of freedom manipulator moving on a ship. As a demonstration, we consider two examples: a one degree-of-freedom system experiencing three sea states operating in a plane to verify the methodology and a 3 degree of freedom system experiencing all six degrees of ship motion to illustrate the ease of computation and complexity of the solution. The first series of simulations explore the impact wave motion has on tracking performance of a position controlled robot. We provide a preliminary comparison between conventional linear control and Repetitive Learning Control (RLC) and show how fixed time delay RLC breaks down due to the varying nature wave disturbance frequency. Next, we explore the impact wave motion disturbances have on Human Amplification Technology (HAT). We begin with a description of the traditional HAT control methodology. Simulations show that the motion of the base of the robot, due to ship motion, generates disturbances forces reflected to the operator that significantly degrade the positioning accuracy and resolution at higher sea states. As with position-controlled manipulators, augmenting the control with a Repetitive

  20. Nuclear Criticality Safety Evaluation of the 9965, 9968, 9972, 9973, 9974, and 9975 Shipping Casks

    SciTech Connect (OSTI)

    Frost, R.L.

    1999-02-26

    A Nuclear Criticality Safety Evaluation (NCSE) has been performed for the 9965, 9968, 9972, 9973, 9974, and 9975 SRS-designed shipping casks. This was done in support of the recertification effort for the 9965 and 9968, and the certification of the newly designed 9972-9975 series. The analysis supports the use of these packages as Fissile Class I for shipment of fissionable material from the SRS FB-Line, HB-Line, and from Lawrence Livermore national Laboratory. six different types of material were analyzed with varying Isotopic composition, of both oxide and metallic form. The mass limits required to support the fissile Class I rating for each of the envelopes are given in the Table below. These mass limits apply if DOE approves an exception as described in 10 CFR 71.55(c), such that water leakage into the primary containment vessel does not need to be considered in the criticality analysis. If this exception is not granted, the mass limits are lower than those shown below. this issue is discussed in detail in sections 5 and 6 of the report.One finding from this work is important enough to highlight in the abstract. The fire tests performed for this family of shipping casks indicates only minimal charring of the Celotex thermal insulation. Analysis of the casks with no Celotex insulation (assuming it has all burned away), results in values of k-eff that exceed 1.0. Therefore, the Celotex insulation must remain intact in order to guarantee sub criticality of the 9972-9975 family of shipping casks.

  1. Safety Analysis Report for Packaging: The unirradiated fuel shipping container USA/9853/AF

    SciTech Connect (OSTI)

    Not Available

    1991-10-18

    The HFBR Unirradiated Fuel Shipping Container was designed and fabricated at the Oak Ridge National Laboratory in 1978 for the transport of fuel for the High Flux Beam Reactor (HFBR) for Brookhaven National Laboratory. The package has been evaluated analytically, as well as the comparison to tests on similar packages, to demonstrate compliance with the applicable regulations governing packages in which radioactive and fissile materials are transported. The contents of this Safety Analysis Report for Packaging (SARP) are based on Regulatory Guide 7.9 (proposed Revision 2 - May 1986), 10 CFR Part 71, DOE Order 1540.2, DOE Order 5480.3, and 49 CFR Part 173.

  2. REVIEW OF CLEANING SOLUTIONS FOR USE ON COMPONENTS OF THE 9975 SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Daugherty, W.

    2013-09-30

    Several candidate cleaning products have been reviewed for use as a disinfectant on 9975 shipping package components which contain or have contacted mold. Following review of the compatibility of these products with each component, ammonia (ammonium hydroxide diluted to 1.5 wt% concentration) appears compatible with all package components that it might contact. Each of the other candidate products is incompatible with one or more package components. Accordingly, ammonia is recommended for this purpose. It is further recommended that all components which are disinfected be subsequently rinsed with di-ionized or distilled water.

  3. Idaho Site Completes Cleanup with Help from Workers who Shipped Waste Decades Ago

    Office of Environmental Management (EM)

    October 6, 2011 Idaho Site Completes Cleanup with Help from Workers who Shipped Waste Decades Ago IDAHO FALLS, Idaho - From the 1950s until the 1980s, workers at the former Rocky Flats Plant near Denver, Colo., sent hundreds of thousands of barrels and boxes of radioactive and hazardous waste to the Idaho National Laboratory (INL) for disposal both above and below ground. Now, some of those who sent the Cold War weapons waste to Idaho are helping identify the waste in pits dug up for the first

  4. Standardized DOE Spent Nuclear Fuel Canister and Transportation System for Shipping to the National Repository

    SciTech Connect (OSTI)

    Pincock, David Lynn; Morton, Dana Keith; Lengyel, Arpad Leslie

    2001-02-01

    The U.S.Department of Energys (DOE) National Spent Nuclear Fuel Program (NSNFP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), has been chartered with the responsibility for developing spent nuclear fuel (SNF) standardized canisters and a transportation cask system for shipping DOE SNF to the national repository. The mandate for this development is outlined in the Memorandum of Agreement for Acceptance of Department of Energy Spent Nuclear Fuel and High-Level Radioactive Waste that states, EM shall design and fabricate DOE SNF canisters for shipment to RW. (1) It also states, EM shall be responsible for the design, NRC certification, and fabrication of the transportation cask system for DOE SNF canisters or bare DOE SNF in accordance with 10 CFR Part 71. (2) In fulfillment of these requirements, the NSNFP has developed four SNF standardized canister configurations and has conceptually designed a versatile transportation cask system for shipping the canisters to the national repository.1 The standardized canister sizes were derived from the national repository waste package design for co-disposal of SNF with high-level waste (HLW). One SNF canister can be placed in the center of the waste package or one can be placed in one of five radial positions, replacing a HLW canister. The internal cavity of the transportation cask was derived using the same logic, matching the size of the internal cavity of the waste package. The size of the internal cavity for the transportation cask allows the shipment of multiple canister configurations with the application of a removable basket design. The standardized canisters have been designed to be loaded with DOE SNF, placed into interim storage, shipped to the national repository, and placed in a waste package without having to be reopened. Significant testing has been completed that clearly demonstrates that the standardized canisters can safely achieve their intended design goals. The

  5. Idaho Cleanup Project ships first Recovery Act-funded remote-handled

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    transuranic waste out of Idaho THE IDAHO SITE NEWS MEDIA CONTACT: Danielle Miller (DOE-ID) 208-526-5709 Joseph Campbell (CWI) 208-360-0142 For Immediate Release March 18, 2010 Idaho Cleanup Project ships first Recovery Act- funded remote-handled transuranic waste out of Idaho DATELINE - The Idaho Cleanup Project made its first shipment of remote-handled transuranic waste funded by the American Recovery and Reinvestment Act on March 11, 2010. This is the first of approximately 150 shipments

  6. HPSS Yearly Network Traffic

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    HPSS Yearly Network Traffic HPSS Yearly Network Traffic Yearly Summary of IO Traffic Between Storage and Network Destinations These bar charts show the total transfer traffic for...

  7. Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 2, Rev. 14

    SciTech Connect (OSTI)

    1994-10-01

    This appendix determines the effective G values for payload shipping categories of contact handled transuranic (CH-TRU) waste materials, based on the radiolytic G values for waste materials that are discussed in detail in Appendix 3.6.8 of the Safety Analysis Report for the TRUPACT-II Shipping Package. The effective G values take into account self-absorption of alpha decay energy inside particulate contamination and the fraction of energy absorbed by nongas-generating materials. As described in Appendix 3.6.8, an effective G value, G{sub eff}, is defined by: G{sub eff} - {Sigma}{sub M} (F{sub M} x G{sub M}) F{sub M}-fraction of energy absorbed by material maximum G value for a material where the sum is over all materials present inside a waste container. The G value itself is determined primarily by the chemical properties of the material and its temperature. The value of F is determined primarily by the size of the particles containing the radionuclides, the distribution of radioactivity on the various materials present inside the waste container, and the stopping distance of alpha particles in air, in the waste materials, or in the waste packaging materials.

  8. Simulation and analysis of the plutonium shipping container subject to 30-foot drops

    SciTech Connect (OSTI)

    Gong, C.; Gupta, N.K.; Gromada, R.J.

    1995-12-31

    The shipping container 5320 is a shipping package for radioactive materials. In order to maintain the component in this packaging within the sub-critical state when subjected to any kind of Hypothetical Accident conditions (HAC), this Type B packaging is designed with various impact limiters. The present study is to examine the energy absorbing capacity of the impact limiter design of this container subjected to a 30-foot drop onto a flat unyielding horizontal surface in each of the three critical dropping orientations. This paper presents the results of a three dimensional nonlinear dynamic impact analysis. This analysis shows the deformed configuration of the container caused by the impact and also determines the effects of different stress wave paths in three distinct drops on the stress states in the critical component. The solution to the problem was obtained using the ABAQUS (explicit) finite element computer code. The nonlinearity of this analysis involves large structural deformation, elasto-plastic materials with strain hardening as well as multiple contact interfaces. Three drop orientations were studied, namely, top down impact, bottom down impact and side impact. Results will be compared against actual drop test data.

  9. Documentation for initial testing and inspections of Beneficial Uses Shipping System (BUSS) Cask

    SciTech Connect (OSTI)

    Lundeen, J.E.

    1994-08-25

    The purpose of this report is to compile data generated during the initial tests and inspections of the Beneficial Uses Shipping System (BUSS) Cask. In addition, this report will verify that the testing criteria identified in section 8.1 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met. The BUSS Cask Model R-1 is a type B shipping container used for shipment of radioactive cesium-137 and strontium-90 capsules to Waste Encapsulation and Storage Facility (WESF). The BUSS Cask body and lid are each one-piece forgings fabricated from ASTM A473, Type 304 stainless steel. The primary purpose of the BUSS Cask is to provide shielding and confinement as well as impact, puncture, and thermal protection for the capsules under both normal and accident conditions. Chapter 8 of the BUSS Cask SARP requires several acceptance tests and inspections, each intended to evaluate the performance of different components of the BUSS Cask system, to be performed before its first use. The results of the tests and inspections required are included in this document.

  10. AGING BEHAVIOR OF VITON O-RING SEALS IN THE 9975 SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Skidmore, E.; Daugherty, W.; Hoffman, E.; Dunn, K.; Bellamy, S.

    2012-01-13

    The Savannah River Site (SRS) is storing plutonium (Pu) materials in the K-Area Materials Storage (KAMS) facility. The Pu materials were packaged according to the DOE-STD-3013 standard and shipped to the SRS in Type B 9975 packages. The robust 9975 shipping package was not designed for long-term product storage, but it is a specified part of the storage configuration and the KAMS facility safety basis credits the 9975 design with containment. Within the 9975 package, nested stainless steel containment vessels are closed with dual O-ring seals based on Viton{reg_sign} GLT or GLT-S fluoroelastomer. The aging behavior of the O-ring compounds is being studied to provide the facility with advanced notice of nonconformance and to develop life prediction models. A combination of field surveillance, leak testing of surrogate fixtures aged at bounding service temperatures, and accelerated-aging methodologies based on compression stress-relaxation and oxygen consumption analysis is being used to evaluate seal performance. A summary of the surveillance program relative to seal aging behavior is presented.

  11. Deployment and Operation of the ES-3100 Type B Shipping Container

    SciTech Connect (OSTI)

    Arbital, J. G.; Tousley, D. R.: Miller, D. B.

    2006-07-27

    The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA) is shipping, for disposition purposes, bulk quantities of fissile materials, primarily highly enriched uranium (HEU). The U.S. Department of Transportation (DOT) specification 6M container has been the workhorse for NNSA and many other shippers of radioactive material since the 1980s. However, the 6M does not conform to the packaging requirements in the Code of Federal Regulations (10 CFR 71) and, for that reason, is being phased out for use in the DOE secure transportation system by the end of 2006. BWXT Y-12 developed and licensed the ES-3100 container to replace the DOT 6M. The ES-3100 was certified by the Nuclear Regulatory Commission (NRC) in April 2006. The process of deploying the new package began in June 2005 and is planned to be completed in July 2006. The package will be fully operational and completely replace the DOT 6M at the Y-12 National Security Complex (Y-12) by October 2006. This paper reviews the deployment process and the mock loading station that was installed at National Transportation Research Center (NTRC) of Oak Ridge National Laboratory. Specialized equipment, tools, and instrumentation that support the handling and loading operations of the ES-3100 are described in detail. Loading options for other user sites are explored in preparation for deployment of this new state-of-the-art shipping container throughout the DOE complex and the private sector.

  12. PCP METHODOLOGY FOR DETERMINING DOSE RATES FOR SMALL GRAM QUANTITIES IN SHIPPING PACKAGINGS

    SciTech Connect (OSTI)

    Nathan, S.

    2011-08-23

    The Small Gram Quantity (SGQ) concept is based on the understanding that small amounts of hazardous materials, in this case radioactive materials, are significantly less hazardous than large amounts of the same materials. This study describes a methodology designed to estimate an SGQ for several neutron and gamma emitting isotopes that can be shipped in a package compliant with 10 CFR Part 71 external radiation level limits regulations. These regulations require packaging for the shipment of radioactive materials perform, under both normal and accident conditions, the essential functions of material containment, subcriticality, and maintain external radiation levels within regulatory limits. 10 CFR 71.33(b)(1)(2)&(3) state radioactive and fissile materials must be identified and their maximum quantity, chemical and physical forms be included in an application. Furthermore, the U.S. Federal Regulations require application contain an evaluation demonstrating the package (i.e., the packaging and its contents) satisfies the external radiation standards for all packages (10 CFR 71.31(2), 71.35(a), & 71.47). By placing the contents in a He leak-tight containment vessel, and limiting the mass to ensure subcriticality, the first two essential functions are readily met. Some isotopes emit sufficiently strong photon radiation that small amounts of material can yield a large external dose rate. Quantifying of the dose rate for a proposed content is a challenging issue for the SGQ approach. It is essential to quantify external radiation levels from several common gamma and neutron sources that can be safely placed in a specific packaging, to ensure compliance with federal regulations. The Packaging Certification Program (PCP) Methodology for Determining Dose Rate for Small Gram Quantities in Shipping Packagings described in this report provides bounding mass limits for a set of proposed SGQ isotopes. Methodology calculations were performed to estimate external radiation levels

  13. HPSS Yearly Network Traffic

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    HPSS Yearly Network Traffic HPSS Yearly Network Traffic Yearly Summary of I/O Traffic Between Storage and Network Destinations These bar charts show the total transfer traffic for each year between storage and network destinations (systems within and outside of NERSC). Traffic for the current year is an estimate derived by scaling the known months traffic up to 12 months. The years shown are calendar years. The first graph shows the overall growth in network traffic to storage over the years.

  14. Experimental data base for estimating the consequences from a hypothetical sabotage attack on a spent fuel shipping cask

    SciTech Connect (OSTI)

    Sandoval, R.P.; Luna, R.E.

    1986-01-01

    This paper describes the results of a program conducted at Sandia National Laboratories for the US Department of Energy to provide an experimental data base for estimating the radiological health effects that could result from the sabotage of a light water reactor spent fuel shipping cask. The primary objectives of the program were limited to: (1) evaluating the effectiveness of selected high energy devices (HED) in breaching full-scale spent fuel shipping casks, (2) quantifying and characterizing relevant aerosol and radiological properties of the released fuel, and (3) using the resulting experimental data to evaluate the radiological health effects resulting from a hypothetical attack on a spent fuel shipping cask in a densely populated urban area. 3 refs.

  15. A GREEN'S FUNCTION APPROACH FOR DETERMINING DOSE RATES FOR SMALL GRAM QUANTITIES IN SHIPPING PACKAGINGS

    SciTech Connect (OSTI)

    Nathan, S.

    2012-06-14

    The Small Gram Quantity (SGQ) concept is based on the understanding that small amounts of hazardous materials, in this case radioactive materials (RAM), are significantly less hazardous than large amounts of the same materials. This paper describes a methodology designed to estimate an SGQ for several neutron and gamma emitting isotopes that can be shipped in a package in compliance with 10 CFR Part 71 external radiation level limits regulations. The neutron and photon sources were calculated using both ORIGEN-S and RASTA. The response from a unit source in each neutron and photon group was calculated using MCNP5 with each unshielded and shielded container configuration. Effects of self-shielding on both neutron and photon response were evaluated by including either plutonium oxide or iron in the source region for the case with no shielded container. For the cases of actinides mixed with light elements, beryllium is the bounding light element. The added beryllium (10 to 90 percent of the actinide mass) in the cases studied represents between 9 and 47 percent concentration of the total mixture mass. For beryllium concentrations larger than 50 percent, the increase in the neutron source term and dose rate tend to increase at a much lower rate than at concentrations lower than 50%. The intimately mixed actinide-beryllium form used in these models is very conservative and thus the limits presented in this report are practical bounds on the mass that can be safely shipped. The calculated dose rate from one gram of each isotope was then used to determin the maximum amount of a single isotope that could be shipped in the Model 9977 Package (or packagings having the same or larger external dimensions as well as similar structural materials) and have the external radiation level within the regulatory dose limits at the surface of the package. The estimates of the mass limits presented would also serve as conservative limits for both the Models 9975 and 9978 packages. If a

  16. PACKAGING CERTIFICATION PROGRAM METHODOLOGY FOR DETERMINING DOSE RATES FOR SMALL GRAM QUANTITIES IN SHIPPING PACKAGINGS

    SciTech Connect (OSTI)

    Nathan, S.; Loftin, B.; Abramczyk, G.; Bellamy, S.

    2012-05-09

    The Small Gram Quantity (SGQ) concept is based on the understanding that small amounts of hazardous materials, in this case radioactive materials (RAM), are significantly less hazardous than large amounts of the same materials. This paper describes a methodology designed to estimate an SGQ for several neutron and gamma emitting isotopes that can be shipped in a package compliant with 10 CFR Part 71 external radiation level limits regulations. These regulations require packaging for the shipment of radioactive materials, under both normal and accident conditions, to perform the essential functions of material containment, subcriticality, and maintain external radiation levels within the specified limits. By placing the contents in a helium leak-tight containment vessel, and limiting the mass to ensure subcriticality, the first two essential functions are readily met. Some isotopes emit sufficiently strong photon radiation that small amounts of material can yield a large dose rate outside the package. Quantifying the dose rate for a proposed content is a challenging issue for the SGQ approach. It is essential to quantify external radiation levels from several common gamma and neutron sources that can be safely placed in a specific packaging, to ensure compliance with federal regulations. The Packaging Certification Program (PCP) Methodology for Determining Dose Rate for Small Gram Quantities in Shipping Packagings provides bounding shielding calculations that define mass limits compliant with 10 CFR 71.47 for a set of proposed SGQ isotopes. The approach is based on energy superposition with dose response calculated for a set of spectral groups for a baseline physical packaging configuration. The methodology includes using the MCNP radiation transport code to evaluate a family of neutron and photon spectral groups using the 9977 shipping package and its associated shielded containers as the base case. This results in a set of multipliers for 'dose per particle' for

  17. Certification testing of the Los Alamos National Laboratory Heat Source/Radioisotopic Thermoelectric Generator shipping container

    SciTech Connect (OSTI)

    Bronowski, D.R.; Madsen, M.M.

    1991-09-01

    The Heat Source/Radioisotopic Thermoelectric Generator shipping counter is a Type B packaging currently under development by Los Alamos National Laboratory. Type B packaging for transporting radioactive material is required to maintain containment and shielding after being exposed to normal and hypothetical accident environments defined in Title 10 of the Code of Federal Regulations Part 71. A combination of testing and analysis is used to verify the adequacy of this packaging design. This report documents the testing portion of the design verification. Six tests were conducted on a prototype package: a water spray test, a 4-foot normal conditions drop test, a 30-foot drop test, a 40-inch puncture test, a 30-minute thermal test, and an 8-hour immersion test.

  18. Probabilistic assessment of spent fuel shipping cask response to severe transportation accident conditions. Report summary

    SciTech Connect (OSTI)

    Fischer, L.E.; Kimura, C.Y.; Witte, M.C.

    1985-01-01

    The licensing of commercial nuclear spent shipping casks in the United States is regulated by 10CFR71. In order to be licensed, casks must be designed not to fail under hypothetical test conditions specified in Appendix B of this regulation. Questions have been raised about the suitability of these tests in simulating actual transportation accident conditions. Our study addresses the adequacy of current regulations by comparing real-world accident conditions with regulatory test specifications using more complete accident statistics and more sophisticated structural analyses than have been used in studies to date. Our objective is to evaluate the protection provided by current regulations against severe accident conditions for commercial spent nuclear fuel casks that are transported by truck or rail. The complete spectrum of truck and rail accidents will be reviewed in order to determine the frequency (or infrequency) of cask failures during transportation accidents. 3 references, 1 figure.

  19. Space charge dosimeters for extremely low power measurements of radiation in shipping containers

    DOE Patents [OSTI]

    Britton, Jr.; Charles L.; Buckner, Mark A.; Hanson, Gregory R.; Bryan, William L.

    2011-04-26

    Methods and apparatus are described for space charge dosimeters for extremely low power measurements of radiation in shipping containers. A method includes in situ polling a suite of passive integrating ionizing radiation sensors including reading-out dosimetric data from a first passive integrating ionizing radiation sensor and a second passive integrating ionizing radiation sensor, where the first passive integrating ionizing radiation sensor and the second passive integrating ionizing radiation sensor remain situated where the dosimetric data was integrated while reading-out. Another method includes arranging a plurality of ionizing radiation sensors in a spatially dispersed array; determining a relative position of each of the plurality of ionizing radiation sensors to define a volume of interest; collecting ionizing radiation data from at least a subset of the plurality of ionizing radiation sensors; and triggering an alarm condition when a dose level of an ionizing radiation source is calculated to exceed a threshold.

  20. Space charge dosimeters for extremely low power measurements of radiation in shipping containers

    DOE Patents [OSTI]

    Britton, Jr., Charles L.; Buckner, Mark A.; Hanson, Gregory R.; Bryan, William L.

    2011-05-03

    Methods and apparatus are described for space charge dosimeters for extremely low power measurements of radiation in shipping containers. A method includes insitu polling a suite of passive integrating ionizing radiation sensors including reading-out dosimetric data from a first passive integrating ionizing radiation sensor and a second passive integrating ionizing radiation sensor, where the first passive integrating ionizing radiation sensor and the second passive integrating ionizing radiation sensor remain situated where the dosimetric data was integrated while reading-out. Another method includes arranging a plurality of ionizing radiation sensors in a spatially dispersed array; determining a relative position of each of the plurality of ionizing radiation sensors to define a volume of interest; collecting ionizing radiation data from at least a subset of the plurality of ionizing radiation sensors; and triggering an alarm condition when a dose level of an ionizing radiation source is calculated to exceed a threshold.

  1. Evaluation of dry versus wet unloading of spent nuclear fuel shipping casks

    SciTech Connect (OSTI)

    Allen, Jr., G. C.; Lambert, R. W.; Larkin, D. J.

    1980-01-01

    The Transportation Technology Center at Sandia National Laboratories completed an evaluation of unloading methods for spent fuel by sponsoring technical programs at Exxon Nuclear Company, Inc., and General Electric Corporation. These programs provided a comprehensive assessment of the relative merits, capabilities, and limitations of dry and wet unloading methods. The results of this evaluation, when continued, are expected to impact the development of future spent fuel and waste transportation systems. In addition, final conclusions of the evaluation will provide input to designers of future receiving and shipping interfaces at away-from-reactor spent fuel storage facilities and geologic nuclear waste repositories in the United States. The results presented here apply to the case where uncanistered spent fuel from light water reactors is to be handled. The conclusions may be different if uncontaminated canistered waste forms are considered in the future.

  2. Spent Nuclear Fuel Transportation: An Examination of Potential Lessons Learned From Prior Shipping Campaigns

    SciTech Connect (OSTI)

    Marsha Keister; Kathryn McBride

    2006-08-01

    The Nuclear Waste Policy Act of 1982 (NWPA), as amended, assigned the Department of Energy (DOE) responsibility for developing and managing a Federal system for the disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for accepting, transporting, and disposing of SNF and HLW at the Yucca Mountain repository in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. OCRWM faces a near-term challenge—to develop and demonstrate a transportation system that will sustain safe and efficient shipments of SNF and HLW to a repository. To better inform and improve its current planning, OCRWM has extensively reviewed plans and other documents related to past high-visibility shipping campaigns of SNF and other radioactive materials within the United States. This report summarizes the results of this review and, where appropriate, lessons learned.

  3. Destructive Testing of an ES-3100 Shipping Container at the Savannah River National Laboratory

    SciTech Connect (OSTI)

    Loftin, B.; Abramczyk, G.

    2015-06-09

    Destructive testing of an ES-3100 Shipping Container was completed by the Packaging Technology and Pressurized Systems organization within the Savannah River National Laboratory in order to qualify the ES-3100 as a candidate storage and transport package for applications at various facilities at the Savannah River Site. The testing consisted of the detonation of three explosive charges at separate locations on a single ES-3100. The locations for the placement were chosen based the design of the ES-3100 as well as the most likely places for the package to incur damage as a result of the detonation. The testing was completed at an offsite location, which raised challenges as well as allowed for development of new partnerships for this testing and for potential future testing. The results of the testing, the methods used to complete the testing, and similar, potential future work will be discussed.

  4. MODELING ASSUMPTIONS FOR THE ADVANCED TEST REACTOR FRESH FUEL SHIPPING CONTAINER

    SciTech Connect (OSTI)

    Rick J. Migliore

    2009-09-01

    The Advanced Test Reactor Fresh Fuel Shipping Container (ATR FFSC) is currently licensed per 10 CFR 71 to transport a fresh fuel element for either the Advanced Test Reactor, the University of Missouri Research Reactor (MURR), or the Massachusetts Institute of Technology Research Reactor (MITR-II). During the licensing process, the Nuclear Regulatory Commission (NRC) raised a number of issues relating to the criticality analysis, namely (1) lack of a tolerance study on the fuel and packaging, (2) moderation conditions during normal conditions of transport (NCT), (3) treatment of minor hydrogenous packaging materials, and (4) treatment of potential fuel damage under hypothetical accident conditions (HAC). These concerns were adequately addressed by modifying the criticality analysis. A tolerance study was added for both the packaging and fuel elements, full-moderation was included in the NCT models, minor hydrogenous packaging materials were included, and fuel element damage was considered for the MURR and MITR-II fuel types.

  5. 50 Years of Space

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    50 Years of Space science-innovationassetsimagesicon-science.jpg 50 Years of Space Since 1943, some of the world's smartest and most dedicated technical people have ...

  6. LANL Reaches Waste Shipment Milestone: Waste from Cold War-era weapons production being shipped to WIPP

    Broader source: Energy.gov [DOE]

    LOS ALAMOS, New Mexico, May 31, 2011 — Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy’s Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico.

  7. Spent Nuclear Fuel Trasportation: An Examination of Potential Lessons Learned From Prior Shipping Campaigns

    SciTech Connect (OSTI)

    M. Keister; K, McBride

    2006-08-28

    The Nuclear Waste Policy Act of 1982 (NWPA), as amended, assigned the Department of Energy (DOE) responsibility for developing and managing a Federal system for the disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for accepting, transporting, and disposing of SNF and HLW at the Yucca Mountain repository (if licensed) in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. OCRWM faces a near-term challenge--to develop and demonstrate a transportation system that will sustain safe and efficient shipments of SNF and HLW to a repository. To better inform and improve its current planning, OCRWM has extensively reviewed plans and other documents related to past high-visibility shipping campaigns of SNF and other radioactive materials within the United States. This report summarizes the results of this review and, where appropriate, lessons learned. The objective of this lessons learned study was to identify successful, best-in-class trends and commonalities from past shipping campaigns, which OCRWM could consider when planning for the development and operation of a repository transportation system. Note: this paper is for analytical and discussion purposes only, and is not an endorsement of, or commitment by, OCRWM to follow any of the comments or trends. If OCRWM elects to make such commitments at a future time, they will be appropriately documented in formal programmatic policy statements, plans and procedures. Reviewers examined an extensive study completed in 2003 by DOE's National Transportation Program (NTP), Office of Environmental Management (EM), as well as plans and documents related to SNF shipments since issuance of the NTP report. OCRWM examined specific planning, business, institutional and operating practices that have been identified by DOE, its transportation contractors

  8. Robust Solution to Difficult Hydrogen Issues When Shipping Transuranic Waste to the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    Countiss, S. S.; Basabilvazo, G. T.; Moody, D. C. III; Lott, S. A.; Pickerell, M.; Baca, T.; CH2M Hill; Tujague, S.; Svetlik, H.; Hannah, T.

    2003-02-27

    The Waste Isolation Pilot Plant (WIPP) has been open, receiving, and disposing of transuranic (TRU) waste since March 26, 1999. The majority of the waste has a path forward for shipment to and disposal at the WIPP, but there are about two percent (2%) or approximately 3,020 cubic meters (m{sup 3}) of the volume of TRU waste (high wattage TRU waste) that is not shippable because of gas generation limits set by the U.S. Nuclear Regulatory Commission (NRC). This waste includes plutonium-238 waste, solidified organic waste, and other high plutonium-239 wastes. Flammable gases are potentially generated during transport of TRU waste by the radiolysis of hydrogenous materials and therefore, the concentration at the end of the shipping period must be predicted. Two options are currently available to TRU waste sites for solving this problem: (1) gas generation testing on each drum, and (2) waste form modification by repackaging and/or treatment. Repackaging some of the high wattage waste may require up to 20:1 drum increase to meet the gas generation limits of less than five percent (5%) hydrogen in the inner most layer of confinement (the layer closest to the waste). (This is the limit set by the NRC.) These options increase waste handling and transportation risks and there are high costs and potential worker exposure associated with repackaging this high-wattage TRU waste. The U.S. Department of Energy (DOE)'s Carlsbad Field Office (CBFO) is pursuing a twofold approach to develop a shipping path for these wastes. They are: regulatory change and technology development. For the regulatory change, a more detailed knowledge of the high wattage waste (e.g., void volumes, gas generation potential of specific chemical constituents) may allow refinement of the current assumptions in the gas generation model for Safety Analysis Reports for Packaging for Contact-Handled (CH) TRU waste. For technology development, one of the options being pursued is the use of a robust container

  9. EXAMINE AND EVALUATE A PROCESS TO USE SALT CAVERNS TO RECEIVE SHIP BORNE LIQUEFIED NATURAL GAS

    SciTech Connect (OSTI)

    Michael M. McCall; William M. Bishop; D. Braxton Scherz

    2003-04-24

    The goal of the U.S. Department of Energy cooperative research project is to define, describe, and validate, a process to utilize salt caverns to receive and store the cargoes of LNG ships. The project defines the process as receiving LNG from a ship, pumping the LNG up to cavern injection pressures, warming it to cavern compatible temperatures, injecting the warmed vapor directly into salt caverns for storage, and distribution to the pipeline network. The performance of work under this agreement is based on U.S. Patent 5,511,905, and other U.S. and Foreign pending patent applications. The cost sharing participants in the research are The National Energy Technology Laboratory (U.S. Department of Energy), BP America Production Company, Bluewater Offshore Production Systems (U.S.A.), Inc., and HNG Storage, L.P. Initial results indicate that a salt cavern based receiving terminal could be built at about half the capital cost, less than half the operating costs and would have significantly higher delivery capacity, shorter construction time, and be much more secure than a conventional liquid tank based terminal. There is a significant body of knowledge and practice concerning natural gas storage in salt caverns, and there is a considerable body of knowledge and practice in handling LNG, but there has never been any attempt to develop a process whereby the two technologies can be combined. Salt cavern storage is infinitely more secure than surface storage tanks, far less susceptible to accidents or terrorist acts, and much more acceptable to the community. The project team developed conceptual designs of two salt cavern based LNG terminals, one with caverns located in Calcasieu Parish Louisiana, and the second in Vermilion block 179 about 50 miles offshore Louisiana. These conceptual designs were compared to conventional tank based LNG terminals and demonstrate superior security, economy and capacity. The potential for the development of LNG receiving terminals

  10. Solid waste 30-year volume summary

    SciTech Connect (OSTI)

    Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

    1994-06-01

    A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford`s Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m{sup 3} of LLMW and TRU/TRUM waste will be managed at Hanford`s SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m{sup 3} of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D&D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford`s future solid waste management requirements.