WorldWideScience

Sample records for berkelium 241

  1. New berkelium isotope: 242Bk

    International Nuclear Information System (INIS)

    A new isotope of berkelium, 242Bk, was produced with a cross section of approx. 10 μb in reactions of boron on uranium and nitrogen on thorium. It decays by electron capture with a half-life of 7 +- 1.3 minutes. The branching ratio for this isotope for alpha decay is less than 1% and that for spontaneous fission is less than 0.03%. 2 figures, 2 tables

  2. Characterization of berkelium(III) dipicolinate and borate compounds in solution and the solid state.

    Science.gov (United States)

    Silver, Mark A; Cary, Samantha K; Johnson, Jason A; Baumbach, Ryan E; Arico, Alexandra A; Luckey, Morgan; Urban, Matthew; Wang, Jamie C; Polinski, Matthew J; Chemey, Alexander; Liu, Guokui; Chen, Kuan-Wen; Van Cleve, Shelley M; Marsh, Matthew L; Eaton, Teresa M; van de Burgt, Lambertus J; Gray, Ashley L; Hobart, David E; Hanson, Kenneth; Maron, Laurent; Gendron, Frédéric; Autschbach, Jochen; Speldrich, Manfred; Kögerler, Paul; Yang, Ping; Braley, Jenifer; Albrecht-Schmitt, Thomas E

    2016-08-26

    Berkelium is positioned at a crucial location in the actinide series between the inherently stable half-filled 5f(7) configuration of curium and the abrupt transition in chemical behavior created by the onset of a metastable divalent state that starts at californium. However, the mere 320-day half-life of berkelium's only available isotope, (249)Bk, has hindered in-depth studies of the element's coordination chemistry. Herein, we report the synthesis and detailed solid-state and solution-phase characterization of a berkelium coordination complex, Bk(III)tris(dipicolinate), as well as a chemically distinct Bk(III) borate material for comparison. We demonstrate that berkelium's complexation is analogous to that of californium. However, from a range of spectroscopic techniques and quantum mechanical calculations, it is clear that spin-orbit coupling contributes significantly to berkelium's multiconfigurational ground state. PMID:27563098

  3. Oxidation-reduction properties of americium, curium, berkelium, californium, einsteinium and fermium, and thermodynamic consequences for the 5f series

    International Nuclear Information System (INIS)

    The amalgamation of 5f elements from Am to Fm has been studied by using 241Am, 244Cm, 249Bk, 249Cf, 252Cf, 253Es, 254Es, 252Fm and 255Fm with two electrochemical methods, radiocoulometry and radiopolarography, perfectly adapted to investigate extremely diluted solutions when the concentration of electroactive species is as low as 10-16M. The theory of radiocoulometry has been developed in the general cases of reversible and irreversible electrode process. It has been used to interpret the experimental data on the kinetic curves of amalgamation, and to estimate the standard rate constant of the electrode process in complexing medium (citric). On the other hand the radiopolarographic method has been applied to study the mechanism of reduction at the dropping mercury electrode of cations M3+ in aqueous medium to the metal M with formation of amalgam. The results are exploited into two directions: 1- Acquisition of some data concerning the oxidation-reduction properties of elements from Am to Fm. Therefore the standard electrode E0 [M(III-0)] potentials for Bk, Cf and Es, and the standard electrode E0 [M(II-0)] potential for Fm are estimated and the relative stability of each oxidation state (from II to VII) of 5f elements is discussed; 2- Acquisition of unknown thermodynamic data on transcalifornium elements. Correlations between 4f and 5f elements are precised and some divergences appear for the second half of 4f and 5f series (i.e. for 65<=Z<=71 and 97<=Z<=103)

  4. SCI 241 WEEKS 1-9 ENTIRE COURSE

    OpenAIRE

    SCI 241 WEEKS 1-9 ENTIRE COURSE

    2016-01-01

    http://www.helperstudy.com/products/sci-241 SCI 241 WEEK 9 CAPSTONE CHECKPOINT REFLECTIONS ON NUTRITION SCI 241 WEEK 9 ASSIGNMENT FINAL PROJECT PERSONALIZED NUTRITION AND EXERCISE PLAN SCI 241 WEEK 7 CHECKPOINT LIFESPAN NUTRITIONAL NEEDS POWERPOINT PRESENTATION SCI 241 WEEK 7 ASSIGNMENT HEALTHY EATING PLAN COMPARISON SCI 241 WEEK 6 CHECKPOINT PERSONAL EXERCISE PLAN SCI 241 WEEK 5 CHECKPOINT MULTIVITIAMIN REVIEW SCI 241 WEEK 5 ASSIGNMENT DEHYDRATION SCI 241 WEEK...

  5. 28 CFR 2.41 - Travel approval.

    Science.gov (United States)

    2010-07-01

    ... 28 Judicial Administration 1 2010-07-01 2010-07-01 false Travel approval. 2.41 Section 2.41..., YOUTH OFFENDERS, AND JUVENILE DELINQUENTS United States Code Prisoners and Parolees § 2.41 Travel approval. (a) The probation officer may approve travel outside the district without approval of...

  6. 24 CFR 241.1010 - Feasibility letter.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Feasibility letter. 241.1010 Section 241.1010 Housing and Urban Development Regulations Relating to Housing and Urban Development...-Eligibility Requirements § 241.1010 Feasibility letter. (a) Request for study. The owner may request...

  7. 43 CFR 24.1 - Introduction.

    Science.gov (United States)

    2010-10-01

    ... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Introduction. 24.1 Section 24.1 Public... POLICY: STATE-FEDERAL RELATIONSHIPS § 24.1 Introduction. (a) In 1970, the Secretary of the Interior... dependent upon habitats on private and public lands managed or subject to administration by many Federal...

  8. 12 CFR 335.241 - Unlisted trading.

    Science.gov (United States)

    2010-01-01

    ... 17 CFR 240.12f-1 through 240.12f-6. ... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Unlisted trading. 335.241 Section 335.241 Banks... SECURITIES OF NONMEMBER INSURED BANKS § 335.241 Unlisted trading. The provisions of the applicable...

  9. 33 CFR 117.241 - Mispillion River.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Mispillion River. 117.241 Section 117.241 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY BRIDGES DRAWBRIDGE OPERATION REGULATIONS Specific Requirements Delaware § 117.241 Mispillion River. The draw of...

  10. 14 CFR 125.241 - Applicability.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Applicability. 125.241 Section 125.241 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR CARRIERS... OR MORE; AND RULES GOVERNING PERSONS ON BOARD SUCH AIRCRAFT Maintenance § 125.241 Applicability....

  11. 42 CFR 413.241 - Pharmacy arrangements.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 2 2010-10-01 2010-10-01 false Pharmacy arrangements. 413.241 Section 413.241... Disease (ESRD) Services and Organ Procurement Costs § 413.241 Pharmacy arrangements. Effective January 1, 2011, an ESRD facility that enters into an arrangement with a pharmacy to furnish renal...

  12. 46 CFR 108.241 - Visual aids.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Visual aids. 108.241 Section 108.241 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) A-MOBILE OFFSHORE DRILLING UNITS DESIGN AND EQUIPMENT Construction and Arrangement Helicopter Facilities § 108.241 Visual aids. (a) Each helicopter deck must—...

  13. 33 CFR 241.3 - References.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false References. 241.3 Section 241.3... CONTROL COST-SHARING REQUIREMENTS UNDER THE ABILITY TO PAY PROVISION § 241.3 References. References cited..., Hyattsville, MD 20781-1102. References cited in paragraphs (d) and (e) may be obtained from the...

  14. 29 CFR 1952.241 - Developmental schedule.

    Science.gov (United States)

    2010-07-01

    ... exceptions to be no broader than those contained in 29 CFR part 1903); (4) Clarification of the appropriate... 29 Labor 9 2010-07-01 2010-07-01 false Developmental schedule. 1952.241 Section 1952.241 Labor... (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Alaska § 1952.241 Developmental...

  15. 46 CFR 169.241 - Machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Machinery. 169.241 Section 169.241 Shipping COAST GUARD... Certification Inspections § 169.241 Machinery. (a) At each inspection for certification and periodic inspection.... Mechanisms are operationally tested and visually examined. (3) Auxiliary machinery. All machinery...

  16. Hanford Single-Shell Tank Leak Causes and Locations - 241-BY and 241-TY Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-11-19

    This document identifies 241-BY Tank Farm (BY Farm) and 241-TY Tank Farm (TY Farm) leak causes and locations for the 100 series leaking tanks (241-BY-103, 241-TY-103, 241-TY-104, 241-TY-105, and 241-TY-106) identified in RPP-RPT-43704, Hanford BY Farm Leak Assessments Report, and in RPP-RPT-42296, Hanford TY Farm Leak Assessments Report. This document satisfies the BY and TY Farm portion of the target (T04) in Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  17. Hanford Single-Shell Tank Leak Causes and Locations - 241-BY and 241-TY Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2014-09-04

    This document identifies 241-BY Tank Farm (BY Farm) and 241-TY Tank Farm (TY Farm) lead causes and locations for the 100 series leaking tanks (241-BY-103, 241-TY-103, 241-TY-104, 241-TY-105 and 241-TY-106) identified in RPP-RPT-43704, Hanford BY Farm Leak Assessments Report, and in RPP-RPT-42296, Hanford TY Farm Leak Assessments Report. This document satisfies the BY and TY Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  18. 241Pu in the biggest Polish rivers

    OpenAIRE

    Dagmara I. Strumińska-Parulska; Skwarzec, Bogdan

    2013-01-01

    In the paper the results of 241Pu activity concentration determination in the biggest Polish rivers are presented. The analysis of more than 100 river water samples showed the Vistula and the Odra as well as three Pomeranian Rivers are important sources of 241Pu in the southern Baltic Sea. There were differences in 241Pu activities depending on season and sampling site and the plutonium contamination came mainly from the global atmospheric fallout as well as the Chernobyl accident, which is c...

  19. Dicty_cDB: AFM241 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available AF (Link to library) AFM241 (Link to dictyBase) - - - - AFM241P (Link to Original site) AFM241F 620 AFM...241Z 717 AFM241P 1317 - - Show AFM241 Library AF (Link to library) Clone ID AFM241 (Link... to dictyBase) Atlas ID - NBRP ID - dictyBase ID - Link to Contig - Original site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/AF/AFM...2-B/AFM241Q.Seq.d/ Representative seq. ID AFM241P (Link to... Original site) Representative DNA sequence >AFM241 (AFM241Q) /CSM/AF/AFM2-B/AFM241Q.Seq.d/ ATTGTCATAATAATAT

  20. 27 CFR 25.241 - Production.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Production. 25.241 Section... THE TREASURY LIQUORS BEER Cereal Beverage § 25.241 Production. Brewers may produce cereal beverage and remove it without payment of tax from the brewery. The method of production shall insure that the...

  1. 40 CFR 86.241-94 - [Reserved

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 18 2010-07-01 2010-07-01 false 86.241-94 Section 86.241-94 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF... Year Gasoline-Fueled New Light-Duty Vehicles, New Light-Duty Trucks and New Medium-Duty...

  2. 7 CFR 1220.241 - Reports.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Reports. 1220.241 Section 1220.241 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (MARKETING AGREEMENTS.... Each producer marketing processed soybeans or soybean products of that producer's own production...

  3. 33 CFR 136.241 - Compensation allowable.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Compensation allowable. 136.241...) MARINE POLLUTION FINANCIAL RESPONSIBILITY AND COMPENSATION OIL SPILL LIABILITY TRUST FUND; CLAIMS PROCEDURES; DESIGNATION OF SOURCE; AND ADVERTISEMENT Procedures for Particular Claims § 136.241...

  4. 40 CFR 436.241 - Specialized definitions.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 29 2010-07-01 2010-07-01 false Specialized definitions. 436.241 Section 436.241 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS MINERAL MINING AND PROCESSING POINT SOURCE CATEGORY Diatomite Subcategory §...

  5. 48 CFR 241.102 - Applicability.

    Science.gov (United States)

    2010-10-01

    ... potable and waste water treatment plants for periods not to exceed 32 years; and (E) 10 U.S.C. 2812 for... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Applicability. 241.102 Section 241.102 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM,...

  6. 24 CFR 241.805 - Insurance premiums.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Insurance premiums. 241.805 Section... Without a HUD-Insured or HUD-Held Mortgage Premiums § 241.805 Insurance premiums. (a) First premium. The... insurance premium equal to one percent of the original face amount of the note. (b) Second premium....

  7. Beneficial uses of /sup 241/Am

    Energy Technology Data Exchange (ETDEWEB)

    Mangeng, C.A.; Thayer, G.R.

    1984-05-01

    This report assesses the uses of /sup 241/Am and the associated costs and supply. The study shows that /sup 241/Am-fueled radioisotope thermoelectric generators in the range of 1 to 5 W electrical provide the most promising use of kilogram amounts of this isotope. For medical uses, where purity is essential, irradiation of /sup 241/Am can produce 97% pure /sup 238/Pu at $21,000/g. Using a pyro-metallurgical process, /sup 241/Am could be recovered from molten salt extraction (MSE) residues at an estimated incremental cost of $83/g adjusted to reflect the disposal costs of waste products. This cost of recovery is less than the $300/g cost for disposal of the /sup 241/Am contained in the MSE residues.

  8. Biosorption of 241Am by R. arrihizus

    International Nuclear Information System (INIS)

    The Biosorption of radionuclide 241Am on R.arrihizus from aqueous solution and the effects of the experimental conditions on the biosorption are investigated by the batch technique. The experimental results show that the R.arrihizus is a very efficient sorbent. The biosorption reaches equilibration in 1 h, the optimum pH range is 1-3. No significant temperature effect on 241Am biosorption is observed in the range of 10-45 degree C. No significant differences of biosorption in the presence and absence of Au3+ or Ag+ are observed. The relationship between concentrations of 241Am in aqueous solutions and adsorption capacities of 241Am can be described by the Freundlich adsorption equation

  9. Biosorption of 241Am by microorganism

    International Nuclear Information System (INIS)

    The biosorption of 241Am on A. niger, R. arrihizus and Candida albicans from aqueous solution, and the effects of the experimental conditions on the biosorption are investigated by the batch technique. The experimental results show that all the microorganism above are very efficient as the sorbent. The biosorption equilibrium time is 2 h and the optimum pH ranges 1-3. No significant differences on 241Am biosorption are observed at the temperature of 15-45 degree C, or in the presence and absence of Au3+ or Ag+. The relationship between concentrations of 241Am in aqueous solutions and adsorption capacities of 241Am can be described by the Freundlich adsorption equation on A. niger and R. arrihizus, while as it can be done by the Langmuir adsorption equation on Candida albicans

  10. Photodisintegration Cross Section of 241Am

    Science.gov (United States)

    Tonchev, A. P.; Hammond, S.; Howell, C. R.; Huibregtse, C.; Hutcheson, A.; Karwowski, H. J.; Kelley, J. H.; Kwan, E.; Rusev, G.; Tornow, W.; Vieira, D. J.; Wilhelmy, J. B.

    2009-03-01

    The photodisintegration cross section of radioactive 241Am has been obtained for the first time using monoenergetic γ-ray beams from the HIγS facility. The induced activity of 240Am produced via the 241Am(γ,n) reaction in the γ-ray energy range from 9.5 to 16 MeV was measured by the activation technique utilizing high resolution HPGe detectors. The 241Am(γ,n) cross section was determined both by measuring the absolute γ-ray flux and by comparison to the 197Au(γ,n) and 58Ni(γ,n) cross section standards. The experimental data for the 241Am(γ,n) reaction in the giant dipole resonance energy region is compared with statistical nuclear-model calculations.

  11. 40 CFR 98.241 - Reporting threshold.

    Science.gov (United States)

    2010-07-01

    ...) MANDATORY GREENHOUSE GAS REPORTING Petrochemical Production § 98.241 Reporting threshold. You must report GHG emissions under this subpart if your facility contains a petrochemical process as specified...

  12. Tank characterization report: Tank 241-C-109

    International Nuclear Information System (INIS)

    Single-shell tank 241-C-109 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in September 1992. Analyses of materials obtained from tank 241-C-109 were conducted to support the resolution of the ferrocyanide unreviewed safety question (USQ) and to support Hanford Federal Facility Agreement and consent Order (Tri- Party Agreement) Milestone M-10-00. This report describes this analysis

  13. Biosorption of 241Am by Candida sp

    International Nuclear Information System (INIS)

    The biosorption of radionuclide 241Am from solutions by Candida sp., and the influences of experimental conditions on the adsorption were studied. The results showed that the adsorption equilibrium was achieved within 4h and the optimum pH=2. No significant differences on 241Am biosorption were observed at 10-45 degree C, or challenged with Au3+ or Ag+, even 1500 times or 4500 times over 241Am, respectively. The adsorption rate could reach 97.8% by dry Candida sp. of 0.82 g/L in 241Am solutions (pH=2) of 5.6-111 MBq/L (44.04-873.0 μg/L) (C0), with maximum adsorption capacity (W) of 63.5 MBq/g (501.8 μg/g), implying that the removal of 241Am by Candida sp. from solutions was feasible. The relationship between activities (C0) and adsorption capacities (W) of 241Am indicated that the biosorption process could be described by Langmuir adsorption isotherm

  14. Waste Feed Delivery Strategy for Tanks 241-AN-102 and 241-AN-107

    International Nuclear Information System (INIS)

    This engineering study establishes the detailed retrieval strategy, equipment requirements, and key parameters for preparing detailed process flowsheets; evaluates the technical and programmatic risks associated with processing, certifying, transferring, and delivering waste from Tanks 241-AN-102 and 241-AN-107 to BNFL; and provides a list of necessary follow-on actions so that program direction from ORP can be successfully implemented

  15. Waste Feed Delivery Strategy for Tanks 241-AN-102 and 241-AN-107

    Energy Technology Data Exchange (ETDEWEB)

    BLACKER, S.M.

    2000-04-13

    This engineering study establishes the detailed retrieval strategy, equipment requirements, and key parameters for preparing detailed process flowsheets; evaluates the technical and programmatic risks associated with processing, certifying, transferring, and delivering waste from Tanks 241-AN-102 and 241-AN-107 to BNFL; and provides a list of necessary follow-on actions so that program direction from ORP can be successfully implemented.

  16. Acceptance test procedure, 241-SY-101/241-C-106 shot loading system

    International Nuclear Information System (INIS)

    This Acceptance Test Procedure is for the 241-SY-101/241-C-106 Shot Loading System. The procedure will test the components of the Shot Loading System and its capability of adequately loading shot into the annular space of the Container. The loaded shot will provide shielding as required for transporting and storage of a contaminated pump after removal from the tank. This test serves as verification that the SLS is acceptable for use in the pump removal operations for Tanks 241-SY-101, 241-C-106 and 241-AY-102. The pump removal operation for these three tanks will be performed by two different organizations with different equipment, but the Shot Loading System will be compatible between the two operations

  17. CESIUM REMOVAL FROM TANKS 241-AN-103 & 241-SX-105 & 241-AZ-101 & 241AZ-102 COMPOSITE FOR TESTING IN BENCH SCALE STEAM REFORMER

    Energy Technology Data Exchange (ETDEWEB)

    DUNCAN JB; HUBER HJ

    2011-04-21

    This report documents the preparation of three actual Hanford tank waste samples for shipment to the Savannah River National Laboratory (SRNL). Two of the samples were dissolved saltcakes from tank 241-AN-103 (hereafter AN-103) and tank 241-SX-105 (hereafter SX-105); one sample was a supernate composite from tanks 241-AZ-101 and 241-AZ-102 (hereafter AZ-101/102). The preparation of the samples was executed following the test plans LAB-PLAN-10-00006, Test Plan for the Preparation of Samples from Hanford Tanks 241-SX-105, 241-AN-103, 241-AN-107, and LAB-PLN-l0-00014, Test Plan for the Preparation of a Composite Sample from Hanford Tanks 241-AZ-101 and 241-AZ-102 for Steam Reformer Testing at the Savannah River National Laboratory. All procedural steps were recorded in laboratory notebook HNF-N-274 3. Sample breakdown diagrams for AN-103 and SX-105 are presented in Appendix A. The tank samples were prepared in support of a series of treatability studies of the Fluidized Bed Steam Reforming (FBSR) process using a Bench-Scale Reformer (BSR) at SRNL. Tests with simulants have shown that the FBSR mineralized waste form is comparable to low-activity waste glass with respect to environmental durability (WSRC-STI-2008-00268, Mineralization of Radioactive Wastes by Fluidized Bed Steam Reforming (FBSR): Comparisons to Vitreous Waste Forms and Pertinent Durability Testing). However, a rigorous assessment requires long-term performance data from FBSR product formed from actual Hanford tank waste. Washington River Protection Solutions, LLC (WRPS) has initiated a Waste Form Qualification Program (WP-5.2.1-2010-001, Fluidized Bed Steam Reformer Low-level Waste Form Qualification) to gather the data required to demonstrate that an adequate FBSR mineralized waste form can be produced. The documentation of the selection process of the three tank samples has been separately reported in RPP-48824, Sample Selection Process for Bench-Scale Steam Reforming Treatability Studies Using

  18. Cesium Removal From Tanks 241-AN-103 and 241-SX-105 and 241-AZ-101 and 241-AZ-102 Composite For Testing In Bench Scale Steam Reformer

    International Nuclear Information System (INIS)

    This report documents the preparation of three actual Hanford tank waste samples for shipment to the Savannah River National Laboratory (SRNL). Two of the samples were dissolved saltcakes from tank 241-AN-103 (hereafter AN-103) and tank 241-SX-105 (hereafter SX-105); one sample was a supernate composite from tanks 241-AZ-101 and 241-AZ-102 (hereafter AZ-101/102). The preparation of the samples was executed following the test plans LAB-PLAN-10-00006, Test Plan for the Preparation of Samples from Hanford Tanks 241-SX-105, 241-AN-103, 241-AN-107, and LAB-PLN-l0-00014, Test Plan for the Preparation of a Composite Sample from Hanford Tanks 241-AZ-101 and 241-AZ-102 for Steam Reformer Testing at the Savannah River National Laboratory. All procedural steps were recorded in laboratory notebook HNF-N-274 3. Sample breakdown diagrams for AN-103 and SX-105 are presented in Appendix A. The tank samples were prepared in support of a series of treatability studies of the Fluidized Bed Steam Reforming (FBSR) process using a Bench-Scale Reformer (BSR) at SRNL. Tests with simulants have shown that the FBSR mineralized waste form is comparable to low-activity waste glass with respect to environmental durability (WSRC-STI-2008-00268, Mineralization of Radioactive Wastes by Fluidized Bed Steam Reforming (FBSR): Comparisons to Vitreous Waste Forms and Pertinent Durability Testing). However, a rigorous assessment requires long-term performance data from FBSR product formed from actual Hanford tank waste. Washington River Protection Solutions, LLC (WRPS) has initiated a Waste Form Qualification Program (WP-5.2.1-2010-001, Fluidized Bed Steam Reformer Low-level Waste Form Qualification) to gather the data required to demonstrate that an adequate FBSR mineralized waste form can be produced. The documentation of the selection process of the three tank samples has been separately reported in RPP-48824, Sample Selection Process for Bench-Scale Steam Reforming Treatability Studies Using

  19. Tank 241-C-105 tank characterization plan

    International Nuclear Information System (INIS)

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from tank 241-C-105

  20. 24 CFR 241.885 - Insurance benefits.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Insurance benefits. 241.885 Section... DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES... Without a HUD-Insured or HUD-Held Mortgage Rights and Duties of Lender Under the Contract of...

  1. Tank 241-TY-104 Tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-02-15

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-C Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-TY-104.

  2. Tank 241-U-105 tank characterization plan

    International Nuclear Information System (INIS)

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-U-105

  3. Tank 241-TY-106 Tank Characterization Plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1995-02-22

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-TY-106.

  4. Tank 241-BX-103 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Bell, K.E. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-04-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BX-103.

  5. Tank 241-C-203: Tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1995-03-06

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. Scope of this plan is to provide guidance for sampling and analysis of samples for tank 241-C-203.

  6. Tank 241-U-201 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1995-02-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 22-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-201.

  7. Tank 241-SX-115 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, L.M.

    1995-04-24

    This document is a plan which serves as the contractual agreement between the Characterization Project, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-SX-115.

  8. Tank 241-C-202: Tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1995-03-06

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. Scope of this plan is to provide guidance for sampling and analysis of samples for tank 241-C-202.

  9. Tank 241-U-202 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1995-02-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-202.

  10. Tank 241-C-101 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1994-12-06

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from tank 241-C-101.

  11. Tank 241-TY-101 Tank Characterization Plan

    Energy Technology Data Exchange (ETDEWEB)

    Homi, C.S.

    1995-03-20

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-TY-101.

  12. 48 CFR 52.241 - Utility Services Provisions and Clauses.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Utility Services Provisions and Clauses. 52.241 Section 52.241 Federal Acquisition Regulations System FEDERAL ACQUISITION... Clauses 52.241 Utility Services Provisions and Clauses....

  13. 24 CFR 241.1215 - Calculation of insurance benefits.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Calculation of insurance benefits. 241.1215 Section 241.1215 Housing and Urban Development Regulations Relating to Housing and Urban... Loans-Contract Rights and Obligations § 241.1215 Calculation of insurance benefits. All of...

  14. 24 CFR 241.1050 - Method of loan payment.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Method of loan payment. 241.1050 Section 241.1050 Housing and Urban Development Regulations Relating to Housing and Urban Development...-Eligibility Requirements § 241.1050 Method of loan payment. The loan shall provide for monthly payments on...

  15. 42 CFR 456.241 - Purpose and general description.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Purpose and general description. 456.241 Section 456.241 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN... Ur Plan: Medical Care Evaluation Studies § 456.241 Purpose and general description. (a) The...

  16. The concentrations of 241Pu in the southern Baltic Sea

    Directory of Open Access Journals (Sweden)

    Strumińska-Parulska D. I.

    2013-04-01

    Full Text Available The aim of the work was 241Pu activities determination in different components (water, plankton and fish of the southern Baltic Sea ecosystem. The determination of 241Pu in the samples was done indirectly by activity measuring the increment in 241Am from the decay of β-emitting 241Pu in samples collected 10-15 years after the Chernobyl accident. Enhanced levels of 241Pu were observed in all analyzed Baltic samples. The plutonium is also non-uniformly distributed between the organs and tissues of the analyzed fish; especially pelagic herring and cod as well as benthic flounder. The annual individual effective doses calculated on the basis of 241Pu concentrations in fish indicated that the impact of the consumption of 241Pu with Baltic fish on the annual effective dose for a statistical inhabitant of Poland was very small.

  17. Evaluation of neutron data for americium-241

    Energy Technology Data Exchange (ETDEWEB)

    Maslov, V.M.; Sukhovitskij, E.Sh.; Porodzinskij, Yu.V.; Klepatskij, A.B.; Morogovskij, G.B. [Radiation Physics and Chemistry Problems Inst., Minsk-Sosny (Belarus)

    1997-03-01

    The evaluation of neutron data for {sup 241}Am is made in the energy region from 10{sup -5} eV up to 20 MeV. The results of the evaluation are compiled in the ENDF/B-VI format. This work is performed under the Project Agreement CIS-03-95 with the International Science and Technology Center (Moscow). The Financing Party for the Project is Japan. The evaluation was requested by Y. Kikuchi (JAERI). (author). 60 refs.

  18. Tank 241-T-111 characterization report

    International Nuclear Information System (INIS)

    In late October and early November of 1991, single-shell tank (SST) 241-T-111 (on the Organic Watch List) was sampled and analyses were conducted on the materials obtained to complete Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00 to sample and analyze two cores from each tank. Other objectives that these measurements and inventory estimates support are as follows: Obtain estimates of both the concentration and total quantity of key analytes relating to safety issues, such as organics and radionuclides; Provided input to risk assessment-based disposal decisions for the waste; and Implement physical property measurements, such as rheology, bulk density, and particle size. These measurements are necessary for the design and fabrication of retrieval, pretreatment, and vitrification systems. The purpose of the tank characterization report is to describe and characterize the waste in SST 241-T-111, based on information from various sources. This report summarizes the available information regarding the waste in tank 241-T-111, and arranges this information in a format useful to support management and technical decisions concerning this waste tank

  19. Gamma-sources on the basis of metallic americium-241

    International Nuclear Information System (INIS)

    A batch of gamma-radiation sources has been manufactured from metallic americium-241 of isotopic purity, its activity varying from 0.08 to 0.93 GBq. The cores of the sources are high-purity americium metal condensate on a tantalum or stainless steel substrate prepared by thermal decomposition of 241Pu-241Am alloy in a high vacuum. 7 refs., 1 tab

  20. Hanford Single-Shell Tank Leak Causes and Locations - 241-SX Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L. [Washington River Protection Solutions (United States); Harlow, Donald G. [Washington River Protection Solutions (United States)

    2014-01-08

    This document identifies 241-SX Tank Farm (SX Farm) leak causes and locations for the 100 series leaking tanks (241-SX-107, 241-SX-108, 241-SX-109, 241-SX-111, 241-SX-112, 241-SX-113, 241-SX-114, and 241-SX-115) identified in RPP-ENV-39658, Rev. 0, Hanford SX-Farm Leak Assessments Report. This document satisfies the SX Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  1. Effect of americium-241 on luminous bacteria. Role of peroxides

    Energy Technology Data Exchange (ETDEWEB)

    Alexandrova, M., E-mail: maka-alexandrova@rambler.r [Siberian Federal University, Svobodny 79, 660041 Krasnoyarsk (Russian Federation); Rozhko, T. [Siberian Federal University, Svobodny 79, 660041 Krasnoyarsk (Russian Federation); Vydryakova, G. [Institute of Biophysics SB RAS, Akademgorodok 50, 660036 Krasnoyarsk (Russian Federation); Kudryasheva, N. [Siberian Federal University, Svobodny 79, 660041 Krasnoyarsk (Russian Federation); Institute of Biophysics SB RAS, Akademgorodok 50, 660036 Krasnoyarsk (Russian Federation)

    2011-04-15

    The effect of americium-241 ({sup 241}Am), an alpha-emitting radionuclide of high specific activity, on luminous bacteria Photobacterium phosphoreum was studied. Traces of {sup 241}Am in nutrient media (0.16-6.67 kBq/L) suppressed the growth of bacteria, but enhanced luminescence intensity and quantum yield at room temperature. Lower temperature (4 {sup o}C) increased the time of bacterial luminescence and revealed a stage of bioluminescence inhibition after 150 h of bioluminescence registration start. The role of conditions of exposure the bacterial cells to the {sup 241}Am is discussed. The effect of {sup 241}Am on luminous bacteria was attributed to peroxide compounds generated in water solutions as secondary products of radioactive decay. Increase of peroxide concentration in {sup 241}Am solutions was demonstrated; and the similarity of {sup 241}Am and hydrogen peroxide effects on bacterial luminescence was revealed. The study provides a scientific basis for elaboration of bioluminescence-based assay to monitor radiotoxicity of alpha-emitting radionuclides in aquatic solutions. - Highlights: {yields} Am-241 in water solutions (A = 0.16-6.7 kBq/L) suppresses bacterial growth.{yields} Am-241 (A = 0.16-6.7 kBq/L) stimulate bacterial luminescence. {yields} Peroxides, secondary radiolysis products, cause increase of bacterial luminescence.

  2. Hazard evaluation for transfer of waste from tank 241-SY-101 to tank 241-SY-102

    Energy Technology Data Exchange (ETDEWEB)

    SHULTZ, M.V.

    1999-04-05

    Tank 241-SY-101 waste level growth is an emergent, high priority issue. The purpose of this document is to record the hazards evaluation process and document potential hazardous conditions that could lead to the release of radiological and toxicological material from the proposed transfer of a limited quantity (approximately 100,000 gallons) of waste from Tank 241-SY-101 to Tank 241-SY-102. The results of the hazards evaluation were compared to the current Tank Waste Remediation System (TWRS) Basis for Interim Operation (HNF-SD-WM-BIO-001, 1998, Revision 1) to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient or may not exist. Comparison to LA-UR-92-3196, A Safety Assessment for Proposed Pump Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-SY-101, was also made in the case of transfer pump removal activities. Revision 1 of this document deletes hazardous conditions no longer applicable to the current waste transfer design and incorporates hazardous conditions related to the use of an above ground pump pit and overground transfer line. This document is not part of the AB and is not a vehicle for requesting authorization of the activity; it is only intended to provide information about the hazardous conditions associated with this activity. The AB Control Decision process will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis.

  3. Concordant plutonium-241-americium-241 dating of environmental samples: results from forest fire ash

    Energy Technology Data Exchange (ETDEWEB)

    Goldstein, Steven J [Los Alamos National Laboratory; Oldham, Warren J [Los Alamos National Laboratory; Murrell, Michael T [Los Alamos National Laboratory; Katzman, Danny [Los Alamos National Laboratory

    2010-12-07

    We have measured the Pu, {sup 237}Np, {sup 241}Am, and {sup 151}Sm isotopic systematics for a set of forest fire ash samples from various locations in the western U.S. including Montana, Wyoming, Idaho, and New Mexico. The goal of this study is to develop a concordant {sup 241}Pu (t{sub 1/2} = 14.4 y)-{sup 241}Am dating method for environmental collections. Environmental samples often contain mixtures of components including global fallout. There are a number of approaches for subtracting the global fallout component for such samples. One approach is to use {sup 242}/{sup 239}Pu as a normalizing isotope ratio in a three-isotope plot, where this ratio for the nonglobal fallout component can be estimated or assumed to be small. This study investigates a new, complementary method of normalization using the long-lived fission product, {sup 151}Sm (t{sub 1/2} = 90 y). We find that forest fire ash concentrates actinides and fission products with {approx}1E10 atoms {sup 239}Pu/g and {approx}1E8 atoms {sup 151}Sm/g, allowing us to measure these nuclides by mass spectrometric (MIC-TIMS) and radiometric (liquid scintillation counting) methods. The forest fire ash samples are characterized by a western U.S. regional isotopic signature representing varying mixtures of global fallout with a local component from atmospheric testing of nuclear weapons at the Nevada Test Site (NTS). Our results also show that {sup 151}Sm is well correlated with the Pu nuclides in the forest fire ash, suggesting that these nuclides have similar geochemical behavior in the environment. Results of this correlation indicate that the {sup 151}Sm/{sup 239}Pu atom ratio for global fallout is {approx}0.164, in agreement with an independent estimate of 0.165 based on {sup 137}Cs fission yields for atmospheric weapons tests at the NTS. {sup 241}Pu-{sup 241}Am dating of the non-global fallout component in the forest fire ash samples yield ages in the late 1950's-early 1960's, consistent with a peak

  4. Concordant 241Pu-241Am Dating of Environmental Samples: Results from Forest Fire Ash

    Science.gov (United States)

    Goldstein, S. J.; Oldham, W. J.; Murrell, M. T.; Katzman, D.

    2010-12-01

    We have measured the Pu, 237Np, 241Am, and 151Sm isotopic systematics for a set of forest fire ash samples from various locations in the western U.S. including Montana, Wyoming, Idaho, and New Mexico. The goal of this study is to develop a concordant 241Pu (t1/2 = 14.4 y)-241Am dating method for environmental collections. Environmental samples often contain mixtures of components including global fallout. There are a number of approaches for subtracting the global fallout component for such samples. One approach is to use 242Pu/239Pu as a normalizing isotope ratio in a three-isotope plot, where this ratio for the non-global fallout component can be estimated or assumed to be small. This study investigates a new, complementary method of normalization using the long-lived fission product, 151Sm (t1/2 = 90 y). We find that forest fire ash concentrates actinides and fission products with ~1E10 atoms 239Pu/g and ~1E8 atoms 151Sm/g, allowing us to measure these nuclides by mass spectrometric (MIC-TIMS) and radiometric (liquid scintillation counting) methods. The forest fire ash samples are characterized by a western U.S. regional isotopic signature representing varying mixtures of global fallout with a local component from atmospheric testing of nuclear weapons at the Nevada Test Site (NTS). Our results also show that 151Sm is well correlated with the Pu nuclides in the forest fire ash, suggesting that these nuclides have similar geochemical behavior in the environment. Results of this correlation indicate that the 151Sm/239Pu atom ratio for global fallout is ~0.164, in agreement with an independent estimate of 0.165 based on 137Cs fission yields for atmospheric weapons tests at the NTS. 241Pu-241Am dating of the non-global fallout component in the forest fire ash samples yield ages in the late 1950’s-early 1960’s, consistent with a peak in NTS weapons testing at that time. The age results for this component are in agreement using both 242Pu and 151Sm normalizations

  5. Disturbance from Am-241 Photons of the Cellular Dose by Am-241 Alpha Emissions: Am-241 as an alternative source of alpha particles to radon daughters

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ki-Man; Kim, Eun-Hee [Seoul National University, Seoul (Korea, Republic of)

    2015-05-15

    The Radiation Bioengineering Laboratory (RadBio Lab) at Seoul National University (SNU) has built an Am-241 alpha particle irradiator for study of cellular responses to radiation from radon daughters. The radon daughters of concern that cause internal exposure from inhalation of radon-contaminated air are Po-218, Po-214 and Po-210. In their alpha decay schemes, the yields of photon emissions are negligible. Unfortunately, Am-241, the source of alpha irradiator in RadBio Lab, emits photons at every alpha decay while transforming to Np-237 of long half-life. Employing Am-241 as the source simulating radon daughters, therefore, requires that photon emissions from Am-241 be specified in term of dose contribution. In this study, Monte Carlo calculations have been made to characterize dose contributions of Am-241 photon emissions. This study confirms that disturbance from Am-241 photon emissions of the cellular dose by Am-241 alpha emissions is negligible. Dose contamination fraction from photon emissions was 8.02 .. 10{sup -6} at 25 mm SSD at maximum. Also, note that LET in tissue-equivalent medium varies within about 20% for alpha particles at energies over 5 MeV.

  6. Cone Penetrometer Shear Strength Measurements of Sludge Waste in Tanks 241-AN-101 and 241-AN-106

    Energy Technology Data Exchange (ETDEWEB)

    Follett, Jordan R.

    2014-03-06

    This document presents the resulting shear strength profiles for sludge waste in Tanks 241-AN-101 and 241-AN-106, as determined with a full-flow cone penetrometer. Full-flow penetrometer measurements indicate shear strength profiles that increase roughly uniformly with depth. For Tank 241-AN-101, the undrained shear strength was calculated to range from 500 Pa near the sludge surface to roughly 3,300 Pa at 15 inches above the tank bottom. For 241-AN-106, the undrained shear strength was calculated to range from 500 Pa near the sludge surface to roughly 5,000 Pa at 15 inches above the tank bottom.

  7. 48 CFR 552.241-71 - Disputes (Utility Contracts).

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Disputes (Utility....241-71 Disputes (Utility Contracts). As prescribed in 541.501, insert clause 552.241-71, Disputes (Utility Contracts), in solicitations and contracts for utility services subject to the jurisdiction...

  8. 24 CFR 241.265 - Insurance of property against flood.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Insurance of property against flood. 241.265 Section 241.265 Housing and Urban Development Regulations Relating to Housing and Urban... Insurance of property against flood. The mortgaged property shall be insured against flood as stipulated...

  9. 24 CFR 241.275 - No vested right in fund.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false No vested right in fund. 241.275... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES SUPPLEMENTARY FINANCING FOR INSURED PROJECT MORTGAGES Contract Rights and Obligations § 241.275 No vested...

  10. 24 CFR 241.900 - No vested right in fund.

    Science.gov (United States)

    2010-04-01

    ... Without a HUD-Insured or HUD-Held Mortgage Rights in Housing Fund § 241.900 No vested right in fund... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false No vested right in fund. 241.900... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER...

  11. 24 CFR 241.1230 - No vested right in fund.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false No vested right in fund. 241.1230... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES... Rights and Obligations § 241.1230 No vested right in fund. Neither the lender nor the borrower shall...

  12. 49 CFR 192.241 - Inspection and test of welds.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Inspection and test of welds. 192.241 Section 192....241 Inspection and test of welds. (a) Visual inspection of welding must be conducted by an individual... nondestructively tested or visually inspected is determined according to the standards in Section 9 of API...

  13. 241-AZ Farm Annulus Extent of Condition Baseline Inspection

    Energy Technology Data Exchange (ETDEWEB)

    Engeman, Jason K.; Girardot, Crystal L.; Vazquez, Brandon J.

    2013-05-15

    This report provides the results of the comprehensive annulus visual inspection for tanks 241- AZ-101 and 241-AZ-102 performed in fiscal year 2013. The inspection established a baseline covering about 95 percent of the annulus floor for comparison with future inspections. Any changes in the condition are also included in this document.

  14. 24 CFR 241.1200 - Cross-references.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Cross-references. 241.1200 Section... Rights and Obligations § 241.1200 Cross-references. (a) Projects with a HUD-insured or HUD-held mortgage....254Insurance endorsement. (2) For the purposes of subpart F of this part, all references in part 207 of...

  15. 38 CFR 17.241 - Sharing medical information services.

    Science.gov (United States)

    2010-07-01

    ... information services. 17.241 Section 17.241 Pensions, Bonuses, and Veterans' Relief DEPARTMENT OF VETERANS... information services. (a) Agreements for exchange of information. Subject to such terms and conditions as the... techniques will be freely exchanged and the medical information services of all parties to the agreement...

  16. 24 CFR 241.1090 - Accumulation of next premium.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Accumulation of next premium. 241... Loans-Eligibility Requirements § 241.1090 Accumulation of next premium. The security instrument shall... insurance premium payable by the lender to the Commissioner. These payments shall continue only as long...

  17. 24 CFR 241.1030 - Mortgage insurance premiums.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Mortgage insurance premiums. 241... Loans-Eligibility Requirements § 241.1030 Mortgage insurance premiums. The lender, upon endorsement of the note, shall pay the Commissioner a first mortgage insurance premium equal to 0.5 percent of...

  18. 24 CFR 241.550 - Accumulation of next premium.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Accumulation of next premium. 241... Security Instruments § 241.550 Accumulation of next premium. The security instrument shall provide for... premium payable by the lender to the Commissioner....

  19. Type B Investigation Report for 241-SY-101 Pump Start and 241-C-106 Pit Cleanout

    Energy Technology Data Exchange (ETDEWEB)

    Ewalt, J.R.

    1993-09-01

    In accordance with the direction of the Department of Energy (DOE) Manager, Richland Operations Office, a Type ``B`` investigation in accordance with the DOE Order 5484.1, Environmental Protection, Safety and Health Protection Information Reporting Requirements, has been conducted. The scope of the investigation included two events: The ``Inadvertent Mixer Pump Operation at 241-SY-101`` (RL-WHC-TANK FARM-1993-069); ``Inadequate Work Control Results in Personnel Skin Contamination at 241-C-106, Pit B`` (RL-WHC-TANK FARM-1993-071) events. Additionally, at the request of the President of the WHC, a broader investigation into Waste Tank Farm ``safety practices`` and ``Conduct of Operations`` was also conducted. The review was focused on (1) WHC organizations performing operations, maintenance, and radiological safety tasks; and (2) KEH organizations performing major maintenance tasks.

  20. Neutron transmission and capture of 241Am

    International Nuclear Information System (INIS)

    A set of neutron transmission and capture experiments based on the Time Of Flight (TOF) technique, were performed in order to determine the 241Am capture cross section in the energy range from 0.01 eV to 1 keV. The GELINA facility of the Institute for Reference Materials and Measurements (IRMM) served as the neutron source. A pair of C6D6 liquid scintillators was used to register the prompt gamma rays emerging from the americium sample, while a Li-glass detector was used in the transmission setup. Results from the capture and transmission data acquired are consistent with each other, but appear to be inconsistent with the evaluated data files. Resonance parameters have been derived for the data up to the energy of 100 eV. (authors)

  1. Vapor characterization of Tank 241-C-103

    International Nuclear Information System (INIS)

    The Westinghouse Hanford Company Tank Vapor Issue Resolution Program has developed, in cooperation with Northwest Instrument Systems, Inc., Oak Ridge National Laboratory, Oregon Graduate Institute of Science and Technology, Pacific Northwest Laboratory, and Sandia National Laboratory, the equipment and expertise to characterize gases and vapors in the high-level radioactive waste storage tanks at the Hanford Site in south central Washington State. This capability has been demonstrated by the characterization of the tank 241-C-103 headspace. This tank headspace is the first, and for many reasons is expected to be the most problematic, that will be characterized (Osborne 1992). Results from the most recent and comprehensive sampling event, sample job 7B, are presented for the purpose of providing scientific bases for resolution of vapor issues associated with tank 241-C-103. This report is based on the work of Clauss et al. 1994, Jenkins et al. 1994, Ligotke et al. 1994, Mahon et al. 1994, and Rasmussen and Einfeld 1994. No attempt has been made in this report to evaluate the implications of the data presented, such as the potential impact of headspace gases and vapors to tank farm workers health. That and other issues will be addressed elsewhere. Key to the resolution of worker health issues is the quantitation of compounds of toxicological concern. The Toxicology Review Panel, a panel of Pacific Northwest Laboratory experts in various areas, of toxicology, has chosen 19 previously identified compounds as being of potential toxicological concern. During sample job 7B, the sampling and analytical methodology was validated for this preliminary list of compounds of toxicological concern. Validation was performed according to guidance provided by the Tank Vapor Conference Committee, a group of analytical chemists from academic institutions and national laboratories assembled and commissioned by the Tank Vapor Issue Resolution Program

  2. Hazard evaluation for transfer of waste from tank 241-SY-101 to tank 241-SY-102

    International Nuclear Information System (INIS)

    Tank 241-SY-101 (SY-101) waste level growth is an emergent, high priority issue. The purpose of this document is to record the hazards evaluation process and document potential hazardous conditions that could lead to the release of radiological and toxicological material from the proposed transfer of a limited quantity (approximately 100,000 gallons) of waste from SY-101 to 241-SY-102 (SY-102). The results of the hazards evaluation will be compared to the current Tank Waste Remediation System (TWRS) Basis for Interim Operation (HNF-SD-WM-BIO-001, 1998, Revision 1) to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient or may not exist. Comparison to LA-UR-92-3196, A Safety Assessment for Proposed Pump Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-SY-101, was also made in the case of transfer pump removal activities. This document is not intended to authorize the activity or determine the adequacy of controls; it is only intended to provide information about the hazardous conditions associated with this activity. The Unreviewed Safety Question (USQ) process will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis

  3. Radiological and toxicological analyses of tank 241-AY-102 and tank 241-C-106 ventilation systems

    International Nuclear Information System (INIS)

    The high heat content solids contained in Tank 241-C-106 are to be removed and transferred to Tank 241-AY-102 by sluicing operations, to be authorized under project W320. While sluicing operations are underway, the state of these tanks will be transformed from unagitated to agitated. This means that the partition fraction which describes the aerosol content of the head space will increase from IE-10 to IE-8 (see WHC-SD-WM-CN062, Rev. 2 for discussion of partition fractions). The head spare will become much more loaded with suspended material. Furthermore, the nature of this suspended material can change significantly: sluicing could bring up radioactive solids which normally would lay under many meters of liquid supernate. It is assumed that the headspace and filter aerosols in Tank 241-AY-102 are a 90/10 liquid/solid split. It is further assumed that the sluicing line, the headspace in Tank 241-C-106, and the filters on Tank 241-C-106 contain aerosols which are a 67/33 liquid/solid split. The bases of these assumptions are discussed in Section 3.0. These waste compositions (referred to as mitigated compositions) were used in Attachments 1 through 4 to calculate survey meter exposure rates per liter of inventory in the various system components. Three accident scenarios are evaluated: a high temperature event which melts or burns the HEPA filters and causes releases from other system components; an overpressure event which crushes and blows out the HEPA filters and causes releases from other system components; and an unfiltered release of tank headspace air. The initiating event for the high temperature release is a fire caused by a heater malfunction inside the exhaust dust or a fire outside the duct. The initiating event for the overpressure event could be a steam bump which over pressurizes the tank and leads to a blowout of the HEPA filters in the ventilation system. The catastrophic destruction of the HEPA filters would release a fraction of the accumulated

  4. Biosorption of 241Am by immobilized Saccharomyces cerevisiae

    International Nuclear Information System (INIS)

    Americium-241 is one of the most serious radioactive contaminating nuclides due to its high toxicity and long half-life. The encouraging biosorption of 241Am from aqueous solutions by free Saccharomyces cerevisiae (S. cerevisiae) has been observed in our previous experiments. 241Am biosorption by immobilized S. cerevisiae and the effect of the various experimental conditions on the adsorption were investigated. The results indicated that the 241Am biosorption by immobilized S. cerevisiae is still very efficient, and immobilized S. cerevisiae can be used repeatedly or continuously. The biosorption equilibrium was achieved within 2 hours, and more than 92% of 241Am was removed by immobilized S. cerevisiae in the pH 1-4 range. No significant differences in 241Am biosorption were observed at 15-45 deg C. The immobilized S. cerevisiae, even after used repeatedly for 6 times, still could adsorb more than 90% of 241Am in solutions of 1.08 MBq/l (8.5 μg/l). At this moment, the total adsorption capacity for 241Am was more than 63.3 KBq/g globe (0.5 μg/g), but has not reached saturation yet. The 241Am left in solutions with initial concentration of 1.08 MBq/l (8.5 μg/l) was noted as low as ∼10 Bq/l (∼8.0 x 10-5 μg/l) after adsorption by the immobilized S. cerevisiae for 3 times. (author)

  5. 241-Z-361 Sludge Characterization Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    BANNING, D.L.

    1999-07-29

    This sampling and analysis plan (SAP) identifies the type, quantity, and quality of data needed to support characterization of the sludge that remains in Tank 241-2-361. The procedures described in this SAP are based on the results of the 241-2-361 Sludge Characterization Data Quality Objectives (DQO) (BWHC 1999) process for the tank. The primary objectives of this project are to evaluate the contents of Tank 241-2-361 in order to resolve safety and safeguards issues and to assess alternatives for sludge removal and disposal.

  6. 241-Z-361 Sludge Characterization Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    BANNING, D.L.

    1999-08-05

    This sampling and analysis plan (SAP) identifies the type, quantity, and quality of data needed to support characterization of the sludge that remains in Tank 241-2-361. The procedures described in this SAP are based on the results of the 241-2-361 Sludge Characterization Data Quality Objectives (DQO) (BWHC 1999) process for the tank. The primary objectives of this project are to evaluate the contents of Tank 241-2-361 in order to resolve safety and safeguards issues and to assess alternatives for sludge removal and disposal.

  7. CESIUM REMOVAL FROM TANKS 241-AN-103 & 241-SX-105 & 241-AZ-101/102 COMPOSITE FOR TESTING IN BENCH SCALE STEAM REFORMER

    Energy Technology Data Exchange (ETDEWEB)

    DUNCAN JB; HUBER HJ

    2011-06-08

    This report documents the preparation of three actual Hanford tank waste samples for shipment to the Savannah River National Laboratory (SRNL). Two of the samples were dissolved saltcakes from tank 241-AN-103 (hereafter AN-103) and tank 241-SX-105 (hereafter SX-105); one sample was a supernate composite from tanks 241-AZ-101 and 241-AZ-102 (hereafter AZ-101/102). The preparation of the samples was executed following the test plans LAB-PLAN-10-00006, Test Plan for the Preparation of Samples from Hanford Tanks 241-SX-105, 241-AN-103, 241-AN-107, and LAB-PLN-10-00014, Test Plan for the Preparation of a Composite Sample from Hanford Tanks 241-AZ-101 and 241-AZ-102 for Steam Reformer Testing at the Savannah River National Laboratory. All procedural steps were recorded in laboratory notebook HNF-N-274 3. Sample breakdown diagrams for AN-103 and SX-105 are presented in Appendix A. The tank samples were prepared in support of a series of treatability studies of the Fluidized Bed Steam Reforming (FBSR) process using a Bench-Scale Reformer (BSR) at SRNL. Tests with simulants have shown that the FBSR mineralized waste form is comparable to low-activity waste glass with respect to environmental durability (WSRC-STI-2008-00268, Mineralization of Radioactive Wastes by Fluidized Bed Steam Reforming (FBSR): Comparisons to Vitreous Waste Forms and Pertinent Durability Testing). However, a rigorous assessment requires long-term performance data from FB SR product formed from actual Hanford tank waste. Washington River Protection Solutions, LLC (WRPS) has initiated a Waste Form Qualification Program (WP-S.2.1-20 1 0-00 1, Fluidized Bed Steam Reformer Low-level Waste Form Qualification) to gather the data required to demonstrate that an adequate FBSR mineralized waste form can be produced. The documentation of the selection process of the three tank samples has been separately reported in RPP-48824, 'Sample Selection Process for Bench-Scale Steam Reforming Treatability Studies

  8. Tank characterization report for double shell tank 241-AP-104

    Energy Technology Data Exchange (ETDEWEB)

    Winkelman, W.D., Westinghouse Hanford

    1996-08-07

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AP-104. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

  9. Tank characterization report for single shell tank 241-S-107

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.

    1996-09-19

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-S-107. This report supports the requirements of Tri- Party Agreement Milestone M-44-09.

  10. Photon interaction studies using 241Am -rays

    Indian Academy of Sciences (India)

    N Ramachandran; K Karunakaran Nair; K K Abdullah; K M Varier

    2006-09-01

    We have carried out some photon interaction measurements using 59.54 keV -rays from a 241Am source. These include attenuation studies as well as photoelectric absorption studies in various samples. The attenuation studies have been made using leaf and wood samples, samples like sand, sugar etc., which contain particles of varying sizes as well as pellets and aqueous solutions of rare earth compounds. In the case of the leaf and wood samples, we have used the -ray attenuation technique for the determination of the water content in fresh and dried samples. The variation of the attenuation coefficient with particle size has been investigated for sand and sugar samples. The attenuation studies as well as the photoelectric studies in the case of rare earth elements have been carried out on samples containing such elements whose K-absorption edge energies lie below and close to the -energy used. Suitable compounds of the rare earth elements have been chosen as mixture absorbers in these investigations. A narrow beam good geometry set-up was used for the attenuation measurements. A well-shielded scattering geometry was used for the photoelectric measurements. The mixture rule was invoked to extract the values of the mass attenuation coefficients for the elements from those of the corresponding compounds. The results are consistent with theoretical values derived from the XCOM package.

  11. Neutron capture cross section of Am241

    Science.gov (United States)

    Jandel, M.; Bredeweg, T. A.; Bond, E. M.; Chadwick, M. B.; Clement, R. R.; Couture, A.; O'Donnell, J. M.; Haight, R. C.; Kawano, T.; Reifarth, R.; Rundberg, R. S.; Ullmann, J. L.; Vieira, D. J.; Wilhelmy, J. B.; Wouters, J. M.; Agvaanluvsan, U.; Parker, W. E.; Wu, C. Y.; Becker, J. A.

    2008-09-01

    The neutron capture cross section of Am241 for incident neutrons from 0.02 eV to 320 keV has been measured with the detector for advanced neutron capture experiments (DANCE) at the Los Alamos Neutron Science Center. The thermal neutron capture cross section was determined to be 665±33 b. Our result is in good agreement with other recent measurements. Resonance parameters for En<12 eV were obtained using an R-matrix fit to the measured cross section. The results are compared with values from the ENDF/B-VII.0, Mughabghab, JENDL-3.3, and JEFF-3.1 evaluations. Γn neutron widths for the first three resonances are systematically larger by 5-15% than the ENDF/B-VII.0 values. The resonance integral above 0.5 eV was determined to be 1553±7 b. Cross sections in the resolved and unresolved energy regions above 12 eV were calculated using the Hauser-Feshbach theory incorporating the width-fluctuation correction of Moldauer. The calculated results agree well with the measured data, and the extracted averaged resonance parameters in the unresolved resonance region are consistent with those for the resolved resonances.

  12. Tank 241-B-101 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-04-28

    The Defense Nuclear Facilities Safety Board (DNFSB) has advised the US Department of Energy (DOE) to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues (Conway 1993). The data quality objective (DQO) process was chosen as a tool to be used to identify the sampling and analytical needs for the resolution of safety issues. As a result, a revision in the Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) milestone M-44 has been made, which states that ``A Tank Characterization Plan (TCP) will be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process``. This document satisfies that requirement for tank 241-B-101 (B-101) sampling activities. Tank B-101 is identified as a low-heat load non-Watch List tank, and is classified as an assumed leaker. The tank is passively ventilated, interim stabilized, and intrusion prevention measures have been completed. As of January 31, 1995, approximately 428,000 liters of non-complexed waste was contained in the tank. Tank B-101 is expected to have two primary layers. A layer of saltcake waste generated from the 242-B evaporator, followed by a top layer of sludge composed of B-Plant high-level, B-Plant low-level, and unknown waste.

  13. Tank 241-AW-101 tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Sathyanarayana, P.

    1994-11-22

    The first section gives a summary of the available information for Tank AW-101. Included in the discussion are the process history and recent sampling events for the tank, as well as general information about the tank such as its age and the risers to be used for sampling. Tank 241-AW-101 is one of the 25 tanks on the Flammable Gas Watch List. To resolve the Flammable Gas safety issue, characterization of the tanks, including intrusive tank sampling, must be performed. Prior to sampling, however, the potential for the following scenarios must be evaluated: the potential for ignition of flammable gases such as hydrogen-air and/or hydrogen-nitrous oxide; and the potential for secondary ignition of organic-nitrate/nitrate mixtures in crust layer initiated by the burning of flammable gases or by a mechanical in-tank energy source. The characterization effort applicable to this Tank Characterization Plan is focused on the resolution of the crust burn flammable gas safety issue of Tank AW-101. To evaluate the potential for a crust burn of the waste material, calorimetry tests will be performed on the waste. Differential Scanning Calorimetry (DSC) will be used to determine whether an exothermic reaction exists.

  14. 241-SY Tank Farm Construction Extent of Condition Review for Tank Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, Travis J.; Boomer, Kayle D.; Gunter, Jason R.; Venetz, Theodore J.

    2013-07-25

    This report provides the results of an extent of condition construction history review for tanks 241-SY-101, 241-SY-102, and 241-SY-103. The construction history of the 241-SY tank farm has been reviewed to identify issues similar to those experienced during tank 241-AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank 241-AY-102 as the comparison benchmark. In the 241-SY tank farm, the third DST farm constructed, refractory quality and stress relief were improved, while similar tank and liner fabrication issues remained.

  15. Test report - 241-AN-274 Caustic Pump Control Building

    Energy Technology Data Exchange (ETDEWEB)

    Paintner, G.P.

    1995-05-01

    This Acceptance Test Report documents the test results of test procedure WHC-SD-WM-ATP-135 `Acceptance Test Procedure for the 241-AN- 274 Caustic Pump Control Building.` The objective of the test was to verify that the 241-AN-274 Caustic Pump Control Building functions properly based on design specifications per applicable H-2-85573 drawings and associated ECN`s. The objective of the test was met.

  16. Analysis and characterization of double shell tank 241-AP-108

    International Nuclear Information System (INIS)

    This document is the first part of a three-part report describing the analysis and characterization of double shell tank 241-AP-108 which is located at the Hanford Reservation.This document is the analytical laboratory data package entitled 'Analysis and Characterization of Double Shell Tank 241-AP-108' which contains a case sampling history, the sampling protocols, the analytical procedures, sampling and analysis quality assurance and quality control measures, and chemical analysis results for samples obtained from the tank

  17. Hanford Single-Shell Tank Leak Causes and Locations - 241-U Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-12-02

    This document identifies 241-U Tank Farm (U Farm) leak causes and locations for the 100 series leaking tanks (241-U-104, 241-U-110, and 241-U-112) identified in RPP-RPT-50097, Rev. 0, Hanford 241-U Farm Leak Inventory Assessment Report. This document satisfies the U-Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  18. Tank 241-AZ-101 tank characterization plan

    International Nuclear Information System (INIS)

    The Defense Nuclear Facilities Safety Board has advised the DOE to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The Data Quality Objective (DQO) process was chosen as a tool to be used in the resolution of safety issues. As a result, A revision in the Federal Facilities Agreement and Consent Order (Tri-Party Agreement) milestone M-44 has been made, which states that ''A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process. Development of TCPs by the DQO process is intended to allow users to ensure their needs will be met and that resources are devoted to gaining only necessary information''. This document satisfies that requirement for Tank 241-AZ-101 (AZ-101) sampling activities. Tank AZ-101 is currently a non-Watch List tank, so the only DQOs applicable to this tank are the safety screening DQO and the compatibility DQO, as described below. The contents of Tank AZ-101, as of October 31, 1994, consisted of 3,630 kL (960 kgal) of dilute non-complexed waste and aging waste from PUREX (NCAW, neutralized current acid waste). Tank AZ-101 is expected to have two primary layers. The bottom layer is composed of 132 kL of sludge, and the top layer is composed of 3,500 kL of supernatant, with a total tank waste depth of approximately 8.87 meters

  19. Tank 241-AZ-102 tank characterization plan

    International Nuclear Information System (INIS)

    The Defense Nuclear Facilities Safety Board has advised the DOE to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The Data Quality Objective (DQO) process was chosen as a tool to be used in the resolution of safety issues. As a result, a revision in the Federal Facilities Agreement and Consent Order (Tri-Party Agreement) milestone M-44 has been made, which states that ''A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process ... Development of TCPs by the DQO process is intended to allow users to ensure their needs will be met and that resources are devoted to gaining only necessary information''. This document satisfies that requirement for tank 241-AZ-102 (AZ-102) sampling activities. Tank AZ-102 is currently a non-Watch List tank, so the only DQOs applicable to this tank are the safety screening DQO and the compatibility DQO, as described below. The current contents of Tank AZ-102, as of October 31, 1994, consisted of 3,600 kL (950 kgal) of dilute non-complexed waste and aging waste from PUREX (NCAW, neutralized current acid waste). Tank AZ-102 is expected to have two primary layers. The bottom layer is composed of 360 kL of sludge, and the top layer is composed of 3,240 kL of supernatant, with a total tank waste depth of approximately 8.9 meters

  20. Tank 241-Z-361 process and characterization history

    Energy Technology Data Exchange (ETDEWEB)

    Jones, S.A.

    1998-08-06

    An Unreviewed Safety Question (Wagoner, 1997) was declared based on lack of adequate authorization basis for Tank 241-Z-361 in the 200W Area at Hanford. This document is a summary of the history of Tank 241-Z-361 through December 1997. Documents reviewed include engineering files, laboratory notebooks from characterization efforts, waste facility process procedures, supporting documents and interviews of people`s recollections of over twenty years ago. Records of transfers into the tank, past characterization efforts, and speculation were used to estimate the current condition of Tank 241-Z-361 and its contents. Information about the overall waste system as related to the settling tank was included to help in understanding the numbering system and process relationships. The Plutonium Finishing Plant was built in 1948 and began processing plutonium in mid-1949. The Incinerator (232-Z) operated from December 1961 until May 1973. The Plutonium Reclamation Facility (PRF, 236-Z) began operation in May 1964. The Waste Treatment Facility (242-Z) operated from August 1964 until August 1976. Waste from some processes went through transfer lines to 241-Z sump tanks. High salt and organic waste under normal operation were sent to Z-9 or Z-18 cribs. Water from the retention basin may have also passed through this tank. The transfer lines to 241-Z were numbered D-4 to D-6. The 241-Z sump tanks were numbered D-4 through D-8. The D-4, 5, and 8 drains went to the D-6 sump tank. When D-6 tank was full it was transferred to D-7 tank. Prior to transfer to cribs, the D-7 tank contents was sampled. If the plutonium content was analyzed to be more than 10 g per batch, the material was (generally) reprocessed. Below the discard limit, caustic was added and the material was sent to the cribs via the 241-Z-361 settling tank where solids settled out and the liquid overflowed by gravity to the cribs. Waste liquids that passed through the 241-Z-361 settling tank flowed from PFP to ground in

  1. Tank characterization data report: Tank 241-C-112

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.; Borsheim, G.L.; Jensen, L.

    1993-09-01

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. Analysis of the process history of the tank as well as studies of simulants provided valuable information about the physical and chemical condition of the waste. This information, in combination with the analysis of the tank waste, sup ports the conclusion that an exothermic reaction in tank 241-C-112 is not plausible. Therefore, the contents of tank 241-C-112 present no imminent threat to the workers at the Hanford Site, the public, or the environment from its forrocyanide inventory. Because an exothermic reaction is not credible, the consequences of this accident scenario, as promulgated by the General Accounting Office, are not applicable.

  2. Tank characterization data report: Tank 241-C-112

    International Nuclear Information System (INIS)

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. It is probable that tank 241-C-112 exceeds the 1,000 g-mol inventory criteria established for the Ferrocyanide USQ; however, extensive energetic analysis of the waste has determined a maximum exothermic value of -9 cal/g dry waste. This value is substantially below any levels of concern (-75 cal/g). In addition, an investigation of potential mechanisms to generate concentration levels of radionuclides high enough to be of concern was performed. No credible mechanism was postulated that could initiate the formation of such concentration levels in the tank. Tank 241-C-112 waste is a complex material made up primarily of water and inert salts. The insoluble solids are a mixture of phosphates, sulfates, and hydroxides in combination with aluminum, calcium, iron, nickel, and uranium. Disodium nickel ferrocyanide and sodium cesium nickel ferrocyanide probably exist in the tank; however, there appears to have been significant degradation of this material since the waste was initially settled in the tank

  3. Tank characterization data report: Tank 241-C-112

    International Nuclear Information System (INIS)

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. Analysis of the process history of the tank as well as studies of simulants provided valuable information about the physical and chemical condition of the waste. This information, in combination with the analysis of the tank waste, sup ports the conclusion that an exothermic reaction in tank 241-C-112 is not plausible. Therefore, the contents of tank 241-C-112 present no imminent threat to the workers at the Hanford Site, the public, or the environment from its forrocyanide inventory. Because an exothermic reaction is not credible, the consequences of this accident scenario, as promulgated by the General Accounting Office, are not applicable

  4. Interim safety equipment list for 241-C-106 waste retrieval, project W-320

    International Nuclear Information System (INIS)

    The purpose of this supporting document is to provide safety classifications for systems, structures, and components of the Tank 241-C-106 Waste Retrieval Sluicing System (WRSS) and to document the methodology used to develop these safety classifications. The WRSS requires two transfer lines, one to carry sluiced waste slurry to tank 241-AY-102 and the other to return supernatant to tank 241-C-106; pumps in each tank; sluicers to direct the supernatant stream inside tank 241-C-106; a slurry distributor in tank 241-AY-102; heating, ventilation, and air conditioning for tank 241-C-106; and instrumentation and control devices

  5. 241Am (n,gamma) isomer ratio measurement

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Evelyn M [Los Alamos National Laboratory; Vieira, David J [Los Alamos National Laboratory; Moody, Walter A [Los Alamos National Laboratory; Slemmons, Alice K [Los Alamos National Laboratory

    2011-01-05

    The objective of this project is to improve the accuracy of the {sup 242}Cm/{sup 241}Am radiochemistry ratio. We have performed an activation experiment to measure the {sup 241}Am(n,{gamma}) cross section leading to either the ground state of {sup 242g}Am (t{sub 1/2} = 16 hr) which decays to {sup 242}Cm (t{sub 1/2} = 163 d) or the long-lived isomer {sup 242m}Am (t{sub 1/2} = 141 yr). This experiment will develop a new set of americium cross section evaluations that can be used with a measured {sup 242}Cm/{sup 241}Am radiochemical measurement for nuclear forensic purposes. This measurement is necessary to interpret the {sup 242}Cm/{sup 241}Am ratio because a good measurement of this neutron capture isomer ratio for {sup 241}Am does not exist. The targets were prepared in 2007 from {sup 241}Am purified from LANL stocks. Gold was added to the purified {sup 241}Am as an internal neutron fluence monitor. These targets were placed into a holder, packaged, and shipped to Forschungszentrum Karlsruhe, where they were irradiated at their Van de Graff facility in February 2008. One target was irradiated with {approx}25 keV quasimonoenergetic neutrons produced by the {sup 7}Li(p,n) reaction for 3 days and a second target was also irradiated for 3 days with {approx}500 keV neutrons. Because it will be necessary to separate the {sup 242}Cm from the {sup 241}Am in order to measure the amount of {sup 242}Cm by alpha spectrometry, research into methods for americium/curium separations were conducted concurrently. We found that anion exchange chromatography in methanol/nitric acid solutions produced good separations that could be completed in one day resulting in a sample with no residue. The samples were returned from Germany in July 2009 and were counted by gamma spectrometry. Chemical separations have commenced on the blank sample. Each sample will be spiked with {sup 244}Cm, dissolved and digested in nitric acid solutions. One third of each sample will be processed at a time

  6. Operational test procedure for Bldg 241-A-701 air compressor

    International Nuclear Information System (INIS)

    This document is an Operability Test Procedure (OTP) which will verify and record that the 241-A-701 air compressor and associated equipment operates within their intended design parameters. The activities defined in this OTP will be performed to ensure the daily operation of the new compressed air system can be reliable and efficient. The Compressed Air System (CAS) for 241-A-701 supplies process and instrument air to the A, AX, AY, and AZ tank farms. The primary use of the CAS is for tank farms instrumentation, air operated valves, and air lift circulators

  7. Vertical distribution of 241Pu in the southern Baltic Sea sediments

    International Nuclear Information System (INIS)

    Highlights: • The unique study on 241Pu in sediments from the southern Baltic Sea was presented. • 241Pu was determined using alpha spectrometry by indirect method. • The biggest amount of 241Pu existed in the surface layers of all analyzed sediments. • The highest 241Pu amount comes from the Chernobyl accident. - Abstract: The vertical distribution of plutonium 241Pu in marine sediments can assist in determining the deposition history and sedimentation process of analyzed regions. In addition, 241Pu/239+240Pu activity ratio could be used as a sensitive fingerprint for radioactive source identification. The present preliminary studies on vertical distribution of 241Pu in sediments from four regions of the southern Baltic Sea are presented. The distribution of 241Pu was not uniform and depended on sediment geomorphology and depth as well as location. The highest concentrations of plutonium were found in the surface layers of all analyzed sediments and originated from the Chernobyl accident

  8. Review of Waste Retrieval Sluicing System Operations and Data for Tanks 241-C-106 and 241-AY-102

    Energy Technology Data Exchange (ETDEWEB)

    Cuta, Judith M.; Carothers, Kelly G.; Damschen, Dennis W.; Kuhn, William L.; Lechelt, Jeanne A.; Sathyanarayana, Kurabalakota; Stauffer, Leslie A.

    2000-09-26

    Sluicing operations were performed to retrieve high-heat sludge from single-shell tank 241-C-106 and transfer it to double-shell tank 241-AY-102 using the Waste Retrieval Sluicing System. This eliminated the high-heat safety issue for C-106 and demonstrated a technology for retrieval of single-shell tank waste. Both AY-102 and C-106 were monitored during the waste transfer operations, providing a clear picture of general trends in each tank. Specific issues addressed were evaluation of the data for evidence of flammable gas accumulation in AY-102 and thermal performance of AY-102 under the increasing heat load.

  9. Residual Waste from Hanford Tanks 241-C-203 and 241-C-204. 2. Contaminant Release Model

    International Nuclear Information System (INIS)

    Fusion analyses, water leaches, selective extractions, empirical solubility measurements, and thermodynamic modeling were used with results from solid-phase characterization studies [see companion paper (1)] to determine total concentrations, contaminant-phase associations, and develop contaminant release models for residual sludge from single-shell underground waste tanks 241-C-203 and 241-C-204 at the U.S. Department of Energy?s Hanford Site in southeastern Washington state. U and Tc are primary contaminants of concern because of their long half-lives and their generally high mobility in oxidizing soil and groundwater environments. Uranium release was determined to be controlled by two phases; ?ejkaite [Na4(UO2)(CO3)3] and poorly crystalline Na2U2O7 [or clarkeite Na[(UO2)O(OH)](H2O)0-1] which were identified in C-203 and C-204 sludge samples (1). U release was determined to occur in three stages from these phases. In the first stage, U release will be controlled by the solubility of ?ejkaite, which is suppressed by high concentrations of sodium released from dissolution of NaNO3 in the residual sludges. Equilibrium solubility calculations indicate the U released during this stage will have a maximum concentration of 0.021 M. When all the NaNO3 has dissolved from the sludge, the solubility of the remaining ?ejkaite will increase to 0.28 M. After ?ejkaite has completely dissolved, the maximum concentration of U released is expected to be controlled by the solubility of Na2U2O7 at a concentration of 3.0 ? 10-5 M. For Tc, a significant fraction of its concentration in the residual sludge was determined to be relatively insoluble (20 wt% for C-203 and 80 wt% for C-204). Because of the low concentrations of Tc in these sludge materials, the characterization studies did not identify any discrete Tc solids phases. Therefore, release of the readily soluble fraction of Tc was assumed to be controlled by the solubility of NaTcO4 at 7.1 M. Selective extraction results

  10. Hanford Single Shell Tank Leak Causes and Locations - 241-TX Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, C. L.; Harlow, D> G.

    2014-07-22

    This document identifies 241-TX Tank Farm (TX Farm) leak causes and locations for the 100 series leaking tanks (241-TX-107 and 241-TX-114) identified in RPP-RPT-50870, Rev. 0, Hanford 241-TX Farm Leak Inventory Assessment Report. This document satisfies the TX Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  11. Hanford Single-Shell Tank Leak Causes and Locations - 241-T Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2014-05-15

    This document identifies 241-T Tank Farm (T Farm) leak causes and locations for the 100 series leaking tanks (241-T-106 and 241-T-111) identified in RPP-RPT-55084, Rev. 0, Hanford 241-T Farm Leak Inventory Assessment Report. This document satisfies the T Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  12. 48 CFR 52.241-13 - Capital Credits.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Capital Credits. 52.241-13... Capital Credits. As prescribed in 41.501(d)(7), insert a clause substantially the same as the following: Capital Credits (FEB 1995) (a) The Government is a member of the ____ , and as any other member,...

  13. Tagging fast neutrons from an (241)Am/(9)Be source.

    Science.gov (United States)

    Scherzinger, J; Annand, J R M; Davatz, G; Fissum, K G; Gendotti, U; Hall-Wilton, R; Håkansson, E; Jebali, R; Kanaki, K; Lundin, M; Nilsson, B; Rosborge, A; Svensson, H

    2015-04-01

    Shielding, coincidence, and time-of-flight measurement techniques are employed to tag fast neutrons emitted from an (241)Am/(9)Be source resulting in a continuous polychromatic energy-tagged beam of neutrons with energies up to 7MeV. The measured energy structure of the beam agrees qualitatively with both previous measurements and theoretical calculations. PMID:25644080

  14. ANALYSIS RESULTS FOR BUILDING 241 702-AZ A TRAIN

    International Nuclear Information System (INIS)

    This report presents the analyses results for three samples obtained under RPP-PLAN-28509, Sampling and Analysis Plan for Building 241 702-AZ A Train. The sampling and analysis was done in response to problem evaluation request number PER-2004-6139, 702-AZ Filter Rooms Need Radiological Cleanup Efforts

  15. 16 CFR 2.41 - Reports of compliance.

    Science.gov (United States)

    2010-01-01

    ... be under oath if so requested. Where the order prohibits the use of a false advertisement of a food... Federal Register citations affecting § 2.41, see the List of CFR Sections Affected, which appears in the... conditions prescribed in the advertisement, or under such conditions as are customary or usual, or if the...

  16. Tank 241-C-101: Tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    This document is a plan which serves as the contractual agreement between the characterization program, sampling operations, and WHC 222-S Laboratory. Scope of this plan is to provide guidance for sampling and analysis of samples for tank 241-C-101. The sampling type has been changed from push mode core sampling to auger sampling

  17. Solubilization of 241AmO2 in siderophore solutions

    International Nuclear Information System (INIS)

    The solubilization of 241AmO2 in tissue culture medium was measured. Variables included serum concentration, chelon type, and time. Serum was found to affect the soluble (0.1 μm filterable) fraction more than any other variable

  18. Justification for Continued Operation for Tank 241-Z-361

    Energy Technology Data Exchange (ETDEWEB)

    BOGEN, D.M.

    1999-09-01

    This justification for continued operations (JCO) summarizes analyses performed to better understand and control the potential hazards associated with Tank 241-2-361. This revision to the JCO has been prepared to identify and control the hazards associated with sampling the tank using techniques developed and approved for use in the Tank Waste Remediation System (TWRS) at Hanford.

  19. Project W-320, 241-C-106 sluicing supporting documentation bibliography

    International Nuclear Information System (INIS)

    This supporting document has been prepared to make the listing of documentation used to develop, or in support of Project W-320, readily retrievable. All documents are sorted by document number and list the document type. Tank 241-C-106 has been included on the High Heat Load Watch List

  20. Solid Phase Characterization of Tank 241-C-105 Grab Samples

    Energy Technology Data Exchange (ETDEWEB)

    Ely, T. M. [Washington River Protection Solutions LLC, Richland, WA (United States); LaMothe, M. E. [Washington River Protection Solutions LLC, Richland, WA (United States); Lachut, J. S. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2016-01-11

    The solid phase characterization (SPC) of three grab samples from single-shell Tank 241-C-105 (C-105) that were received at the laboratory the week of October 26, 2015, has been completed. The three samples were received and broken down in the 11A hot cells.

  1. Tank 241-C-101: Tank characterization plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1995-03-08

    This document is a plan which serves as the contractual agreement between the characterization program, sampling operations, and WHC 222-S Laboratory. Scope of this plan is to provide guidance for sampling and analysis of samples for tank 241-C-101. The sampling type has been changed from push mode core sampling to auger sampling.

  2. 27 CFR 24.241 - Decolorizing juice or wine.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Decolorizing juice or wine..., DEPARTMENT OF THE TREASURY LIQUORS WINE Storage, Treatment and Finishing of Wine § 24.241 Decolorizing juice or wine. (a) Conditions and limitations. If the proprietor wishes to use activated carbon or...

  3. Justification for Continued Operation for Tank 241-Z-361

    International Nuclear Information System (INIS)

    This justification for continued operations (JCO) summarizes analyses performed to better understand and control the potential hazards associated with Tank 241-2-361. This revision to the JCO has been prepared to identify and control the hazards associated with sampling the tank using techniques developed and approved for use in the Tank Waste Remediation System (TWRS) at Hanford

  4. ANALYSIS RESULTS FOR BUILDING 241 702-AZ A TRAIN

    Energy Technology Data Exchange (ETDEWEB)

    DUNCAN JB; FRYE JM; COOKE CA; LI SW; BROCKMAN FJ

    2006-12-13

    This report presents the analyses results for three samples obtained under RPP-PLAN-28509, Sampling and Analysis Plan for Building 241 702-AZ A Train. The sampling and analysis was done in response to problem evaluation request number PER-2004-6139, 702-AZ Filter Rooms Need Radiological Cleanup Efforts.

  5. 40 CFR 180.241 - Bensulide; tolerances for residues.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Bensulide; tolerances for residues...) PESTICIDE PROGRAMS TOLERANCES AND EXEMPTIONS FOR PESTICIDE CHEMICAL RESIDUES IN FOOD Specific Tolerances § 180.241 Bensulide; tolerances for residues. (a) General. Tolerances are established for the...

  6. 30 CFR 241.76 - Can MMS reduce my penalty once it is assessed?

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Can MMS reduce my penalty once it is assessed? 241.76 Section 241.76 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR... Provisions § 241.76 Can MMS reduce my penalty once it is assessed? Under 30 U.S.C. 1719(g), the Director...

  7. 33 CFR 241.5 - Procedures for estimating the alternative cost-share.

    Science.gov (United States)

    2010-07-01

    ... alternative cost-share. 241.5 Section 241.5 Navigation and Navigable Waters CORPS OF ENGINEERS, DEPARTMENT OF THE ARMY, DEPARTMENT OF DEFENSE FLOOD CONTROL COST-SHARING REQUIREMENTS UNDER THE ABILITY TO PAY PROVISION § 241.5 Procedures for estimating the alternative cost-share. (a) Step one, the benefits...

  8. Analysis of the 241SY101 pump removal trailer and the 241SY101 strongback

    International Nuclear Information System (INIS)

    The purpose of the calculations contained in the attached appendix is to determine the vibrational stability of the following combination (The Combination); shipping container, strongback and trailer. The vibrational stability of The Combination will be determined with the shipping container and strongback in the upright position. If the natural frequency of The Combination coincides with the input frequency and no damping is present, resonance will occur. The result of this is that the natural frequency of the Combination must be calculated as well as the input frequency. The input frequency in this case is caused by wind. Due to their geometrical complexity the upper and lower hydraulic clevises were analyzed for structural adequacy by using finite-element analysis (FEA). The FEA software COSMOS/M version 1.70 was used to model the upper and lower hydraulic clevis. All designs are in accordance with Standard Architectural-Civil Design Criteria, Design Loads for Facilities (DOE-RL 1989) and are safety class 3. The design and fabrication of each component is in accordance with American Institute of Steel Construction, Manual of Steel Construction, (AISC, 1989). The analyses contained in this document reflects the as-built condition of the 241SY101 hydraulic trailer

  9. Tank 241-A-105 evaporation estimate, 1970 through 1978

    International Nuclear Information System (INIS)

    Tank 241-A-105 was subjected to a severe steam explosion in January 1965 that caused the metal liner on the bottom to bulge upward approximately 8 feet above its concrete foundation. Shortly after this event, radiation was detected in drywells around the tank and it was declared a leaker. Sluicing operations to remove material from the tank began in August 1968 and continued through August 1970. After sluicing was completed, a significant amount of heat generating material still remained in the tank. To keep tank temperatures below operating limits, the water level in the tank was maintained at an approximate depth of 1.5 feet. This practice was continued until January 1979 when it was believed that the contents had decayed sufficiently to discontinue the water addition and put the tank on a portable exhauster system. Recent concern has focused on what portion of this cooling water added to Tank 241-A-105 actually evaporated and how much leaked into the soil during the nine year time period. This report presents the results of a study that estimates the amount of water evaporated from Tank 241-A-105 between 1970 and 1979. The problem was completed in two parts. The first part involved development of a three dimensional heat transfer model which was used to establish the tank heat load. The results of this model were validated against thermocouple data from Tank 241-A-105. The heat removed from the tank by the ventilation air was then used as input to a second computer code, which calculated the water evaporation. Based upon these two models, the amount of water evaporated from Tank 241-A-105, between 1970 and 1979, was between 378,000 and 410,000 gallons. 9 refs., 17 figs., 7 tabs

  10. Test Results for Caustic Demand Measurements on Tank 241-AX-101 and Tank 241-AX-103 Archive Samples

    Energy Technology Data Exchange (ETDEWEB)

    Doll, Stephanie R. [Washington River Protection Solutions, Richland, WA (United States); Bolling, Stacie D. [Washington River Protection Solutions, Richland, WA (United States)

    2016-07-14

    Caustic demand testing is used to determine the necessary amount of caustic required to neutralize species present in the Hanford tank waste and obtain a target molarity of free hydroxide for tank corrosion control. The presence and quantity of hydroxide-consuming analytes are just as important in determining the caustic demand as is the amount of free hydroxide present. No single data point can accurately predict whether a satisfactory hydroxide level is being met as it is dependent on multiple factors (e.g., free hydroxide, buffers, amphoteric metal hydroxides, bicarbonate, etc.). This enclosure contains the caustic demand, scanning electron microscopy (SEM), polarized light microscopy (PLM), and X-ray diffraction (XRD) analysis for the tank 241-AX-101 (AX-101) and 241-AX-103 (AX-103) samples. The work was completed to fulfill a customer request outlined in the test plan, WRPS-1505529, “Test Plan and Procedure for Caustic Demand Testing on Tank 241-AX-101 and Tank 241-AX-103 Archive Samples.” The work results will provide a baseline to support planned retrieval of AX-101 and AX-103.

  11. Bioremoval of Am-241 and Cs-137 from liquid radioactive wasters by bacterial consortiums; Biorremocao de Am-241 e Cs-137 de rejeitos radioativos liquidos por consorcios bacterianos

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Rafael Vicente de Padua; Lima, Josenilson B. de; Gomes, Mirella C.; Borba, Tania R.; Bellini, Maria Helena; Marumo, Julio Takehiro; Sakata, Solange Kazumi, E-mail: rpadua@ipen.b, E-mail: sksakata@ipen.b, E-mail: jblima@ipen.b, E-mail: mbmarumo@ipen.b, E-mail: jtmarumo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-10-26

    This paper evaluates the capacity of two bacterial consortiums of impacted areas in removing the Am-241 and Cs-137 from liquid radioactive wastes.The experiments indicated that the two study consortiums were able to remove 100% of the Cs-137 and Am-241 presents in the waste from 4 days of contact. These results suggest that the bio removal with the selected consortiums, can be a viable technique for the treatment of radioactive wastes containing Am-241 and Cs-137

  12. 241-AY-101 Tank Construction Extent of Condition Review for Tank Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, Travis J.; Gunter, Jason R.

    2013-08-26

    This report provides the results of an extent of condition construction history review for tank 241-AY-101. The construction history of tank 241-AY-101 has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In tank 241-AY-101, the second double-shell tank constructed, similar issues as those with tank 241-AY-102 construction reoccurred. The overall extent of similary and affect on tank 241-AY-101 integrity is described herein.

  13. 241-AW Tank Farm Construction Extent of Condition Review for Tank Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, Travis J.; Gunter, Jason R.; Reeploeg, Gretchen E.

    2013-11-19

    This report provides the results of an extent of condition construction history review for the 241-AW tank farm. The construction history of the 241-AW tank farm has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In the 241-AW tank farm, the fourth double-shell tank farm constructed, similar issues as those with tank 241-AY-102 construction occured. The overall extent of similary and affect on 241-AW tank farm integrity is described herein.

  14. Operability test procedure [Tank] 241-SY-101 equipment removal system

    International Nuclear Information System (INIS)

    The 241-SY-101 equipment removal system (ERS) consists of components, equipment, instrumentation and procedures that will provide the means to disconnect, retrieve, contain, load and transport the Mitigation Pump Assembly (MPA) from waste Tank 241-SY-101 to the Central Waste Complex (CWC). The Operability Test Procedure (OTP) will test the interfaces between ERS components and will rehearse the procedure for MPA removal and transportation to the extent they can be mocked-up at the CTF (Cold Test Facility). At the conclusion of the OTP, the ERS components and equipment will be removed from the CTF, entered into the Component Based Recall System (CBRS), and stored until needed for actual MPA removal and transportation

  15. 241-AZ Double Shell Tanks (DST) Integrity Assessment Report

    Energy Technology Data Exchange (ETDEWEB)

    JENSEN, C.E.

    1999-09-21

    This report presents the results of the integrity assessment of the 241-A2 double-shell tank farm facility located in the 200 East Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations, are made to ensure the continued safe operation of the tanks.

  16. 241-AY Double Shell Tanks (DST) Integrity Assessment Report

    Energy Technology Data Exchange (ETDEWEB)

    JENSEN, C.E.

    1999-09-21

    This report presents the results of the integrity assessment of the 241-AY double-shell tank farm facility located in the 200 East Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations. are made to ensure the continued safe operation of the tanks.

  17. Tank 241-Z-361 Sludge Retrieval and Treatment Alternatives

    Energy Technology Data Exchange (ETDEWEB)

    HAMPTON, B.K.

    2000-05-24

    The Plutonium Finishing Plant (PFP) Tank 241-Z-361 (Z-361) contains legacy sludge resulting from waste discharges from past missions at PFP. A sketch of the tank is shown in Figure 1. In this view various risers and penetrations are shown along with the sludge level depicted by the horizontal line halfway up the tank, and the ground level depicted by the horizontal line above the tank. The HEPA filter installed for breathing is also shown on one of the risers.

  18. 241-AN Double Shell Tanks (DST) Integrity Assessment Report

    Energy Technology Data Exchange (ETDEWEB)

    JENSEN, C.E.

    1999-09-21

    This report presents the results of the integrity assessment of the 241-AN double-shell tank farm facility located in the 200 East Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations, are made to ensure the continued safe operation of the tanks.

  19. 241-AN Double Shell Tanks (DST) Integrity Assessment Report

    International Nuclear Information System (INIS)

    This report presents the results of the integrity assessment of the 241-AN double-shell tank farm facility located in the 200 East Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations, are made to ensure the continued safe operation of the tanks

  20. 241-SY Double Shell Tanks (DST) Integrity Assessment Report

    International Nuclear Information System (INIS)

    This report presents the results of the integrity assessment of the 241-SY double-shell tank farm facility located in the 200 West Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations, are made to ensure the continued safe operation of the tanks

  1. 241-AW Double Shell Tanks (DST) Integrity Assessment Report

    International Nuclear Information System (INIS)

    This report presents the results of the integrity assessment of the 241-AW double-shell tank farm facility located in the 200 East Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations, are made to ensure the continued safe operation of the tanks

  2. 241-AZ Double-Shell Tanks (DST) Integrity Assessment Report

    International Nuclear Information System (INIS)

    This report presents the results of the integrity assessment of the 241-A2 double-shell tank farm facility located in the 200 East Area of the Hanford Site. The assessment included the design evaluation and integrity examinations of the tanks and concluded that the facility is adequately designed, is compatible with the waste, and is fit for use. Recommendations including subsequent examinations, are made to ensure the continued safe operation of the tanks

  3. Status of tank 241-SY-101 data analyses

    International Nuclear Information System (INIS)

    The Waste Tank Flammable Gas Stabilization Program was established in 1990 to provide for resolution of a major safety issue identified for 23 of the high-level waste tanks at the Hanford Site. The safety issue involves the production, accumulation, and periodic release from these tanks of flammable gases in concentrations exceeding the lower flammability limits. This document deals primarily with tank 241-SY-101 from the SY Tank Farm. The flammable gas condition has existed for this tank since the tank was first filled in the time period from 1977 to 1980. During a general review of waste tank chemical stability in 1988--1989, this situation was re-examined and, in March 1990, the condition was declared to be an unreviewed safety question. Tank 241-SY-101 was placed under special operating restrictions, and a program of investigation was begun to evaluate the condition and determine appropriate courses of action. This report summarizes the data that have become available on tank 241-SY-101 since it was declared as an unreviewed safety question and updates the information reported in an earlier document (WHC-EP-0517). The report provides a technical basis for use in the evaluation of safety risks of the tank and subsequent resolution of the unreviewed safety question

  4. Status of tank 241-SY-101 data analyses

    Energy Technology Data Exchange (ETDEWEB)

    Anantatmula, R.P.

    1992-09-01

    The Waste Tank Flammable Gas Stabilization Program was established in 1990 to provide for resolution of a major safety issue identified for 23 of the high-level waste tanks at the Hanford Site. The safety issue involves the production, accumulation, and periodic release from these tanks of flammable gases in concentrations exceeding the lower flammability limits. This document deals primarily with tank 241-SY-101 from the SY Tank Farm. The flammable gas condition has existed for this tank since the tank was first filled in the time period from 1977 to 1980. During a general review of waste tank chemical stability in 1988--1989, this situation was re-examined and, in March 1990, the condition was declared to be an unreviewed safety question. Tank 241-SY-101 was placed under special operating restrictions, and a program of investigation was begun to evaluate the condition and determine appropriate courses of action. This report summarizes the data that have become available on tank 241-SY-101 since it was declared as an unreviewed safety question and updates the information reported in an earlier document (WHC-EP-0517). The report provides a technical basis for use in the evaluation of safety risks of the tank and subsequent resolution of the unreviewed safety question.

  5. Project W-211, initial tank retrieval systems, description of operations for 241-AP-102 and 241-AP-104

    Energy Technology Data Exchange (ETDEWEB)

    RIECK, C.A.

    1999-02-25

    The primary purpose of the Initial Tank Retrieval Systems (ITRS) is to provide systems for retrieval of radioactive wastes stored in underground double-shell tanks (DSTS) for transfer to alternate storage, evaporation, pretreatment or treatment, while concurrently reducing risks associated with safety watch list and other DSTs. This Description of Operations (DOO) defines the control philosophy for the waste retrieval system for tanks 241-AP-102 (AP-102) and 241-AP-104 (AP-104). This DOO will provide a basis for the detailed design of the Retrieval Control System (RCS) for AP-102 and AP-104 and establishes test criteria for the RCS. The test criteria will be used during qualification testing and acceptance testing to verify operability.

  6. Ion exchange removal of cesium from simulated and actual supernate from Hanford tanks 241-SY-101 and 241-SY-103

    International Nuclear Information System (INIS)

    Pacific Northwest Laboratory (PNL), in conjunction with the Process Chemistry and Statistics Section of Westinghouse Hanford Company (WHC), conducted this study as part of the Supernatant Treatment Development Task for the Initial Pretreatment Module (IPM) Applied Engineering Project. The study assesses the performance of the CS-100 ion exchange material for removing cesium from simulated and actual alkaline supernate from Hanford tanks 241-SY-101 and 241-SY-103. The objective of these experiments is to compare the cesium ion exchange loading and elution profiles of actual and simulated wastes. Specific experimental objectives include (1) demonstration of decontamination factors (DF) for cesium removal, 92) verification of simulant performance, (3) investigation of waste/exchanger chemistry, and (4) determination of the radionuclide content of the regenerated CS-100 resin prior to disposal

  7. Speciation and bioavailability of Americium-241 in the fresh water environment

    International Nuclear Information System (INIS)

    Due to its anthropogenic origin, the transuranic americium 241 confronts physiologists with the intriguing question, which mechanisms are involved in the incorporation or elimination of such artificial elements in biological cycles. The investigations on the speciation and bioavailability of 241Am in the freshwater environment aim to establish a relation between the behavior of 241Am in freshwater ecosystems and its availability for biota. In the limnic environment, most often characterized by a high organic load and a low conductivity, the effect of complexation of 241Am with humic acids and competition with trivalent cations such as A1 and Fe, were proven to be significant on the speciation of 241Am. Based on the registration of the 241Am uptake by a large number of freshwater organisms, the crayfish Astacus leptodactylus Eschscholtz was chosen to study the whole-body uptake of 241Am, its corresponding organ distribution and its retention in the animal. The share of external fixation and ingestion in the global uptake, and the effect of speciation on it, were studied more carefully. Other aspects in this physiological part were: the kinetics of 241Am in the hemolymph and the hepatopancreas, and its subcellular distribution in the digestive gland. Finally, by comparing the physiology of 241Am with some other metals (240Pu, 64Cu, 198Au) with analogous or contradictional properties, we tried to find out whether the behavior of 241Am in organisms can be explained from its chemical characteristics

  8. Investigation of the retention and distribution of americium-241 in the baboon and the enhanced removal of americium-241 from the body by diethylenetriaminepentaacetic acid (DTPA)

    International Nuclear Information System (INIS)

    Experiments were performed to study the metabolism and distribution of intravenously administered 241Am in the adult and juvenile baboon; in addition, decorporation therapy using Na3-CaDTPA was performed on selected baboons to assess the efficacy of this drug in removing systemic burdens of 241Am from this primate species. Determination of the kinetics of 241Am was accomplished principally by in vivo methodologies and by radiochemical analysis of 241Am activity of biological material. The use of Na3-CaDTPA as a therapeutic agent for the removal of 241Am from the body proved to be an effective form of treatment in the case of early administration. (U.S.)

  9. Recovery of Americium-241 from lightning rod by the method of chemical treatment; Recuperacion del Americio-241 provenientes de los pararrayos por el metodo de tratamiento quimico

    Energy Technology Data Exchange (ETDEWEB)

    Cruz, W.H., E-mail: wcruz@ipen.gob.pe [Instituto Peruano de Energia Nuclear (GRRA/IPEN), Lima (Peru). Division de Gestion de Residuos Radiactivos

    2013-07-01

    About 95% of the lightning rods installed in the Peruvian territory have set in their structures, pose small amounts of radioactive sources such as Americium-241 ({sup 241}Am), fewer and Radium 226 ({sup 226}Ra) these are alpha emitters and have a half life of 432 years and 1600 years respectively. In this paper describes the recovery of radioactive sources of {sup 241}Am radioactive lightning rods using the conventional chemical treatment method using agents and acids to break down the slides. The {sup 241}Am recovered was as excitation source and alpha particle generator for analysing samples by X Ray Fluorescence, for fixing the stainless steel {sup 241}Am technique was used electrodeposition. (author)

  10. Hanford Single-Shell Tank Leak Causes and Locations - 241-A Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-09-10

    This document identifies 241-A Tank Farm (A Farm) leak causes and locations for the 100 series leaking tanks (241-A-104 and 241-A-105) identified in RPP-ENV-37956, Hanford A and AX Farm Leak Assessment Report. This document satisfies the A Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  11. Hanford Single-Shell Tank Leak Causes and Locations - 241-C Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L.; Harlow, Donald G.

    2013-07-30

    This document identifies 241-C Tank Farm (C Farm) leak causes and locations for the 100 series leaking tanks (241-C-101 and 241-C-105) identified in RPP-RPT-33418, Rev. 2, Hanford C-Farm Leak Inventory Assessments Report. This document satisfies the C Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  12. {sup 241}Pu concentrations in water, plankton and fish from the southern Baltic Sea

    Energy Technology Data Exchange (ETDEWEB)

    Struminska-Parulska, D.I.; Skwarzec, B. [Gdansk, Univ. (Poland). Facuty of Chemistry

    2013-08-01

    The aim of the work was to determine {sup 241}Pu activities in different components (water, plankton and fish) of the southern Baltic Sea ecosystem. Measurement of {sup 241}Pu in the samples was done indirectly by determining the increment in {sup 241}Am from the decay of the {beta}-emitting {sup 241}Pu in samples collected 10-15 years after the Chernobyl accident. Enhanced levels of {sup 241}Pu were observed in all analyzed Baltic samples. The highest {sup 241}Pu concentrations in fish were found in Perciformes: benthic round goby (0.863 {+-} 0.066 mBq/g ww) and pelagic perch (0.666 {+-} 0.001 mBq/g ww). Plutonium is also non-uniformly distributed in the organs and tissues of the analyzed fish; especially pelagic herring and cod as well as benthic flounder. Most of {sup 241}Pu in flounder, herring and cod is located in soft tissues, especially digestive organs (stomach, intestine, liver). The annual individual effective doses calculated on the basis of {sup 241}Pu concentrations in fish indicated that the impact of the consumption of {sup 241}Pu containing Baltic fish on the annual effective dose for a statistical inhabitant of Poland was very small. (orig.)

  13. 241-AZ Tank Farm Construction Extent of Condition Review for Tank Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, Travis J.; Boomer, Kayle D.; Gunter, Jason R.; Venetz, Theodore J.

    2013-07-30

    This report provides the results of an extent of condition construction history review for tanks 241-AZ-101 and 241-AZ-102. The construction history of the 241-AZ tank farm has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In the 241-AZ tank farm, the second DST farm constructed, both refractory quality and tank and liner fabrication were improved.

  14. Vertical distribution of (241)Pu in the southern Baltic Sea sediments.

    Science.gov (United States)

    Strumińska-Parulska, Dagmara I

    2014-12-15

    The vertical distribution of plutonium (241)Pu in marine sediments can assist in determining the deposition history and sedimentation process of analyzed regions. In addition, (241)Pu/(239+240)Pu activity ratio could be used as a sensitive fingerprint for radioactive source identification. The present preliminary studies on vertical distribution of (241)Pu in sediments from four regions of the southern Baltic Sea are presented. The distribution of (241)Pu was not uniform and depended on sediment geomorphology and depth as well as location. The highest concentrations of plutonium were found in the surface layers of all analyzed sediments and originated from the Chernobyl accident.

  15. Tank 241-AZ-102 Privatization Push Mode Core Sampling and Analysis Plan

    International Nuclear Information System (INIS)

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for samples obtained from tank 241-AZ-102

  16. Electronic structure of polycrystalline Cd metal using 241Am radioisotope

    Science.gov (United States)

    Dhaka, M. S.; Sharma, G.; Mishra, M. C.; Sharma, B. K.

    2014-04-01

    Electronic structure study of the polycrystalline cadmium metal is reported. The experimental measurement is undertaken on a polycrystalline sheet sample using 59.54 keV radioisotope of 241Am. These results are compared with the ab initio calculations. The theoretical calculations are performed using linear combination of atomic orbitals (LCAO) method employing the density functional theories (DFT) and Hartree-Fock (HF) and augmented plane wave (APW) methods. The spherically averaged APW and LCAO based theoretical Compton profiles are in good agreement with the experimental measurement however the APW based theoretical calculations show best agreement.

  17. Effect of 241-americium on bone marrow stroma

    International Nuclear Information System (INIS)

    The regulation of haemopoiesis occurs via complex interactions between the stroma and the haemopoietic cells. An attempt to further clarifying the mechanisms and the exact role of the stroma in the regulation was made in a study. Results revealed that the murine bone marrow stromal cells are highly radiosensitive after injection with 241-americium and can thus be considered as a target population after internal contamination. In addition, observations are made which may be important for risk estimation for the developing animal and during pregnancy. Contamination in utero and by lactation shows persistent damage up to 1 year after contamination at an average annual dose of 5 cGy. (author)

  18. Formulation verification study results for 241-AN-106 waste grout

    International Nuclear Information System (INIS)

    Tests were conducted to determine whether the reference formulation and variations around the formulation are adequate for solidifying 241-AN-106 (106-AN) waste into a grout waste form. The reference formulation consists of 21 wt% type I/II Portland cement, 68 wt% fly ash, and 11 wt% attapulgite clay. The mix ratio is 8.4 lb/gal. Variations in dry blend component ratios, mix ratio, and waste concentration were assessed by using a statistically designed experimental matrix consisting of 44 grout compositions. Based on the results of the statistically designed variability study, the 106-AN grout formulations tested met all the formulation criteria except for the heat of hydration

  19. Preliminary investigation on biosorption mechanism of 241Am by Rhizopus arrhizus

    International Nuclear Information System (INIS)

    As an important radioisotope in nuclear industry and other fields, 241Am is one of the most serious contamination concerns due to its high radiation toxicity and long half-life. Encouraging biosorption of 241Am from aqueous solutions by free or immobilized Rhizopus arrhizus (R. arrhizus) has been observed in our experiments. In this study, the preliminary evaluation on the mechanism was further explored via chemical or biological modification of R. arrhizus using europium as a substitute for americium. The results indicated that in approximately 48 hours R. arrhizus was able for efficient adsorption of 241Am. The pH value of solutions decreased gradually with the uptake of 241Am by R. arrhizus, implying that H+ was released from R. arrhizus via ion-exchange. The biosorption of 241Am by the decomposed cell wall of R. arrhizus was as efficient as by the intact fungus. The adsorption ratio for 241Am by deacylated R. arrhizus dropped, implying that carboxyl functional groups of R. arrhizus play an important role in the biosorption of 241Am. Most of the investigated acidic ions have no significant influence on the adsorption of 241Am, while saturated EDTA can strongly inhibit the biosorption of 241Am by R. arrhizus. When the concentrations of coexistent Eu3+, Nd3+ were 300 times more than that of 241Am, the adsorption ratios would decrease to about 86% from more than 99%. It could be noted by transmission electron microscope (TEM) analysis that the adsorbed Eu is scattered almost in the whole fungus, while Rutherford backscattering spectrometry (RBS) indicated that Ca in R. arrhizus have been replaced by Eu via ion-exchange. The change of the absorption peak structure in the IR spectra implied that there was complexation between metals and microorganism. The results implied that the adsorption mechanism of 241Am by R. arrhizus is very complicated involved ion-exchange, complexation process as well as nonspecific adsorption in the cell wall by static electricity. (author)

  20. Neutron capture and (n,2n) measurements on 241Am

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, D; Jandel, M; Bredeweg, T; Bond, E; Clement, R; Couture, A; Haight, R; O' Donnell, J; Reifarth, R; Ullmann, J; Wilhelmy, J; Wouters, J; Tonchev, A; Hutcheson, A; Angell, C; Crowell, A; Fallin, B; Hammond, S; Howell, C; Karowowski, H; Kelley, J; Pedroni, R; Tornow, W; Macri, R; Agvaanluvsan, U; Becker, J; Dashdorj, D; Stoyer, M; Wu, C

    2007-07-18

    We report on a set of neutron-induced reaction measurements on {sup 241}Am which are important for nuclear forensics and advanced nuclear reactor design. Neutron capture measurements have been performed on the DANCE detector array at the Los Alamos Neutron Scattering CEnter (LANSCE). In general, good agreement is found with the most recent data evaluations up to an incident neutron energy of {approx} 300 keV where background limits the measurement. Using mono-energetic neutrons produced in the {sup 2}H(d,n){sup 3}He reaction at Triangle University Nuclear Laboratory (TUNL), we have measured the {sup 241}Am(n,2n) excitation function from threshold (6.7 MeV) to 14.5 MeV using the activation method. Good agreement is found with previous measurements, with the exception of the three data points reported by Perdikakis et al. around 11 MeV, where we obtain a much lower cross section that is more consistent with theoretical estimates.

  1. Evaluation of tank waste transfers at 241-AW tank farm

    International Nuclear Information System (INIS)

    A number of waste transfers are needed to process and feed waste to the private contractors in support of Phase 1 Privatization. Other waste transfers are needed to support the 242-A Evaporator, saltwell pumping, and other ongoing Tank Waste Remediation System (TWRS) operations. The purpose of this evaluation is to determine if existing or planned equipment and systems are capable of supporting the Privatization Mission of the Tank Farms and continuing operations through the end of Phase 1B Privatization Mission. Projects W-211 and W-314 have been established and will support the privatization effort. Equipment and system upgrades provided by these projects (W-211 and W-314) will also support other ongoing operations in the tank farms. It is recognized that these projects do not support the entire transfer schedule represented in the Tank Waste Remediation system Operation and Utilization Plan. Additionally, transfers surrounding the 241-AW farm must be considered. This evaluation is provided as information, which will help to define transfer paths required to complete the Waste Feed Delivery (WFD) mission. This document is not focused on changing a particular project, but it is realized that new project work in the 241-AW Tank Farm is required

  2. Biosorption of 241Am by Rhizopus arrihizus: preliminary investigation and evaluation

    International Nuclear Information System (INIS)

    The biosorption of 241Am from solution by a fungus--Rhizopus Arrihizus (R. arrihizus), and the effect of experimental conditions on the adsorption were investigated. The preliminary results showed that the biosorption of 241Am by R. arrihizus is very efficient. An average of more than 99% of the total 241Am was removed by R. arrihizus of 1.3 g/l (dry weight) from 241Am solutions of 5.6-111 MBq/l (44.3-877.2 μg/l) (C0), with adsorption capacities (W) of 4.2-79.4 MBq/g biomass (dry weight) (33.2-627.5 μg/g). The biosorption equilibrium was achieved within 1 h and the optimum pH ranged from 1 to 3. No significant differences in 241Am biosorption were observed at 10-45 deg. C, or in solutions containing Au3+ or Ag+, even 2000 times above 241Am concentration. The relationship between concentrations and adsorption capacities of 241Am indicated that the 241Am biosorption by R. arrihizus obeys the Freundlich adsorption equation

  3. 49 CFR 234.241 - Protection of insulated wire; splice in underground wire.

    Science.gov (United States)

    2010-10-01

    ... underground wire. 234.241 Section 234.241 Transportation Other Regulations Relating to Transportation... of insulated wire; splice in underground wire. Insulated wire shall be protected from mechanical injury. The insulation shall not be punctured for test purposes. A splice in underground wire shall...

  4. 241-SY-101 data acquisition and control system (DACS) operator interface upgrade operational test report

    Energy Technology Data Exchange (ETDEWEB)

    ERMI, A.M.

    1999-05-11

    This procedure provides instructions for readiness of the first portion of the upgraded 241-SY-101 Data Acquisition and Control System (DACS) computer system to provide proper control and monitoring of the mitigation mixer pump and instrumentation installed in the 241-SY-101 underground storage tank will be systematically evaluated by the performance of this procedure.

  5. 8 CFR 241.3 - Detention of aliens during removal period.

    Science.gov (United States)

    2010-01-01

    ... governed by the provisions of 8 CFR 236.3. ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Detention of aliens during removal period. 241.3 Section 241.3 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION...

  6. 8 CFR 241.21 - Stay of deportation of excluded alien.

    Science.gov (United States)

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Stay of deportation of excluded alien. 241.21 Section 241.21 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS APPREHENSION AND DETENTION OF ALIENS ORDERED REMOVED Deportation of Excluded Aliens (for Hearings...

  7. 8 CFR 241.9 - Notice to transportation line of alien's removal.

    Science.gov (United States)

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Notice to transportation line of alien's removal. 241.9 Section 241.9 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS APPREHENSION AND DETENTION OF ALIENS ORDERED REMOVED Post-hearing Detention and Removal §...

  8. 8 CFR 241.10 - Special care and attention of removable aliens.

    Science.gov (United States)

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Special care and attention of removable aliens. 241.10 Section 241.10 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS APPREHENSION AND DETENTION OF ALIENS ORDERED REMOVED Post-hearing Detention and Removal §...

  9. Removal of floating organic in Hanford Waste Tank 241-C-103 restart plan

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, T.R.; Hanson, C.

    1994-10-03

    The decision whether or not to remove the organic layer from Waste Tank 241-C-103 was deferred until May, 1995. The following restart plan was prepared for removal of the organic if the decision is to remove the organic from the waste tank 241-C-103.

  10. Airborne plutonium-239 and americium-241 concentrations measured from the 125-meter Hanford Meteorological Tower

    International Nuclear Information System (INIS)

    Airborne plutonium-239 and americium-241 concentrations and fluxes were measured at six heights from 1.9 to 122 m on the Hanford meteorological tower. The data show that plutonium-239 was transported on nonrespirable and small particles at all heights. Airborne americium-241 concentrations on small particles were maximum at the 91 m height

  11. 36 CFR 223.241 - Disposal of seized special forest products.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Disposal of seized special forest products. 223.241 Section 223.241 Parks, Forests, and Public Property FOREST SERVICE, DEPARTMENT OF AGRICULTURE SALE AND DISPOSAL OF NATIONAL FOREST SYSTEM TIMBER Special Forest Products Award...

  12. Removal of floating organic in Hanford Waste Tank 241-C-103 restart plan

    International Nuclear Information System (INIS)

    The decision whether or not to remove the organic layer from Waste Tank 241-C-103 was deferred until May, 1995. The following restart plan was prepared for removal of the organic if the decision is to remove the organic from the waste tank 241-C-103

  13. Structurally novel steroidal spirooxindole by241 potently inhibits tumor growth mainly through ROS-mediated mechanisms.

    Science.gov (United States)

    Shi, Xiao-Jing; Yu, Bin; Wang, Jun-Wei; Qi, Ping-Ping; Tang, Kai; Huang, Xin; Liu, Hong-Min

    2016-01-01

    Cancer cells always have increased ROS levels, thus making them more vulnerable to persistent endogenous oxidative stress. The biochemical difference between cancer and normal cells could be exploited to achieve selective cancer cell killing by exogenous ROS-producing agents. Herein we described a structurally novel steroidal spirooxindole by241 and its anticancer efficacy. By241 exhibited potent inhibition against human cancer cells and less toxic to normal cells. By241 concentration-dependently induced apoptosis of MGC-803 and EC9706 cells, accompanied with the mitochondrial dysfunction and increased ROS levels. NAC can completely restore the decreased cell viability of MGC-803 cells caused by by241, suggesting ROS-mediated mechanisms. The expression levels of proteins involved in the mitochondrion-related pathways were detected, showing increased expression of proapoptotic proteins and decreased expression of anti-apoptotic proteins, and activation of caspases-9/-3, but without activating caspase-8 expression. Pretreatment with Z-VAD-FMK partially rescued by241-induced apoptosis of MGC-803 cells. Additionally, by241 inhibited mTOR, activated p53 and its downstream proteins, cleaved MDM2 and PI3K/AKT as well as NF-κB signaling pathway. In vivo experiments showed that by241 did not have significant acute oral toxicity and exerted good anticancer efficacy against MGC-803 bearing mice models. Therefore, by241 may serve as a lead for further development for cancer therapy. PMID:27527552

  14. Safety evaluation for the interim stabilization of Tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Geschke, G.R.

    1995-03-01

    This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed.

  15. 27 CFR 19.241 - Operations bond-distilled spirits plant and adjacent bonded wine cellar.

    Science.gov (United States)

    2010-04-01

    ... wine cellar. (a) General. A wine cellar under the provisions of 27 CFR part 24 shall be treated as... spirits plant and adjacent bonded wine cellar. 19.241 Section 19.241 Alcohol, Tobacco Products and... subpart G for the production of distilled spirits; and (2) Such wine cellar and distilled spirits...

  16. 40 CFR 51.241 - Nonattainment areas for carbon monoxide and ozone.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 2 2010-07-01 2010-07-01 false Nonattainment areas for carbon monoxide and ozone. 51.241 Section 51.241 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS REQUIREMENTS FOR PREPARATION, ADOPTION, AND SUBMITTAL OF IMPLEMENTATION PLANS Intergovernmental Consultation Agency Designation...

  17. 20 CFR 404.241 - 1977 simplified old-start method.

    Science.gov (United States)

    2010-04-01

    ... Section 404.241 Employees' Benefits SOCIAL SECURITY ADMINISTRATION FEDERAL OLD-AGE, SURVIVORS AND DISABILITY INSURANCE (1950- ) Computing Primary Insurance Amounts Old-Start Method of Computing Primary Insurance Amounts § 404.241 1977 simplified old-start method. (a) Who is qualified. To qualify for the...

  18. Analysis Method of 241Pu Radioactivity by Isotope Dilution-Extraction Liquid Scintillation Spectrometer

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>241Pu is the only pure β emitter with the maximum energy of 20.81 keV in plutonium isotopes of 238Pu, 239Pu, 240Pu and 242Pu, in which 241Pu is mostly specific radioactivity because its half-life is 14.29 a.

  19. Tank characterization report for single-shell tank 241-T-110

    International Nuclear Information System (INIS)

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-110. This report supports the requirements of the Tri-Party Agreement Milestone M-44-15B. Tank 241-T-110 is listed on the Hydrogen Watch List

  20. Hanford Single-Shell Tank Leak Causes and Locations - 241-B Farm

    Energy Technology Data Exchange (ETDEWEB)

    Girardot, Crystal L. [Washington River Protection Systems, Richland, WA (United States); Harlow, Donald G. [Washington River Protection Systems, Richland, WA (United States)

    2013-07-11

    This document identifies 241-B Tank Farm (B Farm) leak cause and locations for the 100 series leaking tank (241-B-107) identified in RPP-RPT-49089, Hanford B-Farm Leak Inventory Assessments Report. This document satisfies the B Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

  1. Hanford Tanks 241-C-202 and 241-C-203 Residual Waste Contaminant Release Models and Supporting Data

    Energy Technology Data Exchange (ETDEWEB)

    Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Mattigod, Shas V.; Schaef, Herbert T.; Arey, Bruce W.

    2007-09-13

    As directed by Congress, the U. S. Department of Energy (DOE) established the Office of River Protection in 1998 to manage DOE's largest, most complex environmental cleanup project – retrieval of radioactive waste from Hanford tanks for treatment and eventual disposal. Sixty percent by volume of the nation's high-level radioactive waste is stored at Hanford in aging deteriorating tanks. If not cleaned up, this waste is a threat to the Columbia River and the Pacific Northwest. CH2M Hill Hanford Group, Inc., is the Office of River Protection's prime contractor responsible for the storage, retrieval, and disposal of Hanford's tank waste. As part of this effort, CH2M HILL Hanford Group, Inc. contracted with Pacific Northwest National Laboratory (PNNL) to develop release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for DOE.

  2. Hanford Tanks 241-C-203 and 241-C-204: Residual Waste Contaminant Release Model and Supporting Data

    International Nuclear Information System (INIS)

    This report describes the development of release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. Key results from this work are (1) future releases from the tanks of the primary contaminants of concern (99Tc and 238U) can be represented by relatively simple solubility relationships between infiltrating water and solid phases containing the contaminants; and (2) high percentages of technetium-99 in the sludges (20 wt% in C-203 and 75 wt% in C-204) are not readily water leachable, and, in fact, are very recalcitrant. This is similar to results found in related studies of sludges from Tank AY-102. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for the U.S. Department of Energy

  3. Hanford Tanks 241-C-202 and 241-C-203 Residual Waste Contaminant Release Models and Supporting Data

    International Nuclear Information System (INIS)

    As directed by Congress, the U. S. Department of Energy (DOE) established the Office of River Protection in 1998 to manage DOE's largest, most complex environmental cleanup project retrieval of radioactive waste from Hanford tanks for treatment and eventual disposal. Sixty percent by volume of the nation's high-level radioactive waste is stored at Hanford in aging deteriorating tanks. If not cleaned up, this waste is a threat to the Columbia River and the Pacific Northwest. CH2M Hill Hanford Group, Inc., is the Office of River Protection's prime contractor responsible for the storage, retrieval, and disposal of Hanford's tank waste. As part of this effort, CH2M HILL Hanford Group, Inc. contracted with Pacific Northwest National Laboratory PNNL to develop release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for DOE.

  4. Hanford Tanks 241-C-203 and 241 C 204: Residual Waste Contaminant Release Model and Supporting Data

    International Nuclear Information System (INIS)

    This report was revised in May 2007 to correct 90Sr values in Chapter 3. The changes were made on page 3.9, paragraph two and Table 3.10; page 3.16, last paragraph on the page; and Tables 3.21 and 3.31. The rest of the text remains unchanged from the original report issued in October 2004. This report describes the development of release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. Key results from this work are (1) future releases from the tanks of the primary contaminants of concern (99Tc and 238U) can be represented by relatively simple solubility relationships between infiltrating water and solid phases containing the contaminants; and (2) high percentages of technetium-99 in the sludges (20 wt% in C-203 and 75 wt% in C-204) are not readily water leachable, and, in fact, are very recalcitrant. This is similar to results found in related studies of sludges from Tank AY-102. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for the U.S. Department of Energy.

  5. Hanford Tanks 241-C-203 and 241 C 204: Residual Waste Contaminant Release Model and Supporting Data

    Energy Technology Data Exchange (ETDEWEB)

    Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

    2007-05-23

    This report was revised in May 2007 to correct 90Sr values in Chapter 3. The changes were made on page 3.9, paragraph two and Table 3.10; page 3.16, last paragraph on the page; and Tables 3.21 and 3.31. The rest of the text remains unchanged from the original report issued in October 2004. This report describes the development of release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. Key results from this work are (1) future releases from the tanks of the primary contaminants of concern (99Tc and 238U) can be represented by relatively simple solubility relationships between infiltrating water and solid phases containing the contaminants; and (2) high percentages of technetium-99 in the sludges (20 wt% in C-203 and 75 wt% in C-204) are not readily water leachable, and, in fact, are very recalcitrant. This is similar to results found in related studies of sludges from Tank AY-102. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for the U.S. Department of Energy.

  6. Distribution of 241Am in the human body as determined by external counting

    International Nuclear Information System (INIS)

    Methods for determining the distribution of 241Am within the body of a contaminated subject and their application to several cases under study at the Center for Human Radiobiology are described. In general, 241Am is found in the lungs even at long times after inhalation, and systemic 241Am is observed to deposit in the liver and to label the skeleton in a fairly uniform manner; similar findings have been reported in animal studies (L172). Further analysis of the skeletal distribution of 241Am indicates deposition on bone surfaces. In contrast, the distribution of injected 239Pu in an (abnormal) skeleton is rather non-uniform when compared to that of 241Am

  7. A Method for Specific Activity Measurement of 241Am Solution

    International Nuclear Information System (INIS)

    According to the principle of coincidence theory, the specific activity of 241Am solution was determined on 4πα+4πγ counting standard device by γ efficiency extrapolation, and the problems of constant correction coefficients of self-absorption and scattering in α ionization chamber method were solved. The method was based on the alteration of detection efficiency when the height of elevator was altered, and the activity was obtained by γ fitting extrapolation according to detection efficiency. The results of more than 20 alpha radioactive sources by this method in our work are accordant with those of 2πα ionization chamber, and their uncertainties are improved to 0.4%. (authors)

  8. Motivation for New Measurements on 241, 242, 243Am Isotopes

    International Nuclear Information System (INIS)

    The initial objective of this work was an updated review on the Am isotopes data since the next official release (3.1) of the JEFF3 evaluated data file is foreseen around June 2005. Alternatively, this work searches for the possible reasons of the observed discrepancies between differential and integral measurement results. In particular, strong differences are encountered on σγth values and epithermal branching ratio values for the 241Am. Although the JEF2.2 validation is used as guide in parallel with a systematic study of all differential and integral results available, the need for new measurements clearly shows up. This paper finally draws up a list of desired and feasible new differential and integral measurements on the Am isotopes

  9. Toxicologic evaluation of analytes from Tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Mahlum, D.D.; Young, J.Y.; Weller, R.E.

    1994-11-01

    Westinghouse Hanford Company requested PNL to assemble a toxicology review panel (TRP) to evaluate analytical data compiled by WHC, and provide advice concerning potential health effects associated with exposure to tank-vapor constituents. The team`s objectives would be to (1) review procedures used for sampling vapors from tanks, (2) identify constituents in tank-vapor samples that could be related to symptoms reported by workers, (3) evaluate the toxicological implications of those constituents by comparison to establish toxicological databases, (4) provide advice for additional analytical efforts, and (5) support other activities as requested by WHC. The TRP represents a wide range of expertise, including toxicology, industrial hygiene, and occupational medicine. The TRP prepared a list of target analytes that chemists at the Oregon Graduate Institute/Sandia (OGI), Oak Ridge National Laboratory (ORNL), and PNL used to establish validated methods for quantitative analysis of head-space vapors from Tank 241-C-103. this list was used by the analytical laboratories to develop appropriate analytical methods for samples from Tank 241-C-103. Target compounds on the list included acetone, acetonitrile, ammonia, benzene, 1, 3-butadiene, butanal, n-butanol, hexane, 2-hexanone, methylene chloride, nitric oxide, nitrogen dioxide, nitrous oxide, dodecane, tridecane, propane nitrile, sulfur oxide, tributyl phosphate, and vinylidene chloride. The TRP considered constituent concentrations, current exposure limits, reliability of data relative to toxicity, consistency of the analytical data, and whether the material was carcinogenic or teratogenic. A final consideration in the analyte selection process was to include representative chemicals for each class of compounds found.

  10. Toxicologic evaluation of analytes from Tank 241-C-103

    International Nuclear Information System (INIS)

    Westinghouse Hanford Company requested PNL to assemble a toxicology review panel (TRP) to evaluate analytical data compiled by WHC, and provide advice concerning potential health effects associated with exposure to tank-vapor constituents. The team's objectives would be to (1) review procedures used for sampling vapors from tanks, (2) identify constituents in tank-vapor samples that could be related to symptoms reported by workers, (3) evaluate the toxicological implications of those constituents by comparison to establish toxicological databases, (4) provide advice for additional analytical efforts, and (5) support other activities as requested by WHC. The TRP represents a wide range of expertise, including toxicology, industrial hygiene, and occupational medicine. The TRP prepared a list of target analytes that chemists at the Oregon Graduate Institute/Sandia (OGI), Oak Ridge National Laboratory (ORNL), and PNL used to establish validated methods for quantitative analysis of head-space vapors from Tank 241-C-103. this list was used by the analytical laboratories to develop appropriate analytical methods for samples from Tank 241-C-103. Target compounds on the list included acetone, acetonitrile, ammonia, benzene, 1, 3-butadiene, butanal, n-butanol, hexane, 2-hexanone, methylene chloride, nitric oxide, nitrogen dioxide, nitrous oxide, dodecane, tridecane, propane nitrile, sulfur oxide, tributyl phosphate, and vinylidene chloride. The TRP considered constituent concentrations, current exposure limits, reliability of data relative to toxicity, consistency of the analytical data, and whether the material was carcinogenic or teratogenic. A final consideration in the analyte selection process was to include representative chemicals for each class of compounds found

  11. 10 CFR 31.8 - Americium-241 and radium-226 in the form of calibration or reference sources.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Americium-241 and radium-226 in the form of calibration or... BYPRODUCT MATERIAL § 31.8 Americium-241 and radium-226 in the form of calibration or reference sources. (a..., americium-241 or radium-226 in the form of calibration or reference sources: (1) Any person in a...

  12. Characterization of Direct-Push Vadose Zone Sediments from the 241-B and 241-BX Tank Farms

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Christopher F.; Icenhower, Jonathan P.; Um, Wooyong; Bjornstad, Bruce N.; Valenta, Michelle M.; Iovin, Cristian; Lanigan, David C.; Clayton, Ray E.; Geiszler, Keith N.; Clayton, Eric T.; Kutnyakov, Igor V.; Baum, Steven R.; Lindberg, Michael J.; Orr, Robert D.

    2007-12-21

    Geochemical tests provide evidence for the transit of a plume of caustic waste solution through the sediment column at the Hanford 241-B and -BX Tank Farms. Direct-push samples recovered from boreholes surrounding Tanks 241-B-110 and 241-BX-102 and related waste transfer lines and diversion boxes included sediments typical of those previously recovered from other localities on the Hanford Site. The Hanford formation sediments are dominantly quartzo-feldspathic sands strewn with lithic fragments, displaying a range of particle size distributions and sorting characteristics. Some moderately well-sorted, fine-grained lithologies are interpreted as lenticular bodies irregularly dispersed in coarser-grained, more poorly sorted sediments. Tier I tests conducted on the vadose zone sediments revealed an inverse correlation between moisture content and sediment size fraction (i.e., there is greater moisture content in finer-grained sediments). The Tier I tests also showed that the pore water solutions were likely sodium-rich, moderately saline, and possessed higher pH values than background (untainted) sediments. These data are characteristic of sediments that have encountered sodium-rich, saline, caustic waste solution, as documented in other reports at other suspect contamination sites around Hanford. Analyses of solutions from 1:1 water extracts reveal relatively balanced cation and anion concentrations, indicating that most of the geochemical species have been accounted for. The water extract data for affected sediments also indicate unusually high concentrations of aluminum, iron, and phosphorus. The relatively high concentrations of aluminum and iron may be the result of dissolution of secondary amorphous phases that precipitated after a reactive plume partially dissolved aluminum- and iron-bearing phases as it migrated through the sediment column. On the other hand, the presence of elevated concentrations of phosphorous may be the tell-tale signature of wastes

  13. Results of Waste Transfer and Back-Dilution in Tanks 241-SY-101 and 241-SY-102

    International Nuclear Information System (INIS)

    This report chronicles the process of remediation of the flammable gas hazard in Tank 241-SY-101 (SY-101) by waste transfer and back-dilution from December 18, 1999 through April 2, 2000. A brief history is given of the development of the flammable gas retention and release hazard in this tank, and the transfer and dilution systems are outlined. A detailed narrative of each of the three transfer and dilution campaigns is given to provide structure for the balance of the report. Details of the behavior of specific data are then described, including the effect of transfer and dilution on the waste levels in Tanks SY-101 and SY-102, data from strain gauges on equipment suspended from the tank dome, changes in waste configuration as inferred from neutron and gamma logs, headspace gas concentrations, waste temperatures, and the mixerpump operating performance. Operating data and performance of the transfer pump in SY-101 are also discussed

  14. Biosorption of radionuclide Americium-241 by A. niger spore and hyphae

    International Nuclear Information System (INIS)

    The biosorption of radionuclide 241Am from solution was studied by a. niger spore and hyphae, and the effects of the operational conditions on the treatment were investigated. The results showed the treatment by A. niger spore and hyphae were very efficient. An average of 96% of the total 241Am was removed from 241Am solutions of 5.6-111 MBq/L (C0), with adsorption capacities (W) of 7.2-142.4 MBq/g biomass, 5.2-106.5 MBq/g, respectively. The biosorption equilibrium was achieved within 1 h and the optimum pH value ranged 3-0.1 mol/L HNO3 and 3-2 for spore and hyphae of A. niger, respectively. No significant effects on 241Am biosorption were observed at 15 degree C-45 degree C, or challenged with containing Au3+ or Ag+, even 2000 times above 241Am amount. the index relationship between concentrations and adsorption capacities of 241Am indicated that the 241Am biosorption by A. niger spore and hyphae obey to Freundlich adsorption equation. The adsorption behavior of A. niger spore and hyphae were basically coincident

  15. Tank 241-T-201, core 192 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Nuzum, J.L.

    1997-08-07

    This document is the final laboratory report for Tank 241-T-201. Push mode core segments were removed from Riser 3 between April 24, 1997, and April 25, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-T-201 Push Mode Core Sampling and Analysis Plan (TSAP) (Hu, 1997), Letter of Instruction for Core Sample Analysis of Tanks 241-T-201, 241-T-202, 241-T-203, and 241-T-204 (LOI) (Bell, 1997), Additional Core Composite Sample from Drainable Liquid Samples for Tank 241-T-2 01 (ACC) (Hall, 1997), and Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DSC) analyses exceeded the notification limits stated in DQO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group, and are not considered in this report.

  16. Americium-241 and plutonium-237 turnover in mussels ( Mytilus galloprovincialis) living in field enclosures

    Science.gov (United States)

    Guary, J. C.; Fowler, S. W.

    1981-02-01

    Loss of 241Am and 237Pu from contaminated mussels ( Mytilus galloprovincialis) living in situ in the Mediterranean Sea is described as the sum of three exponential functions. In the case of 241Am, two short-lived compartments representing a total of 80% of the incorporated radionuclide turned over rapidly with biological half-lives of 2 and 3 weeks. The remaining fraction of 241Am, associated with a long-lived compartment, was lost at an extremely slow rate ( Tb1/2=1·3 years). Plutonium-237 turnover in the two short-lived compartments (containing 70% of the Pu) was more rapid ( Tb1/2=1-2 days and 2 weeks) than that of 241Am; however, there was some indication that subsequent loss rates of the two radionuclides in long-lived compartments may be similar if determined over comparable periods of time. Loss rates of 241Am differed for the various tissues, with the most rapid rates occurring in gill, viscera and shell. Abrupt changes in loss observed in muscle and mantle suggested a translocation of 241Am to muscle and mantle during depuration. Whole shell contained by far the largest fraction (˜90%) of both 241Am and 237Pu taken up; in addition, these radionuclides are not irreversibly bound to mussel shell but readily leach into the water. These observations suggest that mollusc shell may influence the biogeochemistry of transuranic elements in littoral zones.

  17. Operational test report for the 241-A-701 air compressor upgrade

    International Nuclear Information System (INIS)

    A description and safety class designation of the accumulator and 701-A compressor system is contained in VTHC-SD-at sign-DA-137, Safety Classification (of the 241-A-70) Compressed Air System and shown on drawings H-2-62895, Sheet 2 and H-14-20308, Sheet 3. The design basis for the 241-A-702 Ventilation System Accumulator is contained in at sign-C-SD-at sign-DB-016, 241-A-702 Ventilation System Accumulator Design Basis

  18. Strontium-Transuranic Precipitation and Crossflow Filtration of 241-AN-102 Large C

    Energy Technology Data Exchange (ETDEWEB)

    Nash, C.A.

    2001-05-21

    This work provides an important confirmation of the new strontium/permanganate precipitation process to achieve both acceptable filterability and decontamination for Envelope C (Tanks 241-AN-102 and 241-AN-107) wastes to be treated by the Hanford River Protection Project. As a bench-scale demonstration, a series of seven precipitation batches and crossflow filtration campaigns were performed to remove strontium-90 and transuranics from 16.5 liters of Tank 241-AN-102 ''Large C'' supernatant liquid containing entrained solids.

  19. Tank 241-C-106 waste retrieval sluicing system process control plan

    Energy Technology Data Exchange (ETDEWEB)

    Carothers, K.G.

    1998-07-25

    Project W-320 has installed the Waste Retrieval Sluicing System at the 200 East Area on the Hanford Site to retrieve the sludge from single-shell tank 241-C-106 and transfer it into double-shell tank 241-AY-102. Operation of the WRSS process will resolve the high-heat safety issue for tank 241-C-106 and demonstrate a technology for the retrieval of single-shell tank wastes. This process control plan coordinates the technical operating requirements (primarily mass transfer, temperature, and flammable gas) for the sluicing operation and provides overall technical guidance for the retrieval activity.

  20. Tank 241-C-106 waste retrieval sluicing system process control plan

    International Nuclear Information System (INIS)

    Project W-320 has installed the Waste Retrieval Sluicing System at the 200 East Area on the Hanford Site to retrieve the sludge from single-shell tank 241-C-106 and transfer it into double-shell tank 241-AY-102. Operation of the WRSS process will resolve the high-heat safety issue for tank 241-C-106 and demonstrate a technology for the retrieval of single-shell tank wastes. This process control plan coordinates the technical operating requirements (primarily mass transfer, temperature, and flammable gas) for the sluicing operation and provides overall technical guidance for the retrieval activity

  1. 241-AP Tank Farm Construction Extent of Condition Review for Tank Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, Travis J.; Gunter, Jason R.; Reeploeg, Gretchen E.

    2014-04-04

    This report provides the results of an extent of condition construction history review for the 241-AP tank farm. The construction history of the 241-AP tank farm has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In the 241-AP tank farm, the sixth double-shell tank farm constructed, tank bottom flatness, refractory material quality, post-weld stress relieving, and primary tank bottom weld rejection were improved.

  2. Tank 241-Z-361 vapor sampling and analysis plan

    Energy Technology Data Exchange (ETDEWEB)

    BANNING, D.L.

    1999-02-23

    Tank 241-Z-361 is identified in the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement), Appendix C, (Ecology et al. 1994) as a unit to be remediated under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). As such, the U.S. Environmental Protection Agency will serve as the lead regulatory agency for remediation of this tank under the CERCLA process. At the time this unit was identified as a CERCLA site under the Tri-Party Agreement, it was placed within the 200-ZP-2 Operable Unit. In 1997, The Tri-parties redefined 200 Area Operable Units into waste groupings (Waste Site Grouping for 200 Areas Soils Investigations [DOE-RL 1992 and 1997]). A waste group contains waste sites that share similarities in geological conditions, function, and types of waste received. Tank 241-Z-361 is identified within the CERCLA Plutonium/Organic-rich Process Condensate/Process Waste Group (DOE-RL 1992). The Plutonium/Organic-rich Process Condensate/Process Waste Group has been prioritized for remediation beginning in the year 2004. Results of Tank 216-Z-361 sampling and analysis described in this Sampling and Analysis Plan (SAP) and in the SAP for sludge sampling (to be developed) will determine whether expedited response actions are required before 2004 because of the hazards associated with tank contents. Should data conclude that remediation of this tank should occur earlier than is planned for the other sites in the waste group, it is likely that removal alternatives will be analyzed in a separate Engineering Evaluation/Cost Analysis (EE/CA). Removal actions would proceed after the U.S. Environmental Protection Agency (EPA) signs an Action Memorandum describing the selected removal alternative for Tank 216-Z-361. If the data conclude that there is no immediate threat to human health and the environment from this tank, remedial actions for the tank will be defined in a

  3. Spatial distribution of (241)Am, (137)Cs, (238)Pu, (239,240)Pu and (241)Pu over 17 year periods in the Ravenglass saltmarsh, Cumbria, UK.

    Science.gov (United States)

    Oh, J-S; Warwick, P E; Croudace, I W

    2009-01-01

    Ninety five surface scrape samples were collected at the Ravenglass saltmarsh and analysed for radionuclides by alpha spectrometry ((238)Pu and (239,240)Pu), gamma spectrometry ((241)Am and (137)Cs) and liquid scintillation counting ((241)Pu). Both (241)Am and (137)Cs activities are compared with those reported by Horrill [1983. Concentrations and spatial distribution of radioactivity in an ungrazed saltmarsh. In: Coughtrey, P.J. (Ed.), Ecological Aspects of Radionuclide Release. British Ecological Society Special Publication No. 3. Blackwell, Oxford, pp. 119-215.] Significant decreases in activities for both radionuclides were observed which is caused by the declining levels of discharges from the Sellafield nuclear reprocessing plant since the 1980s. It has been concluded that the spatial distribution of these radionuclides are controlled by the tidal currents and the clay contents in the sediments. There is evidence of surface erosion of the saltmarsh and redistribution of radionuclides in the saltmarsh using isotopic ratios of measured Pu.

  4. Radioactive air emissions notice of construction for installation and operation of a waste retrieval system and tanks 241-AP-102 and 241-AP-104 project

    Energy Technology Data Exchange (ETDEWEB)

    DEXTER, M.L.

    1999-11-15

    This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246 247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61 07 for the installation and operation of one waste retrieval system in the 24 1 AP-102 Tank and one waste retrieval system in the 241 AP 104 Tank Pursuant to 40 CFR 61 09 (a)( 1) this application is also intended to provide anticipated initial start up notification Its is requested that EPA approval of this application will also constitute EPA acceptance of the initial start up notification Project W 211 Initial Tank Retrieval Systems (ITRS) is scoped to install a waste retrieval system in the following double-shell tanks 241-AP 102-AP 104 AN 102, AN 103, AN-104, AN 105, AY 102 AZ 102 and SY-102 between now and the year 2011. Because of the extended installation schedules and unknowns about specific activities/designs at each tank, it was decided to submit NOCs as that information became available This NOC covers the installation and operation of a waste retrieval system in tanks 241 AP-102 and 241 AP 104 Generally this includes removal of existing equipment installation of new equipment and construction of new ancillary equipment and buildings Tanks 241 AP 102 and 241 AP 104 will provide waste feed for immobilization into a low activity waste (LAW) product (i.e. glass logs) The total effective dose equivalent (TEDE) to the offsite maximally exposed individual (MEI) from the construction activities is 0 045 millirem per year The unabated TEDE to the offsite ME1 from operation of the mixer pumps is 0 042 millirem per year.

  5. Radioactive air emissions notice of construction for installation and operation of a waste retrieval system and tanks 241-AP-102 and 241-AP-104 project

    International Nuclear Information System (INIS)

    This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246 247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61 07 for the installation and operation of one waste retrieval system in the 24 1 AP-102 Tank and one waste retrieval system in the 241 AP 104 Tank Pursuant to 40 CFR 61 09 (a)( 1) this application is also intended to provide anticipated initial start up notification Its is requested that EPA approval of this application will also constitute EPA acceptance of the initial start up notification Project W 211 Initial Tank Retrieval Systems (ITRS) is scoped to install a waste retrieval system in the following double-shell tanks 241-AP 102-AP 104 AN 102, AN 103, AN-104, AN 105, AY 102 AZ 102 and SY-102 between now and the year 2011. Because of the extended installation schedules and unknowns about specific activities/designs at each tank, it was decided to submit NOCs as that information became available This NOC covers the installation and operation of a waste retrieval system in tanks 241 AP-102 and 241 AP 104 Generally this includes removal of existing equipment installation of new equipment and construction of new ancillary equipment and buildings Tanks 241 AP 102 and 241 AP 104 will provide waste feed for immobilization into a low activity waste (LAW) product (i.e. glass logs) The total effective dose equivalent (TEDE) to the offsite maximally exposed individual (MEI) from the construction activities is 0 045 millirem per year The unabated TEDE to the offsite ME1 from operation of the mixer pumps is 0 042 millirem per year

  6. Tank characterization report for single-shell tank 241-B-201

    Energy Technology Data Exchange (ETDEWEB)

    Conner, J.M., Fluor Daniel Hanford

    1997-02-03

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-201. This report supports the requirements of the Ri- Party Agreement Milestone M-44-05.

  7. Operability Test Report for 241-T compressed air system and heat pump

    International Nuclear Information System (INIS)

    This Operability Test Report (OTR) documents the results of functional testing performed on the operating parameters of the 241-T-701 Compressed Air System. The System was successfully installed and tested per work package 2W-92-01172

  8. Tank characterization report for single-shell tank 241-T-104

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, L.M., Fluor Daniel Hanford

    1997-02-04

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-104. This report supports the requirements of the Tri- Party Agreement Milestone M-44-05.

  9. Results of Retrieval Studies with Waste from Tank 241-C-104

    Energy Technology Data Exchange (ETDEWEB)

    O' ROURKE, J.F.

    2000-02-08

    Laboratory studies were performed on samples of waste from Tank 241-C-104. Physical property data was gathered to develop engineering plans for retrieval operations. Chemical composition data was collected to verify the ability to meet contract feed specifications.

  10. Design basis and requirements for 241-SY Modular Exhauster concrete pad and retaining wall

    International Nuclear Information System (INIS)

    The purpose of this document is to serve as the design and functional requirements for a concrete pad for the new 241-SY Modular Exhauster and for a retaining wall to be built near the new ventilation systems

  11. Tank characterization report for single-shell tank 241-B-107

    Energy Technology Data Exchange (ETDEWEB)

    Conner, J.M.

    1998-05-04

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-107. This report supports the requirements of the Tri-Party Agreement Milestone M-44-ISB.

  12. Tank characterization report for single-shell tank 241-S-106

    Energy Technology Data Exchange (ETDEWEB)

    Field, J.G.

    1998-04-20

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-S-106. This report supports the requirements of the Tri-Party Agreement Milestone M-44-ISB.

  13. Tank characterization report for single-shell tank 241-BY-106

    Energy Technology Data Exchange (ETDEWEB)

    Bell, K.E.

    1996-09-26

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241 BY-106. This report supports the requirements of the Tri Party Agreement Milestone M-44-09.

  14. Tank characterization report for single-shell tank 241-S-106

    International Nuclear Information System (INIS)

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-S-106. This report supports the requirements of the Tri-Party Agreement Milestone M-44-ISB

  15. Biosorption of 241Am by Saccharomyces cerevisiae. Preliminary investigation on mechanism

    International Nuclear Information System (INIS)

    As an important radioisotope in nuclear industry and other fields, 241Am is one of the most serious contamination concerns due to its high radiation toxicity and long half-life. The encouraging biosorption of 241Am from aqueous solutions by free or immobilized Saccharomyces cerevisiae (S. cerevisiae) has been observed in our previous experiments. In this study, the preliminary evaluation on mechanism was further explored via chemical or biological modification of S. cerevisiae, and using europium as a substitute for americium. The results indicated that the culture times of more than 16 hours for S. cerevisiae was suitable and the efficient adsorption of 241Am by the S. cerevisiae was able to achieve. The pH value in solutions decreased gradually with the uptake of 241Am in the S. cerevisiae, implying that H+ released from S. cerevisiae via ion-exchange. The biosorption of 241Am by the decomposed cell wall, protoplasm or cell membrane of S. cerevisiae was same efficient as by the intact fungus. However, the adsorption ratio for 241Am by the deproteinized or deacylated S. cerevisiae dropped obviously, implying that protein or carboxyl functional groups of S. cerevisiaece play an important role in the biosorption of 241Am. Most of the investigated acidic ions have no significant influence on the 241Am adsorption, while the saturated EDTA can strong inhibit the biosorption of 241Am on S. cerevisiae. When the concentrations of coexistent Eu3+, Nd3+ were 100 times more than that of 241Am, the adsorption ratios would decrease to 65% from more than 95%. It could be noted by transmission electron microscope (TEM) analysis that the adsorbed Eu is almost scattered in the whole fungus, while Rutherford backscattering spectrometry (RBS) analysis indicated that Ca in S. cerevisiae have been replaced by Eu via ion-exchange. All the results implied that the adsorption mechanism of 241Am on S. cerevisiae is very complicated and at least involved in ion exchange, complexation

  16. Miscellaneous component design for Tank 241SY101 pump removal

    International Nuclear Information System (INIS)

    A mixer pump has been used to mitigate the hydrogen build-up in tank 241SY101 (SY101), located in the 200 West Area of the Hanford Site. New equipment is being prepared for the removal, transport, storage, and disposal of the test pump. The disposal equipment for the test pump now in tank SY101 includes a shipping container, a strong back, a lifting beam, a test weight, container support stands, a modified mock-up pump, a flexible receiver blast shield, a lifting yoke, and a yoke brace. The structural evaluations of container and strong back are detailed in another supporting document (WHC 1994a), the engineering analyses of flexible receiver blast shield/lifting yoke and yoke brace are given in other supporting documents (WHC 1994b, WHC 1994c), respectively. Engineering tasks that were contracted to Advanced Engineering Consultants (AEC) include the design and analysis of the following. Two spreader-beam lifting devices. a Container test weight. Container support saddles. Mock-up pump modification. This report documents the work description, design basis, assumptions, and design calculations provided by AEC for the above components. All AEC documents appear in Appendix A. Additional work conducted by Westinghouse Hanford Company (WHC) on the modified container test weight, modification to the mock-up pump, the removable support for the transport assembly, and saddle modification for air pallets also are included in this document

  17. 241-SY-101 mixer pump lifetime expectancy. Final report

    International Nuclear Information System (INIS)

    The purpose of WHC-SD-WM-TI-726, Rev. 0 241-SY-101 Mixer Pump Lifetime Expectancy is to determine a best estimate of the mean lifetime of non-repairable (located in the waste) essential features of the hydrogen mitigation mixer pump presently installed in 101-SY. The estimated mean lifetime is 9.1 years. This report does not demonstrate operation of the entire pump assembly within the Tank Farm ''safety envelope''. It was recognized by the Defense Nuclear Facilities Safety Board (DNFSB) this test pump was not specifically designed for long term service in tank 101-SY. In June 95 the DNFSB visited Hanford and ask the question, ''how long will this test pump last and how will the essential features fail?'' During the 2 day meeting with the DNFSB it was discussed and defined within the meeting just exactly what essential features of the pump must operate. These essential features would allow the pump to operate for the purpose of extending the window for replacement. Operating with only essential features would definitely be outside the operating safety envelope and would require a waiver. There are three essential features: 1. The pump itself (i.e. the impeller and motor) must operate 2. Nozzles and discharges leg must remain unplugged 3. The pump can be re-aimed, new waste targeted, even if manually

  18. Tank 241-AY-102 Secondary Liner Corrosion Evaluation - 14191

    Energy Technology Data Exchange (ETDEWEB)

    Boomer, Kayle D. [Washington River Protection Solutions (United States); Washenfelder, Dennis J. [Washington River Protection Solutions (United States); Johnson, Jeremy M. [Department of Energy, Washington, DC (United States). Office of River Protection

    2014-01-07

    In October 2012, Washington River Protection Solutions, LLC (WRPS) determined that the primary tank of 241-AY-102 (AY-102) was leaking. A number of evaluations were performed after discovery of the leak which identified corrosion from storage of waste at the high waste temperatures as one of the major contributing factors in the failure of the tank. The propensity for corrosion of the waste on the annulus floor will be investigated to determine if it is corrosive and must be promptly removed or if it is benign and may remain in the annulus. The chemical composition of waste, the temperature and the character of the steel are important factors in assessing the propensity for corrosion. Unfortunately, the temperatures of the wastes in contact with the secondary steel liner are not known; they are estimated to range from 45 deg C to 60 deg C. It is also notable that most corrosion tests have been carried out with un-welded, stress-relieved steels, but the secondary liner in tank AY-102 was not stress-relieved. In addition, the cold weather fabrication and welding led to many problems, which required repeated softening of the metal to flatten secondary bottom during its construction. This flame treatment may have altered the microstructure of the steel.

  19. Operability Test Report for 241-U Compressed Air System and heat pump

    International Nuclear Information System (INIS)

    The 241-U-701 compressed air system supplies instrument quality compressed air to Tank Farm 241-U. The system was upgraded. The operability test showed that the system operates within its intended design parameters. System performance was monitored, recorded, and used to identify areas of concern. Exceptions to the OTP and additional items for safe system performance were minimal and have been resolved; the air system is ready for Operation's use

  20. Acceptance Test Report for the 241-AZ-101 Ultrasonic Interface Level Analyzer

    International Nuclear Information System (INIS)

    This document comprises the Acceptance Test Report for the 241-AZ-101 Ultrasonic Interface Level Analyzer. This document presents the results of Acceptance Testing of the 241-AZ-101 Ultrasonic Interface Level Analyzers (URSILLAs). Testing of the URSILLAs was performed in accordance with ATP-260-001, ''URSILLA Pre-installation Acceptance Test Procedure''. The objective of the testing was to verify that all equipment and components function in accordance with design specifications and original equipment manufacturer's specifications

  1. Final results of double-shell tank 241-AN-105 ultrasonic inspection

    Energy Technology Data Exchange (ETDEWEB)

    JENSEN, C.E.

    1999-08-23

    This document presents the results and documentation of the nondestructive ultrasonic examination of tank 241-AN-105. A tank inspection supplier was retained to provide and use an ultrasonic examination system (equipment, procedures, and inspectors) to scan a limited area of double-shell tank 241-AN-105 primary tank wall primary knuckle, and secondary tank bottom. The inspection found some indication of general and local wall thinning with no cracks detected.

  2. Study of safety performance of the 241Am fire alarm source

    Institute of Scientific and Technical Information of China (English)

    2000-01-01

    The safety performance of 241Am fire alarm sources made by using powder metallurgical technology has been preliminarily studied, so as to determine an allowable maximum energy limit value of the alpha particles outgoing from this kind of sources in light of radiation safety and the present technology. The yielded results show that 241Am leak has not been found when the peak energy of the alpha energy spectrum of this kind of sources is less than 4.96 MeV.

  3. Closed out Tank 241-SY-101 DACS system change request {number_sign}1--100

    Energy Technology Data Exchange (ETDEWEB)

    Gauck, G.J.

    1995-03-07

    This report is a compilation of system change requests processed during the development of the Data Acquisition and Control System for the Tank 241-SY-101 hydrogen mitigation project. Tank 241-SY-101 is on the Hydrogen Watch List. The disposition of the request, date the change was installed, date verified, and whether an Acceptance Test Procedure was required and completed are described for each request change.

  4. System Description for Tank 241-AZ-101 Waste Retrieval Data Acquisition System

    Energy Technology Data Exchange (ETDEWEB)

    ROMERO, S.G.

    2000-02-14

    The proposed activity provides the description of the Data Acquisition System for Tank 241-AZ-101. This description is documented in HNF-5572, Tank 241-AZ-101 Waste Retrieval Data Acquisition System (DAS). This activity supports the planned mixer pump tests for Tank 241-AZ-101. Tank 241-AZ-101 has been selected for the first full-scale demonstration of a mixer pump system. The tank currently holds over 960,000 gallons of neutralized current acid waste, including approximately 12.7 inches of settling solids (sludge) at the bottom of the tank. As described in Addendum 4 of the FSAR (LMHC 2000a), two 300 HP mixer pumps with associated measurement and monitoring equipment have been installed in Tank 241-AZ-101. The purpose of the Tank 241-AZ-101 retrieval system Data Acquisition System (DAS) is to provide monitoring and data acquisition of key parameters in order to confirm the effectiveness of the mixer pumps utilized for suspending solids in the tank. The suspension of solids in Tank 241-AZ-101 is necessary for pretreatment of the neutralized current acid waste and eventual disposal as glass via the Hanford Waste Vitrification Plant. HNF-5572 provides a basic description of the Tank 241-AZ-101 retrieval system DAS, including the field instrumentation and application software. The DAS is provided to fulfill requirements for data collection and monitoring. This document is not an operations procedure or is it intended to describe the mixing operation. This USQ screening provides evaluation of HNF-5572 (Revision 1) including the changes as documented on ECN 654001. The changes include (1) add information on historical trending and data backup, (2) modify DAS I/O list in Appendix E to reflect actual conditions in the field, and (3) delete IP address in Appendix F per Lockheed Martin Services, Inc. request.

  5. ^241Am(n,γ) absolute cross sections measured with DANCE

    Science.gov (United States)

    Jandel, M.; Bredeweg, T. A.; Fowler, M. M.; Bond, E. M.; Chadwick, M. B.; Clement, R. R.; Couture, A.; O'Donnell, J. M.; Reifarth, R.; Rundberg, R. S.; Ullmann, J. L.; Vieira, D. J.; Wilhelmy, J. B.; Wouters, J. M.; Agvaanluvsan, U.; Macri, R. A.; Sheets, S. A.; Wu, C. Y.; Becker, J. A.

    2007-10-01

    ^241Am is present in plutonium due to the beta decay of ^241Pu (t1/2=14.38 years). As such ^241Am can be used as a detector for nuclear forensics. A precise measurement of ^241Am(n,γ) cross section is thus needed for this application. The measurement is also of interest for advanced reactor design as part of the Global Nuclear Energy Partnership (GNEP). The Detector for Advanced Neutron Capture Experiments (DANCE) at Los Alamos National Laboratory (LANL) was used for neutron capture cross section measurement on ^241Am. The high granularity of DANCE (160 BaF2 detectors in a 4π geometry) enables the efficient detection of prompt gamma-rays following a neutron capture. DANCE is located on the 20.26 m neutron flight path 14(FP14) at the Manuel Lujan Jr. Neutron Scattering Center at the Los Alamos Neutron Science Center (LANSCE). The absolute ^241Am(n,γ) cross sections were obtained in the range of neutron energies from 0.02 eV to 320 keV. The results will be compared to existing evaluations in detail.

  6. Tank 241-T-203, core 190 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1997-08-05

    This document is the analytical laboratory report for tank 241-T-203 push mode core segments collected on April 17, 1997 and April 18, 1997. The segments were subsainpled and analyzed in accordance with the Tank 241-T-203 Push Mode Core Sampling andanalysis Plan (TSAP) (Schreiber, 1997a), the Safety Screening Data Quality Objective (DQO)(Dukelow, et al., 1995) and Leffer oflnstructionfor Core Sample Analysis of Tanks 241-T-201, 241-T-202, 241-T-203, and 241-T-204 (LOI)(Hall, 1997). The analytical results are included in the data summary report (Table 1). None of the samples submitted for Differential Scanning Calorimetry (DSC), Total Alpha Activity (AT) and Total Organic Carbon (TOC) exceeded notification limits as stated in the TSAP (Schreiber, 1997a). The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems (TWRS) Technical Basis Group in accordance with the Memorandum of Understanding (Schreiber, 1997b) and not considered in this report.

  7. Recommended alternative for interim stabilization of Tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Dukelow, G.T.; Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Grigsby, J.M.

    1995-04-01

    The waste in tank 241-C-103 poses several health and safety risks and potential soil contamination caused by tank leaks. To minimize the risk of contaminating the soil beneath the tank, the pumpable waste liquids are planned to be removed by salt well pumping. In addition to aqueous liquids, this tank is unique because it also contains a layer of degraded PUREX solvent floating on the aqueous liquid. The following three options for removing and storing this separable phase organic solvent have been proposed and studied: transferring the organic solvent and pumpable aqueous liquids using existing salt well pumping equipment and procedures to a double-shell tank (DST) for storage; removing most of the organic solvent using a skimmer pump, then salt well pumping the remaining pumpable liquids to a different DST for storage; removing most of the organic solvent to an aboveground storage tank for eventual treatment or offsite transfer, and then salt well pumping the remaining pumpable liquids to a DST for interim storage. As a result of evaluating these three options and a no pumping option, the recommended action is to transfer both the organic solvent and pumpable aqueous liquid to a DST for storage using existing salt well pumping equipment. The evaluation considers the following criteria: public health and safety, worker safety, environmental compliance, engineering feasibility, and cost. The options compared these factors. Two key areas drove the selection of the recommended approach: the minimization of potential soil contamination from tank leaks caused the (interim stabilization by salt well pumping) options to be rated more highly than the no pumping option; and cost and implementation factors caused the transfer and storage to DST using existing tank farm salt well pumping equipment option to rate higher than the skimming options. Other factors have only a second order effect on the selection process. Evaluation results are described in this report.

  8. 241-SY-101 air lance removal lessons learned

    International Nuclear Information System (INIS)

    An emergency task was undertaken to remove four air lances and one thermocouple (TC) tree from tank 241-SY-101 (SY-101). This resulted from video observation that these pipes were being severely bent during periodic gas release events that regularly occurred every three to four months. At the time, the gas release events were considered to be the number one safety issue within the US Department of Energy (DOE) complex. This emergency removal task was undertaken on an extremely short schedule that required all activities possible to be completed in parallel. This approach and extremely short schedule, while successful, resulted in some undesirable consequences from less than desired time for design, reviews, equipment testing, operations training, and bad weather conditions. These consequences included leakage of liquid waste from the containers to the ground, higher than expected dose rates at the container surface, difficult field operations, and unexpected pipe configuration during removal. In addition, changes to environmental regulations and severe winter weather impacted the packaging and shipping activities required the prepare the removed pipes for storage at the Central Waste Complex (CWC). The purpose of this document is to identify lessons to be learned for future activities. In context of the emergency conditions that existed at the time and the urgency to remove these pipes, their removal was successfully completed under extremely difficult conditions and schedule. The success of the task should not be overshadowed by the desire to identify areas needing improvement and lessons to be learned. Many of the lessons identified in this document have already resulted in improved conduct of operations and engineering

  9. Determination of the half-life and specific thermal power of 241Pu by nuclear calorimetry

    International Nuclear Information System (INIS)

    241Pu has the shortest half-life of the abundant plutonium isotopes present in reprocessed irradiated nuclear fuel with a value of approximately 14.3 years. It is important to know the half-life of 241Pu with a higher fractional accuracy than that of the other plutonium isotopes because the half-life of 241Pu and its associated uncertainty affects the estimation by decay calculation of both the total amount of separated plutonium in storage and the determination of the total plutonium mass by non-destructive assay. This paper addresses the determination of the 241Pu half-life using nuclear calorimetry by the measurement of the thermal power as 241Pu evolves in time from a sealed plutonium source, ideally initially rich in 241Pu and chemically stripped of 241Am. The absolute accuracy of nuclear calorimeters can be ensured over long periods of time (many years) using long-lived nuclear reference materials and/or traceable electrical heat standards. One can, therefore, expect nuclear calorimetry to offer an accurate way to determine the half-life of 241Pu, which is comparable in quality and independent, yet complementary, to other approaches. Temporal analysis of the power-versus-time data also yields an estimate of the specific power of 241Pu, which other methods do not. After describing the principle of the method and developing the pertinent mathematical expressions, we outline the approach by drawing on some unpublished notes of Kenneth C. Jordan who carried out such experiments at the Mound Laboratory over 40 years ago. Today, Jordan’s work remains possibly the most significant experiment of its type to the 241Pu nuclear data evaluator. However, objectively assigning confidence to his results is problematic because the details of the experiments and data reduction have never been adequately reported. This work goes some way to that end but, without the raw data and first-hand knowledge, cannot provide a complete record. We conclude that a new high

  10. Studies on the binding and transport processes of americium-241 hydroxide polymers in rat lung and bovine alveolar macrophages

    International Nuclear Information System (INIS)

    The binding of Am-241 hydroxide polymers to the cell components of rat lung was investigated using differential centrifugation, density gradient centrifugation with different media, gel chromatography, free flow electrophoresis and electron microscopic autoradiography with Pu-241. The bovine alveolar macrophage cultures were introduced as an in vitro test system for Am-241 uptake. Form the biochemical and electron microscopic studies it can be concluded that Am-241 is taken up by pulmonary macrophages, where its first storage site is probably the lysosome. Then the Am-241 seems to be solubilized in the lysosomes and to be bound to the cytosolic ferritin of macrophages. Am-241 might be released from the cells and crosses the alveolar membranes as bound to transferrin or as low molecular weight form. (orig.)

  11. Determination of 241Pu in nuclear waste slurries: a comparative study using LSC and ICP-MS.

    Science.gov (United States)

    Jäggi, M; Röllin, S; Alvarado, J A Corcho; Eikenberg, J

    2012-02-01

    (241)Pu was determined in slurry samples from a nuclear reactor decommissioning project at the Paul Scherrer Institute (Switzerland). To validate the results, the (241)Pu activities of five samples were determined by LSC (TriCarb and Quantulus) and ICP-MS, with each instrument at a different laboratory. In lack of certified reference materials for (241)Pu, the methods were further validated using the (241)Pu information values of two reference sediments (IAEA-300 and IAEA-384). Excellent agreement with the results was found between LSC and ICP-MS in the nuclear waste slurries and the reference sediments.

  12. Influence of organic fertilization on the sorption mechanisms of 241 Am in tropical soils

    International Nuclear Information System (INIS)

    In this work the mechanisms involved in the sorption of 241Am were investigated depending on the physicochemical properties of some Brazilian soils and on alterations promoted by organic amendment. This experimental study was conducted in a controlled area, where pots containing different kinds of soils (histisol, ferralsol and nitisol), with different organic amendment doses (without amendment; 2 kg m-2 and 4 kg m-2) were artificially contaminated by radioactive solution water, which contained 241Am. Migration studies, distribution (or partition) coefficient (KJ), bioavailability and organic matter were carried out in these soils, with ar without organic amendment. In order to evaluate the effective bioavailability of radionuclides, radish (Raphanus sativus L.) was cultivated in these pots, and later the concentration of 241Am in radish's roots was measured. The main results show that 241Am tends to be strongly attached to organic matter and that organic amendment in tropical soils minimizes the radionuclide studied desorption. Also, distribution (or partition) coefficient values for 241Am were generated and these values are smaller than those ones determined for soils from temperate zones. Physical and chemical fractioning of organic matter were carried out. (author)

  13. Chemical Characterization of an Envelope A Sample from Hanford Tank 241-AN-103

    International Nuclear Information System (INIS)

    A whole tank composite sample from Hanford waste tank 241-AN-103 was received at the Savannah River Technology Center (SRTC) and chemically characterized. Prior to characterization the sample was diluted to ∼5 M sodium concentration. The filtered supernatant liquid, the total dried solids of the diluted sample, and the washed insoluble solids obtained from filtration of the diluted sample were analyzed. A mass balance calculation of the three fractions of the sample analyzed indicate the analytical results appear relatively self-consistent for major components of the sample. However, some inconsistency was observed between results where more than one method of determination was employed and for species present in low concentrations. A direct comparison to previous analyses of material from tank 241-AN-103 was not possible due to unavailability of data for diluted samples of tank 241-AN-103 whole tank composites. However, the analytical data for other types of samples from 241-AN-103 we re mathematically diluted and compare reasonably with the current results. Although the segments of the core samples used to prepare the sample received at SRTC were combined in an attempt to produce a whole tank composite, determination of how well the results of the current analysis represent the actual composition of the Hanford waste tank 241-AN-103 remains problematic due to the small sample size and the large size of the non-homogenized waste tank

  14. Tank 241-AZ-101 Mixer Pump Test Vapor Sampling and Analysis Plan

    International Nuclear Information System (INIS)

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of mixer pumps in tank 241-AZ-101. The primary purpose of the mixer pump test (MPT) is to demonstrate that the two 300 horsepower mixer pumps installed in tank 241-AZ-101 can mobilize the settled sludge so that it can be retrieved for treatment and vitrification Sampling will be performed in accordance with Tank 241-AZ-101 Mixer Pump Test Data Quality Objective (Banning 1999) and Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis (Mulkey 1999). The sampling will verify if current air emission estimates used in the permit application are correct and provide information for future air permit applications

  15. Effect of alcohol on internally deposited Am-241 in the baboon: a pilot study

    International Nuclear Information System (INIS)

    The efficacy of ethyl alcohol in enhancing the excretion of Am-241 from the baboon has been tested. Alcohol enhances Am-241 excretion via the fecal route by a factor of about 2.5. However, there is a corresponding increase in fecal volume, and no significant change in the concentration of the nuclide in the feces. Other cathartics tested caused increased fecal volumes with no change in amount of activity excreted leading to a decreased concentration of the nuclide in the feces. Alcohol is not as effective as DTPA in removing Am-241 from the body. Preliminary results suggest that alcohol has little or no enhancement effect on the decorporation capability of DTPA

  16. Tank 241-AZ-101 Mixer Pump Test Vapor Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    TEMPLETON, A.M.

    2000-03-06

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples obtained during the operation of mixer pumps in tank 241-AZ-101. The primary purpose of the mixer pump test (MPT) is to demonstrate that the two 300 horsepower mixer pumps installed in tank 241-AZ-101 can mobilize the settled sludge so that it can be retrieved for treatment and vitrification. Sampling will be performed in accordance with Tank 241-AZ-101 Mixer Pump Test Data Quality Objective (Banning 1999) and Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis (Mulkey 1999). The sampling will verify if current air emission estimates used in the permit application are correct and provide information for future air permit applications.

  17. Engineering evaluation of alternatives: Managing the assumed leak from single-shell Tank 241-T-101

    International Nuclear Information System (INIS)

    At mid-year 1992, the liquid level gage for Tank 241-T-101 indicated that 6,000 to 9,000 gal had leaked. Because of the liquid level anomaly, Tank 241-T-101 was declared an assumed leaker on October 4, 1992. SSTs liquid level gages have been historically unreliable. False readings can occur because of instrument failures, floating salt cake, and salt encrustation. Gages frequently self-correct and tanks show no indication of leak. Tank levels cannot be visually inspected and verified because of high radiation fields. The gage in Tank 241-T-101 has largely corrected itself since the mid-year 1992 reading. Therefore, doubt exists that a leak has occurred, or that the magnitude of the leak poses any immediate environmental threat. While reluctance exists to use valuable DST space unnecessarily, there is a large safety and economic incentive to prevent or mitigate release of tank liquid waste into the surrounding environment. During the assessment of the significance of the Tank 241-T-101 liquid level gage readings, Washington State Department of Ecology determined that Westinghouse Hanford Company was not in compliance with regulatory requirements, and directed transfer of the Tank 241-T-101 liquid contents into a DST. Meanwhile, DOE directed WHC to examine reasonable alternatives/options for safe interim management of Tank 241-T-101 wastes before taking action. The five alternatives that could be used to manage waste from a leaking SST are: (1) No-Action, (2) In-Tank Stabilization, (3) External Tank Stabilization, (4) Liquid Retrieval, and (5) Total Retrieval. The findings of these examinations are reported in this study

  18. Fast Neutron Imaging Using 241Am-Be Neutron Source%241Am-Be中子源快中子成像研究

    Institute of Scientific and Technical Information of China (English)

    蒋诗平; 陈亮; 万里飚; 杜淮江; 范扬眉; 韩荣典

    2007-01-01

    中子成像是一种与X射线成像互补的无损探测技术.为探索同位素中子源用于发展可移动的无损检测系统,利用241Am-Be作为中子源,使用自制的中子发光转换屏和X射线胶片作为探测系统开展了快中子成像研究,并获得了较高质量的图像.研究结果表明,利用241Am-Be中子源发展小型探测系统是有潜力的.

  19. Systems engineering study: tank 241-C-103 organic skimming,storage, treatment and disposal options

    Energy Technology Data Exchange (ETDEWEB)

    Klem, M.J.

    1996-10-23

    This report evaluates alternatives for pumping, storing, treating and disposing of the separable phase organic layer in Hanford Site Tank 241-C-103. The report provides safety and technology based preferences and recommendations. Two major options and several varations of these options were identified. The major options were: 1) transfer both the organic and pumpable aqueous layers to a double-shell tank as part of interim stabilization using existing salt well pumping equipment or 2) skim the organic to an above ground before interim stabilization of Tank 241-C-103. Other options to remove the organic were considered but rejected following preliminary evaluation.

  20. Analysis of potential hazards associated with 241Am loaded resins from nitrate media

    Energy Technology Data Exchange (ETDEWEB)

    Schulte, Louis D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rubin, Jim [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fife, Keith William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ricketts, Thomas Edgar [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tappan, Bryce C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chavez, David E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-02-19

    LANL has been contacted to provide possible assistance in safe disposition of a number of 241Am-bearing materials associated with local industrial operations. Among the materials are ion exchange resins which have been in contact with 241Am and nitric acid, and which might have potential for exothermic reaction. The purpose of this paper is to analyze and define the resin forms and quantities to the extent possible from available data to allow better bounding of the potential reactivity hazard of the resin materials. An additional purpose is to recommend handling procedures to minimize the probability of an uncontrolled exothermic reaction.

  1. Uncertainty of the estimation of 241Am content of the human body

    International Nuclear Information System (INIS)

    The aim of the study was to make a realistic estimation of 241Am activity in the body of the people with old internal contamination. A whole-body counter equipped with HPGe and LEGe detectors was used as a major tool. Calibration was performed using phantoms of the human head, knee, arm and leg of different origin. Using it for the evaluation of 241Am in the body of an internally contaminated case, body activity was estimated to be 5.6 kBq and its uncertainty was in the range given by factor 1.5 ± 1. (author)

  2. Waste compatibility safety issues and final results for tank 241-T-110 push mode samples

    Energy Technology Data Exchange (ETDEWEB)

    Nuzum, J.L.

    1997-05-15

    This document is the final laboratory report for Tank 241-T-110. Push mode core segments were removed from risers 2 and 6 between January 29, 1997, and February 7, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-T-110 Push Mode Core Sampling and analysis Plan (TSAP) and Safety Screening Data Quality Objective (DQO). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DSC) analyses exceeded the notification limits stated in DQO.

  3. Engineering Task Plan for Tank 241-C-106 contingency chiller definitive design

    International Nuclear Information System (INIS)

    This document identifies the scope, cost, schedule and responsible organizations for completing a design of a contingency ventilation inlet air cooling system for Tank 241-C-106. The air cooling system, described in Rensink (1995), consists of a chiller, cooling coils, and supporting equipment that, when installed will be capable of assuring that the waste temperatures in Tank 241-C-106 are maintained within acceptable limits for safe storage. The effort described herein is scheduled for completion by May 31, 1995 to support Performance Based Incentive (PBI) Milestone SI-2x

  4. Engineering study of the criticality issues associated with Hanford tank 241-Z-361

    Energy Technology Data Exchange (ETDEWEB)

    Lipke, E.J.

    1997-12-22

    Tank 241-Z-361 is associated with the Plutonium Finishing Plant (PFP). Uncertainty about the contents of the tank have led to the declaration of an Unreviewed Safety Question (USQ) and the preparation of a Justification for Continued Operation (JCO) to address flammable gas and other authorization basis issued. A Criticality Safety Team was assembled to review old data, determine its validity, and reevaluate the tank. It was concluded that the tank has a sufficient margin of safety to allow opening, sampling, and other characterizing activities. The team concluded that a criticality in Tank 241-Z-361 was extremely unlikely.

  5. Waste compatibility safety issues and final results for tank 241-SY-102 grab samples

    International Nuclear Information System (INIS)

    Three grab samples (2SY-96-1, 2SY-96-2, and 2SY-96-3) were taken from Riser 1A of Tank 241-SY 102 on January 14, 1997, and received by 222-S Laboratory on January 14, 1997. These samples were analyzed in accordance with Compatibility Grab Sampling and Analysis Plan (TSAP) and Data Quality Objectives for Tank Farm Waste Compatibility Program (DQO) in support of the Waste Compatibility Program. No notifications were required based on sample results. Acetone analysis was not performed in accordance with Cancellation of Acetone Analysis for Tank 241-SY-102 Grab Samples

  6. Project W-314 specific test and evaluation plan for 241-AY-02A pump pit upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Hays, W.H.

    1998-05-19

    This Specific Test and Evaluation Plan (STEP) defines the test and evaluation activities encompassing the upgrade of the 241-AY-02A Pump Pit for the W-314 Project. The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AY-02A Pump Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system`s performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP).

  7. Waste compatibility safety issues and final results for tank 241-SY-102 grab samples

    Energy Technology Data Exchange (ETDEWEB)

    Nuzum, J.L.

    1997-08-14

    Three grab samples (2SY-96-1, 2SY-96-2, and 2SY-96-3) were taken from Riser 1A of Tank 241-SY 102 on January 14, 1997, and received by 222-S Laboratory on January 14, 1997. These samples were analyzed in accordance with Compatibility Grab Sampling and Analysis Plan (TSAP) and Data Quality Objectives for Tank Farm Waste Compatibility Program (DQO) in support of the Waste Compatibility Program. No notifications were required based on sample results. Acetone analysis was not performed in accordance with Cancellation of Acetone Analysis for Tank 241-SY-102 Grab Samples.

  8. Transport parameters of 241 Am from low and intermediate level radioactive waste in disposal surroundings

    International Nuclear Information System (INIS)

    A programme on the safety analysis linked to the geological disposal of radioactive wastes is under study at the Institute for Nuclear Research Pitesti. In relation to the migration of radionuclides in the terrestrial environment following a possible release from the repository, specific experimental studies have been developed in order to provide the necessary input data for the risk assessment models. The paper reports the results of studies performed with 241 Am. Laboratory experiments were conducted to determine the transport parameters of 241 Am in the geological formations of Saligny site - the potential near-surface repository for low and intermediate radioactive wastes in Romania. (authors)

  9. Operational experience in mitigating flammable gas releases from Hanford Site Tank 241-SY-101

    International Nuclear Information System (INIS)

    Flammable gases consisting of hydrogen, nitrous oxide, ammonia, and methane are periodically released from Hanford Site waste tank 241-SY-101 at concentrations above the flammable limit. A large mixer pump installed in the tank in 1993 has effectively mitigated this problem by continuously releasing small amounts of the flammable gases at the rate they are generated. Tank 241-SY-101 is also equipped with multiple high-sensitivity gas monitoring systems and level detection systems to measure the quantity of gas that is retained in and released from the waste

  10. Evolution of late blood damage from decreasing doses of 241Am following injection in the rat

    International Nuclear Information System (INIS)

    Rats were given intravenous or intramuscular injections of 241Am at decreasing doses ranging from 7.5 μCi to 0.075 μCi per kg of body weight. Blood examinations showed that higher doses exerted an irreversible destructive effect on all blood cells. As the administered doses decreased, the destructive effect of 241Am dropped and even became reversible for white cells. Proliferative disorders such as leukocytosis with myelemias, leukemias -chiefly acute or chronic granulocytic leukemias- were then demonstrated. Red cells only dropped but more and more slowly. At the lowest doses, life-span shortening was the most evident effect

  11. Engineering test plan for Tank 241-SY-101 in situ viscometer. Revision 1

    International Nuclear Information System (INIS)

    To obtain in situ measurements of the rheological properties within tank 241-SY-101, this document will implement the test strategy defined in PNLMIT-041994, Acquisition and Reduction of Data Obtained in Tank SY-101 with the Ball Rheometer. Instructions for all sequences are defined within the procedure. All safety requirements as defined in LA-UR-92-3196, A Safety Assessment for Proposed Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-101-SY have been implemented into this procedure

  12. Engineering test plan for Tank 241-SY-101 in situ viscometer

    International Nuclear Information System (INIS)

    To obtain in situ measurements of the rheological properties within tank 241-SY-101, this document will implement the test strategy defined in PNLMIT-041994, acquisition and Reduction of Data Obtained in Tank SY-101 with the Ball Rheometer. Instructions for all sequences are defined within the procedure. All safety requirements as defined in LA-UR-92-3196, A Safety Assessment for Proposed Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-101-SY have been implemented into this procedure

  13. Engineering study of the criticality issues associated with tank 241-Z-361

    International Nuclear Information System (INIS)

    Tank 241-Z-361 is associated with the Plutonium Finishing Plant (PFP). Uncertainty about the contents of the tank have led to the declaration of an Unreviewed Safety Question (USQ) and the preparation of a Justification for Continued Operation (JCO) to address flammable gas and other authorization basis issued. A Criticality Safety Team was assembled to review old data, determine its validity, and reevaluate the tank. It was concluded that the tank has a sufficient margin of safety to allow opening, sampling, and other characterizing activities. The team concluded that a criticality in Tank 241-Z-361 was extremely unlikely

  14. Tank 241-U-106, cores 147 and 148, analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1996-09-27

    This document is the final report deliverable for tank 241-U-106 push mode core segments collected between May 8, 1996 and May 10, 1996 and received by the 222-S Laboratory between May 14, 1996 and May 16, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-U-106 Push Mode Core Sampling and analysis Plan (TSAP), the Historical Model Evaluation Data Requirements (Historical DQO), Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO) and the Safety Screening Data Quality Objective (DQO). The analytical results are included in Table 1.

  15. Tank 241-BY-106 vapor sampling and analysis tank characterization report. Revision 1

    International Nuclear Information System (INIS)

    Tank 241-BY-106 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in open-quotes Program Plan for the Resolution of Tank Vapor Issues.close quotes Tank 241-BY-106 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  16. Tank 241-BY-107 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-BY-107 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in open-quotes Program Plan for the Resolution of Tank Vapor Issuesclose quotes. Tank 241-BY-107 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolutionclose quotes

  17. Tank 241-SY-102, January 2000 Compatibility Grab Samples Analytical Results for the Final Report

    International Nuclear Information System (INIS)

    This document is the format IV, final report for the tank 241-SY-102 (SY-102) grab samples taken in January 2000 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank SY-102 samples were performed as directed in Comparability Grab Sampling and Analysis Plan for Fiscal Year 2000 (Sasaki 1999). No notification limits were exceeded. Preliminary data on samples 2SY-99-5, -6, and -7 were reported in ''Format II Report on Tank 241-SY-102 Waste Compatibility Grab Samples Taken in January 2000'' (Lockrem 2000). The data presented here represent the final results

  18. Tank 241-BY-107 vapor sampling and analysis tank characterization report. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Huckaby, J.L.

    1995-05-31

    Tank 241-BY-107 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in {open_quotes}Program Plan for the Resolution of Tank Vapor Issues.{close_quotes} Tank 241-BY-107 was vapor sampled in accordance with {open_quotes}Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.{close_quotes}

  19. Tank 241-BY-107 vapor sampling and analysis tank characterization report

    Energy Technology Data Exchange (ETDEWEB)

    Huckaby, J.L.

    1995-05-05

    Tank 241-BY-107 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in {open_quotes}Program Plan for the Resolution of Tank Vapor Issues{close_quotes}. Tank 241-BY-107 was vapor sampled in accordance with {open_quotes}Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution{close_quotes}.

  20. A feasibility study for transportable 241Am-in-lung and 241Am-in-nose-blow monitoring systems for use following a weapons accident

    International Nuclear Information System (INIS)

    In a nuclear weapon accident involving fire or conventional explosion, most of the radiation dose received by people in the immediate vicinity would result from inhalation of 239Pu. This is accompanied by the nuclide 241Am, which is much easier to determine by external counting because of the 60 keV gamma ray emission. In the event of an accident, a priority would be to identify any people who have had intakes of 239Pu which were so large that decorporation therapy should be considered. Direct measurement of lung content provides the most rapid and convenient method for assessing intakes by inhalation. A transportable system has been considered as this could be deployed close to the site of the accident and would allow rapid measurements to be made. The feasibility of a transportable 241Am-in-nose-blow and nasal swab measurement system has also been considered. This would be used to help select people for 241Am-in-lung measurements. (author)

  1. Sequential leaching extraction of 239,240Pu, 238Pu, 241Pu and 241Am from a mud sample: An intercomparison study

    International Nuclear Information System (INIS)

    Full text: The determination of the association percentages of transuranics to different sediment phases could define their fate once they have been deposited onto the marine floor and their possible reactivity at the sediment/sea water interphase. Nowadays, there is a wide variety of leaching methods to extract transuranics from the different geochemical compounds conforming the sediments. Nevertheless, a general controversy is extended in the scientific world due to the extreme difficulty in testing their reliability, since the standards of transuranics linked to a certain sedimentary phase are not commercially available. Two mud subsamples taken from a storage container were analysed employing the same sequential extraction method, but with small handling differences.The following fractions were isolated: (1) Readily available (2) Carbonate bound and specifically adsorbed (3) Organically bound (4) Oxide and hydroxides bound and (5) residual. The 239,240Pu, 238Pu and 241Am extracted in each phase were analysed using standard radiochemical procedures. 241Pu was determined by both direct scintillation counting and through the 241Am in-growth up on the old disks containing Plutonium. The procedure for uncertainty calculations has been also included. (author)

  2. Sequential leaching extraction of 239,240Pu, 238Pu, 241Pu, 237Np and 241Am from a mud sample: An intercomparison study

    International Nuclear Information System (INIS)

    The transuranics content of a mud sample taken from a nuclear waste storage container was analysed employing two different sequential extraction methods. The following fractions were isolated: (1)Water soluble (2) Readily available (3) Carbonate bound and specifically adsorbed (4) Organically bound (5) Oxide and hydroxides bound and (6) residual. Both methods differ in the reagents employed, the extraction sequence applied as well as the temperature and means of extraction. The 239,240Pu, 238Pu, 237Np and 241Am extracted in each phase were determined using standard radiochemical procedures. 241Pu was analysed through the 241Am in-growth on just one old disk of the residual fraction containing plutonium. Plutonium was mainly associated to organic-oxides fractions (89-92 %). The percentage extracted in each fraction depended on the method and the extraction sequence used. The soluble fraction of plutonium was less than 13%. Neptunium seemed to be the more soluble than the other transuranics (27%) and the americium showed a tendency to be associated to carbonates (30%). (author)

  3. 10 CFR 32.57 - Calibration or reference sources containing americium-241 or radium-226: Requirements for license...

    Science.gov (United States)

    2010-01-01

    ... or radium-226: Requirements for license to manufacture or initially transfer. 32.57 Section 32.57... americium-241 or radium-226: Requirements for license to manufacture or initially transfer. An application... containing americium-241 or radium-226, for distribution to persons generally licensed under § 31.8 of...

  4. Vapor and gas sampling of single-shell tank 241-T-104 using the in situ vapor sampling system

    Energy Technology Data Exchange (ETDEWEB)

    Lockrem, L.L.

    1997-08-08

    The Vapor Issue Resolution Program tasked the Vapor Team (the team) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-T-104. This document presents sampling data resulting from the February 7, 1996 sampling of SST 241-T-104. Analytical results will be presented in separate reports issued by the laboratories that supplied and analyzed the sampling media.

  5. Spatial statistical analysis of contamination level of 241Am and 239Pu, Thule, North-West Greenland

    Energy Technology Data Exchange (ETDEWEB)

    Strodl Andersen, J. (JSA EnviroStat (Denmark))

    2011-10-15

    A spatial analysis of data on radioactive pollution on land at Thule, North-West Greenland is presented. The data comprises levels of 241Am and 239,240Pu on land. Maximum observed level of 241Am is 2.8x105 Bq m-2. Highest levels were observed near Narsaarsuk. This area was also sampled most intensively. In Groennedal the maximum observed level of 241Am is 1.9-104 Bq m-2. Prediction of the overall amount of 241Am and 239,240Pu is based on grid points within the range from the nearest measurement location. The overall amount is therefore highly dependent on the model. Under the optimal spatial model for Narsaarsuk, within the area of prediction, the predicted total amount of 241Am is 45 GBq and the predicted total amount of 239,240Pu is 270 GBq. (Author)

  6. Spatial statistical analysis of contamination level of 241Am and 239Pu, Thule, North-West Greenland

    DEFF Research Database (Denmark)

    Strodl Andersen, Jens

    A spatial analysis of data on radioactive pollution on land at Thule, North-West Greenland is presented. The data comprises levels of 241Am and 239,240Pu on land. Maximum observed level of 241Am is 2.8×105 Bq m-2. Highest levels were observed near Narsaarsuk. This area was also sampled most...... intensively. In Grønnedal the maximum observed level of 241Am is 1.9×104 Bq m-2. Prediction of the overall amount of 241Am and 239,240Pu is based on grid points within the range from the nearest measurement location. The overall amount is therefore highly dependent on the model. Under the optimal spatial...... model for Narsaarsuk, within the area of prediction, the predicted total amount of 241Am is 45 GBq and the predicted total amount of 239,240Pu is 270 GBq....

  7. 48 CFR 52.241-1 - Electric Service Territory Compliance Representation.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Electric Service Territory... ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Text of Provisions and Clauses 52.241-1 Electric Service Territory Compliance Representation. As prescribed in...

  8. Plutonium {sup 241}Pu in tissues and organs of Cervidae from Northern Poland

    Energy Technology Data Exchange (ETDEWEB)

    Struminska-Parulska, Dagmara I.; Skwarzec, Bogdan [Gdansk Univ. (Poland). Dept. of Environmental Chemistry and Radiochemistry

    2015-07-01

    Livers, kidneys and muscles of large herbivorous animals: roe deer, red deer and fallow deer, collected in Northern Poland, were the subject of the investigation. The concentration of {sup 241}Pu ranged widely between 1.31 ± 0.28 and 214.5 ± 25.8 mBq kg{sup -1} ww and decreased in the order kidney > liver > muscle. The average values of the activity concentrations of {sup 241}Pu were 11.5 ± 1.8 mBq kg{sup -1} ww in muscles, 14.0 ± 2.25 mBq kg{sup -1} ww in liver and 85.5 ± 9.7 mBq kg{sup -1} ww in kidneys. As statistically checked the sampling location, sex, age and species of animals did not influence on plutonium concentrations of the analyzed samples. Only the organ type significantly influenced {sup 241}Pu content. The values of {sup 241}Pu/{sup 29+240}Pu activity ratio in analyzed samples ranged from 7.12 ± 2.15 to 99.3 ± 16.4 and the results showed the main source of plutonium in analyzed organs could be the Chernobyl accident.

  9. Tank characterization report for single-shell tank 241-BY-112

    Energy Technology Data Exchange (ETDEWEB)

    Baldwin, J.H.

    1997-08-22

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-112. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10. (This tank has been designated a Ferrocyanide Watch List tank.)

  10. Plutonium 241Pu in tissues and organs of Cervidae from Northern Poland

    International Nuclear Information System (INIS)

    Livers, kidneys and muscles of large herbivorous animals: roe deer, red deer and fallow deer, collected in Northern Poland, were the subject of the investigation. The concentration of 241Pu ranged widely between 1.31 ± 0.28 and 214.5 ± 25.8 mBq kg-1 ww and decreased in the order kidney > liver > muscle. The average values of the activity concentrations of 241Pu were 11.5 ± 1.8 mBq kg-1 ww in muscles, 14.0 ± 2.25 mBq kg-1 ww in liver and 85.5 ± 9.7 mBq kg-1 ww in kidneys. As statistically checked the sampling location, sex, age and species of animals did not influence on plutonium concentrations of the analyzed samples. Only the organ type significantly influenced 241Pu content. The values of 241Pu/29+240Pu activity ratio in analyzed samples ranged from 7.12 ± 2.15 to 99.3 ± 16.4 and the results showed the main source of plutonium in analyzed organs could be the Chernobyl accident.

  11. 12 CFR 303.241 - Reduce or retire capital stock or capital debt instruments.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Reduce or retire capital stock or capital debt... RULES OF PRACTICE FILING PROCEDURES Other Filings § 303.241 Reduce or retire capital stock or capital... or preferred stock, or to retire any part of its capital notes or debentures pursuant to section...

  12. 19 CFR 24.1 - Collection of Customs duties, taxes, fees, interest, and other charges.

    Science.gov (United States)

    2010-04-01

    ... affecting § 24.1, see the List of CFR Sections Affected, which appears in the Finding Aids section of the... other obligation by check and more than one check is returned dishonored by the debtor's financial... negotiable papers covering duties, taxes, fees, interest, and other Customs charges shall be made payable...

  13. Tank characterization report for single-shell tank 241-B-108

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1997-05-12

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-108. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05.

  14. Effects of the herbicide glyphosate on the uptake of 239Pu and 241Am to vegetation

    International Nuclear Information System (INIS)

    Glyphosate (n-phosphonomethyl glycine) is a broad spectrum herbicide widely used in lowland agriculture, forestry and improved upland pastures. Although its metal chelating properties are well established, its interaction with radionuclides remains unknown. A pot experiment was conducted to determine the effect of soil applications of glyphosate on the uptake of 239Pu and 241Am to peas and carrots grown in loam, peat and sand soils. Soil-to-plant transfer factors were calculated for treated and untreated soils at harvest. The most marked effect was an increase in 241Am uptake to crops grown in loam soil. Supplementary laboratory batch experiments were conducted by shaking radiolabelled soil and its associated soil solution with glyphosate. The activity concentration of 241Am increased ten fold in the liquid phase of loam soils treated with glyphosate. It is postulated that this 241Am desorption could have been mediated by the formation of a stable Am-glyphosate complex which was subsequently more available for crop uptake than Am alone. (author)

  15. Project W-320, 241-C-106 sluicing HVAC calculations, Volume 4

    International Nuclear Information System (INIS)

    This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following design calculations: Cooling load in pump pit 241-AY-102; Pressure relief seal loop design; Process building piping stress analysis; Exhaust skid maximum allowable leakage criteria; and Recirculation heat, N509 duct requirements

  16. Concentrations of sup(239,240)Pu and 241Am in drinking water and organic fertilizer

    International Nuclear Information System (INIS)

    As part of an investigation of the chemistry and aquatic distribution of fallout-derived sup(239,240)Pu and 241Am in the aquatic environment a study has been made of the concentration of these nuclides in the drinking water and organic fertilizer, distributed to the populace of the Chicago area. The results clearly indicate that the concentration of sup(239,240)Pu is always lower in the water which has been treated at the Chicago Central Water Filtration Plant than in the raw water before treatment. Raw water levels are consistent with normal levels of sup(239,240)PU found in Lake Michigan waters which are approx 6 orders of magnitude below the maximum permissible concentration standard for drinking water. An additional possible source of sup(239,240)Pu and 241Am to humans can be through the distribution of the organic fertilizer, 'Nu Earth', by the Metropolitan Sanitary District, free of charge, for the use in home gardens. 'Nu Earth' consists primarily of sediment from an Imhoff Process which has been air-dried and aged in large, open-air piles. Samples of this organic fertilizer were analysed for sup(239,240)Pu and 241Am. The results indicate that there is little evidence to indicate that sup(239,240)Pu in drinking water or sup(239,240)Pu and 241Am from organic sludge will be health hazards in the Chicago area under current conditions. (U.K.)

  17. Structural evaluation of thermocouple probes for 241-AZ-101 waste tank

    International Nuclear Information System (INIS)

    This document reports on the structural analysis of the thermocouple probe to be installed in 241-AZ-101 waste tank. The thermocouple probe is analyzed for normal pump mixing operation and potential earthquake induced loads required by the Hanford Site Design Criteria SDC-4.1

  18. Tank characterization report for single-shell tank 241-BX-107

    Energy Technology Data Exchange (ETDEWEB)

    Raphael, G.F.

    1996-02-28

    This study examined and assessed the status, safety issues, composition, and distribution of the wastes contained in the tank 241-BX-107. Historical and most recent information, ranging from engineering structural assessment experiments, process history, monitoring and remediation activities, to analytical core sample data, were compiled and interpreted in an effort to develop a realistic, contemporary profile for the tank BX-107 contents.

  19. Tank characterization report for double-shell Tank 241-AP-107

    International Nuclear Information System (INIS)

    The purpose of this tank characterization report is to describe and characterize the waste in Double-Shell Tank 241-AP-107 based on information gathered from various sources. This report summarizes the available information regarding the waste in Tank 241-AP-107, and arranges it in a useful format for making management and technical decisions concerning this particular waste tank. In addition, conclusion and recommendations based on safety and further characterization needs are given. Specific objectives reached by the sampling and characterization of the waste in Tank 241-AP-107 are: Contribute toward the fulfillment of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05 concerning the characterization of Hanford Site high-level radioactive waste tanks; Complete safety screening of the contents of Tank 241-AP-107 to meet the characterization requirements of the Defense Nuclear Facilities Safety board (DNFSB) Recommendation 93-5; and Provide tank waste characterization to the Tank Waste Remediation System (TWRS) Program Elements in accordance with the TWRS Tank Waste Analysis Plan

  20. Tank 241-BY-109, cores 201 and 203, analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Esch, R.A.

    1997-11-20

    This document is the final laboratory report for tank 241-BY-109 push mode core segments collected between June 6, 1997 and June 17, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (Bell, 1997), the Tank Safety Screening Data Quality Objective (Dukelow, et al, 1995). The analytical results are included.

  1. Cesium-137 and americium-241 distribution by granulometric fractions of soil at Azgir test site grounds

    International Nuclear Information System (INIS)

    In measurements of radionuclide specific content in surface soil layer of contaminated territories it is important to determine in what agglomerations of soil particles there is the highest radionuclide concentration. For this purpose granulometric composition of soil at Azgir test site was studied and cesium-137 and americium-241 distribution by soil fractions was researched. (author)

  2. Contractor annual self-assessment report mixer pump replacementtank 241-SY-101

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, M.J.

    1997-01-14

    The purpose of this report is to provide the results of the first annual self- assessment to confirm readiness to replace the mixer pump (pump {number_sign}1) in Tank 241-SY-101, should the mixer pump fail or need to be replaced for some other reason.

  3. Tank 241-C-103 organic vapor and liquid characterization and supporting activities, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    The action proposed is to sample the vapor space and liquid waste and perform other supporting activities in Tank 241-C-103 located in the 241-C Tank Farm on the Hanford Site. Operations at Tank 241-C-103 are curtailed because of an unreviewed safety question (USQ) concerning flammability issues of the organic waste in the tank. This USQ must be resolved before normal operation and surveillance of the tank can resume. In addition to the USQ, Tank 241-C-103 is thought to be involved in several cases of exposure of individuals to noxious vapors. This safety issue requires the use of supplied air for workers in the vicinity of the tank. Because of the USQ, the US Department of Energy proposes to characterize the waste in the vapor space and the organic and aqueous layers, to determine the volume of the organic layer. This action is needed to: (1) assess potential risks to workers, the public, and the environment from continued routine tank operations and (2) provide information on the waste material in the tank to facilitate a comprehensive safety analysis of this USQ. The information would be used to determine if a flammable condition within the tank is credible. This information would be used to prevent or mitigate an accident during continued waste storage and future waste characterization. Alternatives to the proposed activities have been considered in this analysis

  4. Project W-320, 241-C-106 sluicing HVAC calculations, Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, J.W.

    1998-07-30

    This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following design calculations: Cooling load in pump pit 241-AY-102; Pressure relief seal loop design; Process building piping stress analysis; Exhaust skid maximum allowable leakage criteria; and Recirculation heat, N509 duct requirements.

  5. Ultrasonic Examination of Double-Shell Tank 241-AW-106 Examination Completed July 2009.

    Energy Technology Data Exchange (ETDEWEB)

    Pardini, Allan F.; Weier, Dennis R.; Anderson, Kevin K.; Hathaway, John E.

    2009-08-28

    AREVA Federal Services LLC (AFS), under a contract from Washington River Protection Solutions (WRPS), has performed an ultrasonic examination of selected portions of Double-Shell Tank 241-AW-106. PNNL is responsible for preparing a report(s) that describes the results of the AFS ultrasonic examinations.

  6. Ultrasonic Examination of Double-Shell Tank 241-AW-105 Examination Completed April 2009.

    Energy Technology Data Exchange (ETDEWEB)

    Pardini, Allan F.; Weier, Dennis R.; Anderson, Kevin K.; Hathaway, John E.

    2009-05-31

    AREVA Federal Services LLC (AFS), under a contract from Washington River Protection Solutions (WRPS), has performed an ultrasonic examination of selected portions of Double-Shell Tank 241-AW-105. PNNL is responsible for preparing a report(s) that describes the results of the AFS ultrasonic examinations.

  7. Ultrasonic Examination of Double-Shell Tank 241-AN-102 Examination Completed July 2008.

    Energy Technology Data Exchange (ETDEWEB)

    Pardini, Allan F.; Weier, Dennis R.; Anderson, Kevin K.

    2008-08-28

    AREVA Federal Services LLC (AFS), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic examination of selected portions of Double-Shell Tank 241-AN-102. PNNL is responsible for preparing a report(s) that describes the results of the AFS ultrasonic examinations.

  8. Ultrasonic Examination of Double-Shell Tank 241-AW-101 Examination Completed February 2009.

    Energy Technology Data Exchange (ETDEWEB)

    Pardini, Allan F.; Weier, Dennis R.; Anderson, Kevin K.

    2009-03-18

    AREVA Federal Services LLC (AFS), under a contract from Washington River Protection Solutions (WRPS), has performed an ultrasonic examination of selected portions of Double-Shell Tank 241-AW-101. PNNL is responsible for preparing a report(s) that describes the results of the AFS ultrasonic examinations.

  9. 24 CFR 241.825 - Pro rata refund of insurance premium.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Pro rata refund of insurance... Projects Without a HUD-Insured or HUD-Held Mortgage Premiums § 241.825 Pro rata refund of insurance premium... Commissioner shall refund to the lender for the account of the borrower an amount equal to the pro rata...

  10. Tank 241-AY-102 Leak Assessment Supporting Documentation: Miscellaneous Reports, Letters, Memoranda, And Data

    International Nuclear Information System (INIS)

    This report contains reference materials cited in RPP-ASMT -53793, Tank 241-AY-102 Leak Assessment Report, that were obtained from the National Archives Federal Records Repository in Seattle, Washington, or from other sources including the Hanford Site's Integrated Data Management System database (IDMS)

  11. Biosorption of Am-241 and Cs-137 by radioactive liquid waste by coffee husk

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Rafael Vicente de Padua; Sakata, Solange Kazumi; Bellini, Maria Helena; Marumo, Julio Takehiro, E-mail: jtmarumo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Radioactive Waste Management Laboratory of Nuclear and Energy Research Institute, IPEN-CNEN/SP, has stored many types of radioactive liquid wastes, including liquid scintillators, mixed wastes from chemical analysis and spent decontamination solutions. These wastes need special attention, because the available treatment processes are often expensive and difficult to manage. Biosorption using biomass of vegetable using agricultural waste has become a very attractive technique because it involves the removal of heavy metals ions by low cost biossorbents. The aim of this study is to evaluate the potential of the coffee husk to remove Am-241 and Cs-137 from radioactive liquid waste. The coffee husk was tested in two forms, treated and untreated. The chemical treatment of the coffee husk was performed with HNO{sub 3} and NaOH diluted solutions. The results showed that the coffee husk did not showed significant differences in behavior and capacity for biosorption for Am-241 and Cs-137 over time. Coffee husk showed low biosorption capacity for Cs-137, removing only 7.2 {+-} 1.0% in 4 hours of contact time. For Am-241, the maximum biosorption was 57,5 {+-} 0.6% in 1 hours. These results suggest that coffee husk in untreated form can be used in the treatment of radioactive waste liquid containing Am-241. (author)

  12. Tank characterization report for single-shell tank 241-S-104

    Energy Technology Data Exchange (ETDEWEB)

    DiCenso, A.T.; Simpson, B.C.

    1994-09-29

    In July and August 1992, Single-Shell Tank 241-S-104 was sampled as part of the overall characterization effort directed by the Hanford Federal Facility Agreement and Consent Order. Sampling was also performed to determine proper handling of the waste, to address corrosivity and compatibility issues, and to comply with requirements of the Washington Administrative Code. This Tank Characterization Report presents an overview of that tank sampling and analysis effort, and contains observations regarding waste characteristics. It also presents expected concentration and bulk inventory data for the waste contents based on this latest sampling data and background historical and surveillance tank information. Finally, this report makes recommendations and conclusions regarding operational safety. The purpose of this report is to describe the characteristics the waste in Single-Shell Tank 241-S-104 (hereafter, Tank 241-S-104) based on information obtained from a variety of sources. This report summarizes the available information regarding the chemical and physical properties of the waste in Tank 241-S-104, and using the historical information to place the analytical data in context, arranges this information in a format useful for making management and technical decisions concerning waste tank safety and disposal issues. In addition, conclusions and recommendations are presented based on safety issues and further characterization needs.

  13. Disposition of 241AmO2 following inhalation by beagle dogs

    International Nuclear Information System (INIS)

    Translocation of 241Am from the lungs of beagles following inhalation of AmO2 was fairly rapid, roughly equal quantities being found in the liver and skeleton at all postexposure times to 810 days. Less than 16 percent of the initial body burden was excreted, more than two-thirds of this in the feces

  14. Fate and transport of constituents leaked from Tank 241-A-105

    International Nuclear Information System (INIS)

    Following a January 28, 1965 sudden steam release in Tank 241-A-105, the carbon steel liner of the tank was noted to have bulged to a maximum height of about 8.5 feet (2.6 meters). Most of this bulging likely resulted from the January 28, 1965 incident. But available data indicate that some bulging during an earlier leak in 1963 when waste was being added to the tank may have contributed. By March 8, 1965, increases in radiation in the 14-05-03 leak detection lateral indicted that fluids had escaped the tank and that the liner was ruptured. Waste was subsequently transferred from Tank 241-A-105 to other tanks, and liquid levels in Tank 241-A-105 were maintained at about 18 inches to control temperature to prevent deterioration of the concrete. Spray cooling water was added weekly to the tank from February 1971 to December 1978 to maintain liquid levels and temperatures, and some of this fluid is assumed to have leaked from the tank. This study examined available data to determine, to the extent possible, the distribution of the leaked constituents in surrounding soils and whether they migrated to groundwater. In this assessment, available data from gross gamma logging of dry wells and leak detection laterals as well as data from analyses of groundwater samples were examined throughout the period of interest. Logs of wells and photographs taken during construction of the 241-A-105 Tank Farm were also examined

  15. Tank 241-AY-102 Leak Assessment Supporting Documentation: Miscellaneous Reports, Letters, Memoranda, And Data

    Energy Technology Data Exchange (ETDEWEB)

    Engeman, J. K.; Girardot, C. L.; Harlow, D. G.; Rosenkrance, C. L.

    2012-12-20

    This report contains reference materials cited in RPP-ASMT -53793, Tank 241-AY-102 Leak Assessment Report, that were obtained from the National Archives Federal Records Repository in Seattle, Washington, or from other sources including the Hanford Site's Integrated Data Management System database (IDMS).

  16. Tank characterization report for single-shell tank 241-A-101

    International Nuclear Information System (INIS)

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-A-101. This tank has been listed on the Hydrogen Watch List. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10

  17. Tank characterization report for double-shell tank 241-AN-104

    Energy Technology Data Exchange (ETDEWEB)

    Hu, T.A.

    1997-08-20

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AN-104. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10.

  18. Tank Characterization Report for Single-Shell Tank 241-U-103

    International Nuclear Information System (INIS)

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-U-103. This report supports the requirements of the Tri-Party Agreement Milestone M-44-15B

  19. Tank characterization report for double-shell tank 241-AN-104

    International Nuclear Information System (INIS)

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AN-104. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10

  20. Chemical Characterization of an Envelope C Sample from Hanford Tank 241-AN-102

    International Nuclear Information System (INIS)

    An approximately 14.25 L sample from Hanford waste tank 241-AN-102 was received at the Savannah River Technology Center (SRTC) and chemically characterized. Prior to characterization the sample was diluted to ∼6 M sodium concentration. The filtered supernatant liquid, the total dried solids of the diluted sample, and the washed insoluble solids obtained from filtration of the diluted sample were analyzed. A mass balance calculation of the three fractions of the sample analyzed indicate the analytical results appear relatively self-consistent for major components of the sample. However, some inconsistency was observed between results were more than one method of determination was employed and for species present in low concentrations. An analysis of the organic complexants appears to be consistent with the TOC result. Some evidence was found to indicate the possible contamination of the first shipment of 241-AN-102 samples received at SRTC with Cm244 and possibly Am241 and plutonium isotopes. The comparison to previous analyses of samples from 241-AN-102 indicates general agreement with the current analytical results. The comparison of the solids analysis showed large deviations attributed to differences in obtaining the solids from the bulk sample

  1. Influence of some factors on alpha energy spectrum of 241Am fire alarm source

    Institute of Scientific and Technical Information of China (English)

    1999-01-01

    Several primary factors influencing the alpha energy spectrum of 241Am fire alarm source have been studied in order to get betteralpha energy spectrum.The results show that the homogeneity andthe thickness of metal surface coat and the size of active area of thesource have considerable influence on the alpha energy spectrum of thesource.

  2. Tank characterization report for single-shell tank 241-b-110

    Energy Technology Data Exchange (ETDEWEB)

    Field, J.G.

    1997-08-14

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-110. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05.

  3. Progress toward resolution of vapor problems associated with tank 241-C-103

    International Nuclear Information System (INIS)

    Noxious and flammable gases and vapors associated with high-level radioactive waste storage tank 241-C-103 at the Hanford Site are discussed. Focus is on the Westinghouse Hanford Company strategy to characterize the tank headspace. The sampling and analysis methodology is described. Sampling limitations, devices, and equipment are discussed. Results to date are given

  4. Tank characterization report for double-shell tank 241-AN-103

    Energy Technology Data Exchange (ETDEWEB)

    Wilkins, N.E.

    1997-08-22

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AN-103. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10. (This tank has been designated an Hydrogen Watch List tank.)

  5. Development of an 241Am applicator for intracavitary irradiation of gynecologic cancers.

    Science.gov (United States)

    Nath, R; Peschel, R E; Park, C H; Fischer, J J

    1988-05-01

    Sealed sources of 241Am that emit primarily 60 keV photons produce relative dose distributions in water comparable to those from 137Cs or 226Ra sources and can produce dose rates of up to 100 cGy/hr at 1 cm in water. Also, 241Am gamma rays can be effectively shielded by thin layers of high atomic number materials (HVL is 1/8th mm of lead) placed on the applicator or inside some body cavities (for example, hypaque in bladder, barium sulphate in rectum). These properties of 241Am sources open a new approach to optimizing intracavitary irradiation of various cancers by allowing a reduction in dose and volume of irradiated critical organs or by increasing tumor doses. The relative ease with which highly effective shielding is achievable with 241Am sources would allow the design and fabrication of partially shielded applicators which can produce asymmetric dose distributions to allow unidirectional irradiation of localized lesions. Design and dosimetry characteristics of a gynecological applicator containing 241Am sources are presented. The applicator consists of a 2, 3, or 4 segment vaginal plaque (loaded with 2 and 5 Ci 241Am sources) and a tandem made up of a single 8 Ci 241Am source. Dose rates at 2 cm from the plaques are 42.0, 47.4, 58.3 and 56.7 cGy/hr for 5-5, 5-4-5, 5-5-5, and 5-4-4-5 Ci plaques, respectively. The 5-4-5 Ci plaque in combination with the 8 Ci tandem produces dose rates of 60.0 and 22.8 cGy/hr to points A and B, respectively. Surface dose rates on the plaque applicators are 143, 124, 142 and 132 cGy/hr for 5-5, 5-4-5, 5-5-5 and 5-4-4-5 Ci applicators, respectively. The shielding effect of a 0.5 mm thick lead foil on one side of the 5-4-5 Ci applicator is found to be a factor of 16.8; for example, the dose rate at 2 cm from the unshielded side is 42.0 cGy/hr compared to a dose rate of 2.5 cGy/hr at 2 cm from the shielded side. Initial clinical experience with this applicator in the treatment of recurrent gynecological lesions is also presented

  6. Proposed retention model for human inhalation exposure to 241AmO2

    International Nuclear Information System (INIS)

    A dosimetry model based on a four-year study in Beagle dogs was developed to predict patterns of absorbed radiation doses for people exposed by inhalation to 241AmO2. Following a single inhalation exposure to one of three sizes of monodisperse or a polydisperse aerosol of 241AmO2, pairs of dogs were sacrificed at 8, 32, 64 and 256 days, and 2 and 4 years. For about 80% of the initial lung burden, the retention halftimes were 11, 18, 26 and 27 days for the 0.75, 1.5 and 3.0 μm aerodynamic diameter and the 1.8 μm activity median aerodynamic diameter aerosols, respectively. For the remaining 20% of the initial lung burden, the retention halftimes were between 200 to 300 days with no apparent particle size influence. Additional 241Am metabolic studies reported in the literature using inhalation exposure or injection of the citrate complex were synthesized in the model as were eleven reported cases of human inhalation exposure. This model is compared to the ICRP II and TGLD lung models, both developed by analogy to Pu metabolism. The proposed model differs from these latter models in two important areas: (a) lung retention of 241AmO2 could not be adapted to the classifications used in these models, and (b) the fractional translocation from lung to other organs is 2 to 8 times larger. These factors considerably alter the predicted radiation dose distribution among organs and lead to the conclusion that derived radiation protection standards for 241AmO2 inhalation exposure should be modified. (author)

  7. Process Control Plan for Tank 241-SY-101 Surface Level Rise Remediation

    International Nuclear Information System (INIS)

    The tank 241-SY-101 transfer system was conceived and designed to address the immediate needs presented by rapidly changing waste conditions in tank 241-SY-101. Within the last year or so, the waste in this tank has exhibited unexpected behavior (Rassat et al. 1999) in the form of rapidly increasing crust growth. This growth has been brought about by a rapidly increasing rate of gas entrapment within the crust. It has been conceived that the lack of crust agitation beginning upon the advent of mixer pump operations may have set-up a more consolidated, gas impermeable barrier when compared to a crust regularly broken up by the prior buoyant displacement events within the tank. As a result, a series of level-growth remediation activities have been developed for tank 241-SY-101. The initial activities are also known as near-term crust mitigation. The first activity of near-term mitigation is to perform the small transfer of convective waste from tank 241-SY-101 into tank 241-SY-102. A 100 kgal transfer represents about a 10% volume reduction allowing a 10% water in-tank dilution. Current thinking holds that this should be enough to dissolve nitrite solids in the crust and perhaps largely eliminate gas retention problem in the crust (Raymond 1999). Additional mitigation activities are also planned on less constrained schedules. The net affect of the small transfer and follow-on mitigation activities for tank 241-SY-101 is strongly believed to be the remediation of tank 241-SY-101 as a flammable gas safety concern. The process for remediating the tank will require two or more transfer/dilution cycles. In-tank dilution will begin shortly after the initial transfer and the total dilution required to reach the final state is estimated to be between 250 to 400K gallons. The final state of the waste will not require any active measures to safely store the waste and operation of the mixer pump will no longer be necessary. The remediation activities are centered on a purpose

  8. Radiochemical determination of the neutron capture cross sections of {sup 241}Am irradiated in the JMTR reactor

    Energy Technology Data Exchange (ETDEWEB)

    Shinohara, N.; Hatsukawa, Y.; Hata, K.; Kohno, N. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    The thermal neutron capture cross section {sigma}{sub 0} and Resonance integral I{sub 0} of {sup 241}Am leading to the production of {sup 242m}Am and {sup 242g}Am were measured by radiochemical method. The cross sections obtained in this study are {sigma}{sub 0}=60.9 {+-} 2.6 barn, I{sub 0}=213 {+-} 13 barn for {sup 241}Am(n,{gamma}){sup 242m}Am and {sigma}{sub 0}=736 {+-} 31 barn, I{sub 0}=1684 {+-} 92 barn for {sup 241}Am(n,{gamma}){sup 242g}Am. (author)

  9. Measurement of the Am241(γ,n)Am240 reaction in the giant dipole resonance region

    Science.gov (United States)

    Tonchev, A. P.; Hammond, S. L.; Howell, C. R.; Huibregtse, C.; Hutcheson, A.; Kelley, J. H.; Kwan, E.; Raut, R.; Rusev, G.; Tornow, W.; Kawano, T.; Vieira, D. J.; Wilhelmy, J. B.

    2010-11-01

    The photodisintegration cross section of the radioactive nucleus Am241 has been obtained using activation techniques and monoenergetic γ-ray beams from the HIγS facility. The induced activity of Am240 produced via the Am241(γ,n) reaction was measured in the energy interval from 9 to 16 MeV utilizing high-resolution γ-ray spectroscopy. The experimental data for the Am241(γ,n) reaction in the giant dipole resonance energy region are compared with statistical nuclear-model calculations.

  10. Final report for Tank 241-B-101, push mode cores 90 and 91. Revision 1

    International Nuclear Information System (INIS)

    This is the final report for tank 241-at sign 101, cores 90 and 91. Samples from these cores were analyzed for safety screening purposes in accordance with the Tank 241-B-101 Tank Characterization Plan (TCP) (Reference 1). This final report contains the results for three sets of TGA and gravimetric analyses performed after the 90-day report was issued. Two of these TGA/gravimetric percent water sets of analyses were done because low original TGA results were obtained for the lower half segment of core 90, segment 2 and the facie of core 91, segment 2; the third set of analyses were performed because the TGA and gravimetric percent water results for the upper half segment of core 90, segment 2 differed by approximately a factor of three and further investigation was warranted

  11. Tank 241-B-109, cores 169 and 170 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Nuzum, J.L.

    1997-01-20

    This document is the final laboratory report for tank 241-B-109. Push mode core segments were removed from risers 4 and 7 between August 22, 1996, and August 27, 1996. Segments were received and extruded at 222-S Analytical Laboratory. Analyses were performed in accordance with Tank 241-B-109 Push Mode Core Sampling and Analysis Plan (TSAP) and Tank Safety Screening Data Quality Objective (DQO). The results for primary safety screening data, including differential scanning calorimetry (DSC) analyses, thermogravimetric analyses (TGA), bulk density determinations, and total alpha activity analyses for each subsegment, were presented in the 45-Day report (Rev. 0 of this document). The 45-Day report is included as Part II of this revision. The raw data for DSC and TGA is found in Part II of this report. The raw data for all other analyses are included in this revision.

  12. Tank 241-T-112, cores 185 and 186 analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the analytical laboratory report for tank 241-T-112 push mode core segments collected between February 26, 1997 and March 19, 1997. The segments were subsampled and analyzed in accordance with the Tank 241-T-112 Push Mode Core Samplings and Analysis Plan (TSAP) and the Safety Screening Data Quality Objective (DQO). The analytical results are included in the data summary table. None of the samples submitted for Differential Scanning Calorimetry and Total Alpha Activity (AT) exceeded notification limits as stated in the TSAP. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group in accordance with the Memorandum of Understanding and are not considered in this report

  13. Tank 241-AX-103, cores 212 and 214 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1998-02-05

    This document is the analytical laboratory report for tank 241-AX-103 push mode core segments collected between July 30, 1997 and August 11, 1997. The segments were subsampled and analyzed in accordance with the Tank 241-AX-103 Push Mode Core Sampling and Analysis Plan (TSAP) (Comer, 1997), the Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995) and the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO) (Turner, et al., 1995). The analytical results are included in the data summary table (Table 1). None of the samples submitted for Differential Scanning Calorimetry (DSC), Total Alpha Activity (AT), plutonium 239 (Pu239), and Total Organic Carbon (TOC) exceeded notification limits as stated in the TSAP (Conner, 1997). The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group in accordance with the Memorandum of Understanding (Schreiber, 1997) and not considered in this report.

  14. Structural analysis of color video camera installation on tank 241AW101 (2 Volumes)

    Energy Technology Data Exchange (ETDEWEB)

    Strehlow, J.P.

    1994-08-24

    A video camera is planned to be installed on the radioactive storage tank 241AW101 at the DOE` s Hanford Site in Richland, Washington. The camera will occupy the 20 inch port of the Multiport Flange riser which is to be installed on riser 5B of the 241AW101 (3,5,10). The objective of the project reported herein was to perform a seismic analysis and evaluation of the structural components of the camera for a postulated Design Basis Earthquake (DBE) per the reference Structural Design Specification (SDS) document (6). The detail of supporting engineering calculations is documented in URS/Blume Calculation No. 66481-01-CA-03 (1).

  15. Precision Cross Section Measurement for the ^241Am(γ,n) Reaction at HIγS

    Science.gov (United States)

    Tonchev, A.; Hutcheson, A.; Howell, C. R.; Kwan, E.; Rusev, G.; Tornow, W.; Hammond, S.; Karwowski, H. J.; Huibregtse, C.; Kelley, J. H.; Vieira, D. L.; Wilhelmy, J. B.; Stoyer, M. A.

    2008-10-01

    The photodisintegration cross section on radioactive ^241Am target has been measured for the first time using monoenergetic γ-ray beams from the HIγS facility. Induced activity from ^240Am produced via the (γ,n) reaction was measured by the activation technique using high resolution HPGe detectors. The (γ,n) cross section was determined both by measuring the absolute γ-flux and by comparison to the ^197Au(γ,n) cross section used as a standard. In the following, we report new data for the excitation function of the ^241Am(γ,n ) reaction from near threshold to 16 MeV incident γ-ray energy and we compare the data with statistical nuclear-model calculations performed with the GNASH, EMPIRE, and TALYS codes.

  16. Measurement of the ^241Am(n,2n) Reaction Cross Section with the Activation Technique

    Science.gov (United States)

    Tonchev, A.; Crowell, A.; Fallin, B.; Howell, C.; Hutcheson, A.; Tornow, W.; Kelley, J.; Angell, C.; Karwowski, H.; Pedroni, R.; Becker, J.; Dashdorj, D.; Macri, R.; Wilhelmy, J.; Bond, E.; Fitzpatrick, J.; Slemmons, A.; Vieira, D.

    2006-10-01

    High-precision measurements of the ^241Am(n,2n)^240Am reaction have been performed with neutron energies from 8.8 to 14.0 MeV. The monoenergetic neutron beams were produced via the ^2H(d,n)^3He reaction using the 10 MV Tandem accelerator at TUNL. The radioactive targets consisted of 1mg highly-enriched ^241Am sandwiched between four different thin monitor foils. They were irradiated with a neutron flux of 3x10^7 n cm-2 s-1. After each irradiation the induced activity in the targets and monitors was measured off-line with 60% HPGe detectors. Our preliminary neutron induced cross sections will be compared with recent literature results and statistical model calculations using the GNASH and EMPIRE codes.

  17. Tank 241-A-101, cores 154 and 156 analytical results for the 45 day report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1996-10-18

    This document is the 45-day laboratory report for tank 241 -A-101 push mode core segments collected between July II, 1996 and July 25, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-A-101 Push Mode Core Sampling and Analysis Plan (TSAP) (Field, 1996) and the Safety Screening Data Quality Objective (DQO)(Dukelow, et al., 1995). The analytical results are included in the data summary table (Table 1). None of the samples submitted for Total Alpha Activity (AT) or Differential Scanning Calorimetry (DSC) analyses exceeded notification limits as stated in the Safety Screening DQO (Dukelow, et al., 1995). Statistical evaluation on results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. Primary safety screening results and the raw data from thermogravimetric analysis (TGA) and DSC analyses are included in this report.

  18. Tank characterization report for double-shell Tank 241-AW-105

    Energy Technology Data Exchange (ETDEWEB)

    DiCenso, A.T.; Amato, L.C.; Franklin, J.D.; Lambie, R.W.; Stephens, R.H. [Los Alamos Technical Associates, Kennewick, WA (United States); Simpson, B.C. [Westinghouse Hanford Co., Richland, WA (United States)

    1994-09-28

    In May 1990, double-shell Tank 241-AW-105 was sampled to determine proper handling of the waste, to address corrosivity and compatibility issues, and to comply with requirements of the Washington Administrative Code. This Tank Characterization Report presents an overview of that tank sampling and analysis effort, and contains observations regarding waste characteristics. It also addresses expected concentration and bulk inventory data for the waste contents based on this latest sampling data and background tank information. This report summarizes the available information regarding the waste in Tank 241-AW-105, and using the historical information to place the analytical data in context, arranges this information in a useful format for making management and technical decisions concerning this waste tank. In addition, conclusions and recommendations are given based on safety issues and further characterization needs.

  19. Tank 241-T-112, cores 185 and 186 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1997-06-03

    This document is the analytical laboratory report for tank 241-T-112 push mode core segments collected between February 26, 1997 and March 19, 1997. The segments were subsampled and analyzed in accordance with the Tank 241-T-112 Push Mode Core Samplings and Analysis Plan (TSAP) and the Safety Screening Data Quality Objective (DQO). The analytical results are included in the data summary table. None of the samples submitted for Differential Scanning Calorimetry and Total Alpha Activity (AT) exceeded notification limits as stated in the TSAP. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group in accordance with the Memorandum of Understanding and are not considered in this report.

  20. Tank characterization report for single-shell tank 241-BY-107

    Energy Technology Data Exchange (ETDEWEB)

    Mccain, D.J.

    1997-04-09

    One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-BY-107. The objectives of this report are (1) to use characterization data in response to technical issues associated with 241-BY-107 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 provides the best-basis inventory estimate, and Section 4.0 makes recommendations about the safety status and additional sampling needs. The appendices contain supporting data and information.

  1. Tank characterization report for single-shell tank 241-C-109

    International Nuclear Information System (INIS)

    One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-C-109. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241 C-109 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices

  2. Project W-314 241-AN-B valve pit upgrade acceptance for beneficial use

    International Nuclear Information System (INIS)

    This report identifies the responsibilities and requirements, applicable to the 241-AN-B Valve Pit Upgrades portion of Project W-314, for Acceptance for Beneficial Use in accordance with HNF-IP-0842, Vol IV, Sec 3.12. At project turnover, the end user accepts the affected Structures, Systems, and Components (SSCs) for beneficial use. This checklist is used to help the end user ensure that all documentation, training, and testing requirements are met prior to turnover. This checklist specifically identifies those items related to the upgrading of the 241-AN-B valve pit. The upgrades include: the installation of jumper/valve manifolds with position sensors, replacement pit leak detection systems, construction of replacement cover blocks, and electrical upgrades to support the instrumentation upgrades

  3. Project W-314 241-AN-A valve pit upgrade acceptance for beneficial use

    International Nuclear Information System (INIS)

    This report identifies the responsibilities and requirements, applicable to the 241-AN-A Valve Pit Upgrades portion of Project W-314, for Acceptance for Beneficial Use in accordance with HNF-IP-0842, Vol IV, Sec 3.12. At project turnover, the end user accepts the affected Structures, Systems, and Components (SSCs) for beneficial use. This checklist is used to help the end user ensure that all documentation, training, and testing requirements are met prior to turnover. This checklist specifically identifies those items related to the upgrading of the 241-AN-A valve pit. The upgrades include: the installation of jumper/valve manifolds with position sensors, replacement pit leak detection systems, construction of replacement cover blocks, and electrical upgrades to support the instrumentation upgrades

  4. Standard test method for quantitative determination of americium 241 in plutonium by Gamma-Ray spectrometry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1994-01-01

    1.1 This test method covers the quantitative determination of americium 241 by gamma-ray spectrometry in plutonium nitrate solution samples that do not contain significant amounts of radioactive fission products or other high specific activity gamma-ray emitters. 1.2 This test method can be used to determine the americium 241 in samples of plutonium metal, oxide and other solid forms, when the solid is appropriately sampled and dissolved. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  5. Tank characterization report for single-shell tank 241-C-109

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.

    1997-05-23

    One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-C-109. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241 C-109 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices.

  6. Investigations of the chemical forms of 239Pu and 241Am in estuarine sediments and a salt marsh soil

    International Nuclear Information System (INIS)

    Estuarine sediments and a salt marsh soil have been fractionated by non-destructive procedures. The distribution of 239Pu and 241Am in these fractions has been determined by gel permeation chromatography and extraction with complexing agents. (author)

  7. SKIN DOSIMETRY IN CONDITIONS OF ITS CONSTANT SURFACE CONTAMINATION WITH SOLUTIONS OF PLUTONIUM-239 AND AMERICIUM-241

    Directory of Open Access Journals (Sweden)

    E. B. Ershov

    2012-01-01

    Full Text Available The article considers, on the basis of experimental data, the issue of assessing dose burdens to the skin basal layer in conditions of its permanent contamination with solutions of plutonium-239 and americium-241 and subsequent decontamination.

  8. ELECTROCHEMICAL CORROSION STUDIES CORE 308 SEGMENTS 14R1 & 14R2 TANK 241-AY-102

    Energy Technology Data Exchange (ETDEWEB)

    DUNCAN JB; COOKE GA

    2003-10-30

    This document reports the results of electrochemical corrosion tests on AS1S Grade 60 carbon steel coupons exposed to tank 241-AY-102 sludge under conditions similar to those near the bottom of the tank. The tests were performed to evaluate the corrosive behavior of the waste in contact with sludge that does not meet the chemistry control limits of Administrative Control (AC) 5.15, Corrosion Mitigation Program.

  9. TANK CHARACTERIATION REPORT FOR SINGLE-SHELL TANK 241-T-111

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.

    1996-04-06

    This document was initially released as WHC-EP-0806. This document is now being released as WHC-SD-WM-ER-540 in order to accommodate internet publishing. This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-111. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05.

  10. Tank 241-T-107 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    This report presents the details of the Hanford waste tank characterization study for tank 241-T-107. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedure that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank

  11. Project W-320, 241-C-106 sluicing HVAC calculations, Volume 1

    International Nuclear Information System (INIS)

    This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following calculations: Exhaust airflow sizing for Tank 241-C-106; Equipment sizing and selection recirculation fan; Sizing high efficiency mist eliminator; Sizing electric heating coil; Equipment sizing and selection of recirculation condenser; Chiller skid system sizing and selection; High efficiency metal filter shielding input and flushing frequency; and Exhaust skid stack sizing and fan sizing

  12. Carcinogenic effects of the combined action of /sup 241/Am and. gamma. -radiation

    Energy Technology Data Exchange (ETDEWEB)

    Filippova, L.G.; Buldakov, L.A.; Nifatov, A.P. (Institut Biofiziki, Moscow (USSR))

    In experiments on Wistar rats a study was made of the carcinogenic effects of the combined exposure to /sup 241/Am administered intrapertioneally (6.7 to 229.4 kBq/kg body weight) and external ..gamma..-radiation (/sup 137/Cs, 175 cGy). The occurrence of osteosarcoma, leucosis, skin and mammary tumors increased in the exposed animals. The combined irradiation produced an additive carcinogenic effect.

  13. Hanford Tank 241-C-106: Residual Waste Contaminant Release Model and Supporting Data

    International Nuclear Information System (INIS)

    CH2M HILL is producing risk/performance assessments to support the closure of single-shell tanks at the DOE's Hanford Site. As part of this effort, staff at PNNL were asked to develop release models for contaminants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. This report provides the information developed by PNNL

  14. Tank 241-B-203 Push Mode Core Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    Jo, J. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-05-16

    This Sampling and Analysis Plan (SAP) will identify characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements in accordance with the Tank Safety Screening Data Quality Objective (Babad and Redus 1994). This Data Quality Objective (DQO) is described in the Tank Characterization Plan (Jo, 1995) for tank 241-B-203 (B-203). This SAP will also identify procedures and requirements for collecting and characterizing samples from tank B-203 by the core sampling method.

  15. Project W-320, 241-C-106 sluicing HVAC calculations, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, J.W.

    1998-08-07

    This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following calculations: Exhaust airflow sizing for Tank 241-C-106; Equipment sizing and selection recirculation fan; Sizing high efficiency mist eliminator; Sizing electric heating coil; Equipment sizing and selection of recirculation condenser; Chiller skid system sizing and selection; High efficiency metal filter shielding input and flushing frequency; and Exhaust skid stack sizing and fan sizing.

  16. On a low intensity 241Am Compton spectrometer for measurement of electron momentum density

    Indian Academy of Sciences (India)

    B L Ahuja; N L Heda

    2007-05-01

    In this paper, a new design and construction of a low intensity (100 mCi) 241Am -ray Compton spectrometer is presented. The planar spectrometer is based on a small disc source with the shortest geometry. Measurement of the momentum density of polycrystalline Al is used to evaluate the performance of the new design. The measured profile is in good agreement with the existing theoretical data and our density functional calculations.

  17. Tank 241-C-107 vapor sampling and analysis tank characterization report

    Energy Technology Data Exchange (ETDEWEB)

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank 241-C-107. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  18. Tank 241-C-105 vapor sampling and analysis tank characterization report

    Energy Technology Data Exchange (ETDEWEB)

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank 241-C-105. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  19. Tank 241-T-107 vapor sampling and analysis tank characterization report

    Energy Technology Data Exchange (ETDEWEB)

    Huckaby, J.L.

    1995-05-31

    This report presents the details of the Hanford waste tank characterization study for tank 241-T-107. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedure that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank.

  20. Bolting sequence for attaching the container to the strong-back for 241SY101

    International Nuclear Information System (INIS)

    This bolting sequence is for attaching the container to the strong-back for Tank 241-SY-101. This supporting document includes information for the proper bolting sequence for attaching the container to the strong-back is found in supporting document WHC-SD-WM-DA-165 (WHC 1994a) and is in accordance with Standard Arch-Civil Design Criteria, Design Loads for Facilities (SDC 4.1) Safety Class 3

  1. Hanford Tank 241-C-106: Residual Waste Contaminant Release Model and Supporting Data

    Energy Technology Data Exchange (ETDEWEB)

    Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

    2005-06-03

    CH2M HILL is producing risk/performance assessments to support the closure of single-shell tanks at the DOE's Hanford Site. As part of this effort, staff at PNNL were asked to develop release models for contaminants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. This report provides the information developed by PNNL.

  2. Tank 241-TX-113 rotary mode core sampling and analysis plan

    International Nuclear Information System (INIS)

    This sampling and analysis plan (SAP) identities characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for push mode core samples from tank 241-TX-113 (TX-113). The Tank Characterization Technical Sampling Basis document identities Retrieval, Pretreatment and Immobilization as an issue that applies to tank TX-113. As a result, a 150 gram composite of solids shall be made and archived for that program. This tank is not on a Watch List

  3. Isolating 241Am from waste solutions containing Al, Ca, Fe, and Cr

    International Nuclear Information System (INIS)

    About 2.4 kg of 241Am contaminated with calcium and aluminum had been recovered from low-activity waste during recycle of 11% 240Pu. A process was developed and demonstrated to purify the americium before shipment as 241AmO2. The americium and some of the calcium were batch extracted into 50% TBP-n-paraffin from 2.2M Al(NO3)3 - 0.3M HNO3 solution in a canyon tank. Pregnant solvent was scrubbed first with 2.1M Al3+-0.3M Li+-6.7M NO3- and then with 7M LiNO3 to reduce the calcium content and to displace the aluminum. Americium was then stripped from the solvent with water and concentrated by evaporation. Before precipitating the americium with oxalic acid, the nitric acid was adjusted with NH4OH to yield a 1M NH4NO3 solution. Recovery across the batch extraction step was 97.8%, while 93% of the calcium and >99% of the aluminum was rejected. Recovery across precipitation averaged >96% while producing a product which was >99.3% pure 241AmO2. The major impurities were water, carbon, calcium, iron, and zinc

  4. Assessment of magnetite to remove Cs (Total) and Am-241 from radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Priscila; Lima, Josenilson B.; Bueno, Vanessa N.; Yamamura, Mitiko H.; Holland, Helber; Hiromoto, Goro; Potiens Junior, Ademar J.; Sakata, Solange K., E-mail: apotiens@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    Radioactive waste can affect human hea lt and the environment, thus their safe management has received considerable attention worldwide. Radioactive waste treatment is an important step in its management. Sorption technique is one of the most studied methods to reduce the volume of radioactive waste streams and it has been successfully used for treatment of radioactive liquid wastes. Herein, the experiments were performed using magnetite (Fe{sub 3}O{sub 4}) as adsorbents for removal the cesium and americium from different radioactive aqueous solution. An aqueous solution with 13.9 ppm of Cs-133 was stirred with 20-25 mg of magnetite and another solution of 117.94 Bq/mL Am-241 was stirred with 50 mg using the same adsorbent but in different contact times and pH. After the experiments the magnetite was removal using a super magnet and the solutions were analyzed by ICP-OES for Cs-133 and Am-241 remaining in solution was quantified by a gamma spectrometry. The results suggested that the biosorption process for Cs is more efficient at pH 6 and 30 minutes of contact time and for Am-241 the most efficient pH was also 6 and 40 min of contact time with 93% of removal of this radionuclide from the solution. (author)

  5. Selective Leaching of Chromium from Hanford Tank Sludge 241-U-108

    Energy Technology Data Exchange (ETDEWEB)

    Rapko, Brian M.; Vienna, John D.

    2002-09-09

    This study evaluated the oxidants permanganate, MnO4-, and peroxynitrite, ONOO-, as selective chromium-leaching agents from washed 241-U-108 tank sludge under varying conditions of hydroxide concentration, temperature, and time. The mass changes and final sludge compositions were evaluated using glass-property models to ascertain the relative impacts of the various oxidative alkaline leach conditions on the amount of borosilicate glass required to immobilize a given amount of washed 241-U-108 Hanford tank sludge. Only permanganate leaching removes sufficient chromium to make the chromium concentration in the oxidatively alkaline leached solids non-limiting. In the absence of added oxidants, continued washing or caustic leaching have no beneficial effects. Peroxynitrite addition reduces the amount of glass required to immobilize a given amount of washed 241-U-108 tank sludge by approximately a factor of two. Depending on the leach conditions and the exact chromium concentration limits, contact with alkaline permanganate solutions reduces the amount of immobilized high-level waste glass by a factor of 10 to 30.

  6. Plutonium, 90Sr and 241Am in human bones from southern and northeastern parts of Poland

    International Nuclear Information System (INIS)

    The paper presents the results of our study on 238Pu, 239Pu, 240Pu, 241Am and 90Sr concentration in human bones carried out on a set of 88 individual samples of central Europe origin. Bone tissue samples were retrieved under surgery while introducing hip joint implants. The conducted surgeries tend to cover either southern or northeastern parts of Poland. While for the southern samples only global fallout was expected to be seen, a mixed global and Chernobyl fallout were to be reflected in the others. Alpha spectrometry was applied to obtain activity concentration for 238Pu, 239+240Pu, 241Am, while liquid scintillation spectrometry for 90Sr and mass spectrometry to receive 240Pu/239Pu mass ratio. Surprisingly enough, and to the contrary to our expectations we could not see any significant differences in either Pu activity or Pu mass ratio between the studied populations. In both populations Chernobyl fraction proved marginal. The results on 90Sr and 241Am confirm similarities between the two examined groups. (author)

  7. PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION

    International Nuclear Information System (INIS)

    Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D and D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D and D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D and D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and Liability Act of 1980

  8. Tank characterization report for Double-Shell Tank 241-SY-102

    Energy Technology Data Exchange (ETDEWEB)

    DiCenso, A.T.; Amato, L.C. [Los Alamos Technical Associates, Inc., NM (United States); Winters, W.I. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-06-09

    This tank characterization report presents an overview of Double-Shell Tank 241-SY-102 (hereafter, Tank 241-SY-102) and its waste contents. It provides estimated concentrations and inventories for the waste components based on the latest sampling and analysis activities and background tank information. This report describes the results of three sampling events. The first core sample was taken in October 1988. The tank supernate and sludge were next core sampled in February and March of 1990 (Tingey and Sasaki 1995). A grab sample of the supernate was taken in March of 1994. Tank 241-SY-102 is in active service and can be expected to have additional transfers to and from the tank that will alter the composition of the waste. The concentration and inventory estimates reported in this document no longer reflect the exact composition of the waste but represent the best estimates based on the most recent and available data. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order Milestone M-44-08 (Ecology, EPA, DOE 1994).

  9. Characterization and Potential Remediation Approaches for Vadose Zone Contamination at Hanford 241-SX Tank Farm

    Energy Technology Data Exchange (ETDEWEB)

    Eberlein, Susan J.; Sydnor, Harold A.; Parker, Danny L.; Glaser, Danney R.

    2013-01-10

    Unplanned releases of radioactive and hazardous wastes have occurred at the 241-SX Tank Farm on the U.S. Department of Energy Hanford Site in southeast Washington State. Interim and long-term mitigation efforts are currently under evaluation for 241-SX Tank Farm. Two contiguous interim surface barriers have been designed for deployment at 241-SX Tank Farm to reduce future moisture infiltration; however, construction of the surface barriers has been deferred to allow testing of alternative technologies for soil moisture reduction and possibly contaminant source term reduction. Previous tests performed by other organizations at the Hanford Site have demonstrated that: vadose zone desiccation using large diameter (greater than 4 inch) boreholes is feasible; under certain circumstances, mobile contaminants may be removed in addition to water vapor; and small diameter (approximately 2 inch) boreholes (such as those placed by the direct push hydraulic hammer) can be used to perform vapor extractions. Evaluation of the previous work combined with laboratory test results have led to the design of a field proof-of-principle test to remove water and possibly mobile contaminants at greater depths, using small boreholes placed with the direct push unit.

  10. Engineer/constructor description of work for Tank 241-SY-102 retrieval system, project W-211, initial tank retrieval systems

    International Nuclear Information System (INIS)

    This document provides a description of work for the design and construction of a waste retrieval system for Tank 241-SY-102. The description of work includes a working estimate and schedule, as well as a narrative description and sketches of the waste retrieval system. The working estimate and schedule are within the established baselines for the Tank 241-SY-102 retrieval system. The technical baseline is provided in Functional Design Criteria, WHC-SD-W211-FDC-001, Revision 2

  11. Engineer/constructor description of work for Tank 241-SY-102 retrieval system, project W-211, initial tank retrieval systems

    Energy Technology Data Exchange (ETDEWEB)

    Rieck, C.A. [Westinghouse Hanford Co., Richland, WA (United States)

    1996-02-01

    This document provides a description of work for the design and construction of a waste retrieval system for Tank 241-SY-102. The description of work includes a working estimate and schedule, as well as a narrative description and sketches of the waste retrieval system. The working estimate and schedule are within the established baselines for the Tank 241-SY-102 retrieval system. The technical baseline is provided in Functional Design Criteria, WHC-SD-W211-FDC-001, Revision 2.

  12. Inorganic, radioisotopic and organic analysis of 241-AP-101 tank waste

    International Nuclear Information System (INIS)

    Battelle received five samples from Hanford waste tank 241-AP-101, taken at five different depths within the tank. No visible solids or organic layer were observed in the individual samples. Individual sample densities were measured, then the five samples were mixed together to provide a single composite. The composite was homogenized and representative sub-samples taken for inorganic, radioisotopic, and organic analysis. All analyses were performed on triplicate sub-samples of the composite material. The sample composite did not contain visible solids or an organic layer. A subsample held at 10 C for seven days formed no visible solids. The characterization of the 241-AP-101 composite samples included: (1) Inductively-coupled plasma spectrometry for Ag, Al, Ba, Bi, Ca, Cd, Cr, Cu, Fe, K, La, Mg, Mn, Na, Nd, Ni, P, Pb, Pd, Ru, Rh, Si, Sr, Ti, U, Zn, and Zr (Note: Although not specified in the test plan, As, B, Be, Co, Li, Mo, Sb, Se, Sn, Tl, V, W, and Y were also measured and reported for information only) (2) Radioisotopic analyses for total alpha and total beta activities, 3H, 14C, 60Co, 79Se, 90Sr, 99Tc as pertechnetate, 106Ru/Rh, 125Sb, 134Cs, 137Cs, 152Eu, 154Eu, 155Eu, 238Pu, 239+240Pu, 241Am, 242Cm, and 243+244Cm; (3) Inductively-coupled plasma mass spectrometry for 237Np, 239Pu, 240Pu, 99Tc, 126Sn, 129I, 231Pa, 233U, 234U, 235U, 236U, 238U, 241AMU, 242AMU, 243AMU, As, B, Be, Ce, Co, Cs, Eu, I, Li, Mo, Pr, Rb, Sb, Se, Ta, Te, Th, Tl, V, and W; (4) total U by kinetic phosphorescence analysis; (5) Ion chromatography for Cl, F, NO2, NO3, PO4, SO4, acetate, formate, oxalate, and citrate; (6) Density, inorganic carbon and organic carbon by two different methods, mercury, free hydroxide, ammonia, and cyanide. The 241-AP-101 composite met all contract limits (molar ratio of analyte to sodium or ratio of becquerels of analyte to moles of sodium) defined in Specification 7 for Envelope A. Except for a few cases, the characterization results met or surpassed the

  13. Inorganic, radioisotopic and organic analysis of 241-AP-101 tank waste

    Energy Technology Data Exchange (ETDEWEB)

    SK Fiskum; PR Bredt; JA Campbell; LR Greenwood; OT Farmer; GJ Lumetta; GM Mong; RT Ratner; CZ Soderquist; RG Swoboda; MW Urie; JJ Wagner

    2000-06-28

    Battelle received five samples from Hanford waste tank 241-AP-101, taken at five different depths within the tank. No visible solids or organic layer were observed in the individual samples. Individual sample densities were measured, then the five samples were mixed together to provide a single composite. The composite was homogenized and representative sub-samples taken for inorganic, radioisotopic, and organic analysis. All analyses were performed on triplicate sub-samples of the composite material. The sample composite did not contain visible solids or an organic layer. A subsample held at 10 C for seven days formed no visible solids. The characterization of the 241-AP-101 composite samples included: (1) Inductively-coupled plasma spectrometry for Ag, Al, Ba, Bi, Ca, Cd, Cr, Cu, Fe, K, La, Mg, Mn, Na, Nd, Ni, P, Pb, Pd, Ru, Rh, Si, Sr, Ti, U, Zn, and Zr (Note: Although not specified in the test plan, As, B, Be, Co, Li, Mo, Sb, Se, Sn, Tl, V, W, and Y were also measured and reported for information only) (2) Radioisotopic analyses for total alpha and total beta activities, {sup 3}H, {sup 14}C, {sup 60}Co, {sup 79}Se, {sup 90}Sr, {sup 99}Tc as pertechnetate, {sup 106}Ru/Rh, {sup 125}Sb, {sup 134}Cs, {sup 137}Cs, {sup 152}Eu, {sup 154}Eu, {sup 155}Eu, {sup 238}Pu, {sup 239+240}Pu, {sup 241}Am, {sup 242}Cm, and {sup 243+244}Cm; (3) Inductively-coupled plasma mass spectrometry for {sup 237}Np, {sup 239}Pu, {sup 240}Pu, {sup 99}Tc, {sup 126}Sn, {sup 129}I, {sup 231}Pa, {sup 233}U, {sup 234}U, {sup 235}U, {sup 236}U, {sup 238}U, {sup 241}AMU, {sup 242}AMU, {sup 243}AMU, As, B, Be, Ce, Co, Cs, Eu, I, Li, Mo, Pr, Rb, Sb, Se, Ta, Te, Th, Tl, V, and W; (4) total U by kinetic phosphorescence analysis; (5) Ion chromatography for Cl, F, NO{sub 2}, NO{sub 3}, PO{sub 4}, SO{sub 4}, acetate, formate, oxalate, and citrate; (6) Density, inorganic carbon and organic carbon by two different methods, mercury, free hydroxide, ammonia, and cyanide. The 241-AP-101 composite met all

  14. Monitoring gas retention and slurry transport during the transfer of waste from Tank 241-C-106 to Tank 241-AY-102

    International Nuclear Information System (INIS)

    The retained gas volume can be estimated by several methods. All of these methods have significant uncertainties, but together they form a preponderance of evidence that describes the gas retention behavior of the tank. The methods are (1) an increase in nonconvective layer thickness; (2) a waste surface level rise (surface level effect [SLE] model); (3) the barometric pressure effect (BPE model); (4) direct void measurement; and (5) the consequences of the transfer process. The nonconvective layer thickness can be determined with sufficient accuracy to describe the overall waste configuration by means of temperature profiles or densitometer indications. However, the presence of a nonconvective layer does not necessarily indicate significant gas retention, and small changes in layer thickness that could quantify gas retention cannot be detected reliably with the methods available. The primary value of this measurement is in establishing the actual open-quotes fluffing factorclose quotes for thermal calculations. Surface level rise is not a useful measure of gas retention in Tank 241-C-106 (C-106) since the waste level fluctuates with regular makeup water additions. In Tank 241-AY-102 (AY-102) with the existing ventilation system it should be possible to determine the gas retention rate within 30-60% uncertainty from the surface level rise, should a significant rise be observed. The planned ventilation system upgrades in AY- 102 will greatly reduce the exhaust flow and the headspace humidity, and the evaporation rate should be significantly lower when transfers begin. This could reduce the uncertainty in gas retention rate estimates to around ± 10%

  15. The potential for buoyant displacement gas release events in Tank 241-SY-102 after waste transfer from Tank 241-SY-101

    International Nuclear Information System (INIS)

    Tank 241-SY-101 (SY-101) is a double-shell, radioactive waste storage tank with waste that, before the recent transfer and water back-dilution operations, was capable of retaining gas and producing buoyant displacement (BD) gas release events (GREs). Some BD GREs caused gas concentrations in the tank headspace to exceed the lower flammability limit (LFL). A BD GRE occurs when a portion of the nonconvective layer retains enough gas to become buoyant, rises to the waste surface, breaks up, and releases some of its stored gas. The installation of a mixer pump in 1993 successfully mitigated gas retention in the settled solids layer in SY-101 and has since prevented BD GREs. However, operation of the mixer pump over the years caused gas retention in the floating crust layer and a corresponding accelerated waste level growth. The accelerating crust growth trend observed in 1997--98 led to initiation of sequences of waste removal and water back-dilutions in December 1999. Waste is removed from the mixed slurry layer in Tank SY-101 and transferred into Tank 241-Sy-102 (SY-102). Water is then added back to dissolve soluble solids that retain gas. The initial transfer of 89,500 gallons of SY-101 waste, diluted in-line at 0.94:1 by volume with water, to SY-102 was conducted in December 1999. The second transfer of 230,000 gallons of original SY-101 waste, diluted approximately 0.9:1, was completed in January 2000, and the third transfer of 205,500 gallons of original SY-101 waste diluted at 0.9:1 was completed in March 2000

  16. PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION

    Energy Technology Data Exchange (ETDEWEB)

    JOHNSTON GA

    2008-01-15

    Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D&D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D&D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and

  17. Effects of americium-241 and humic substances on Photobacterium phosphoreum: Bioluminescence and diffuse reflectance FTIR spectroscopic studies

    Science.gov (United States)

    Kamnev, Alexander A.; Tugarova, Anna V.; Selivanova, Maria A.; Tarantilis, Petros A.; Polissiou, Moschos G.; Kudryasheva, Nadezhda S.

    The integral bioluminescence (BL) intensity of live Photobacterium phosphoreum cells (strain 1883 IBSO), sampled at the stationary growth stage (20 h), was monitored for further 300 h in the absence (control) and presence of 241Am (an α-emitting radionuclide of a high specific activity) in the growth medium. The activity concentration of 241Am was 2 kBq l-1; [241Am] = 6.5 × 10-11 M. Parallel experiments were also performed with water-soluble humic substances (HS, 2.5 mg l-1; containing over 70% potassium humate) added to the culture medium as a possible detoxifying agent. The BL spectra of all the bacterial samples were very similar (λmax = 481 ± 3 nm; FWHM = 83 ± 3 nm) showing that 241Am (also with HS) influenced the bacterial BL system at stages prior to the formation of electronically excited states. The HS added per se virtually did not influence the integral BL intensity. In the presence of 241Am, BL was initially activated but inhibited after 180 h, while the system 241Am + HS showed an effective activation of BL up to 300 h which slowly decreased with time. Diffuse reflectance infrared Fourier transform (DRIFT) spectroscopy, applied to dry cell biomass sampled at the stationary growth phase, was used to control possible metabolic responses of the bacteria to the α-radioactivity stress (observed earlier for other bacteria under other stresses). The DRIFT spectra were all very similar showing a low content of intracellular poly-3-hydroxybutyrate (at the level of a few percent of dry biomass) and no or negligible spectroscopic changes in the presence of 241Am and/or HS. This assumes the α-radioactivity effect to be transmitted by live cells mainly to the bacterial BL enzyme system, with negligible structural or compositional changes in cellular macrocomponents at the stationary growth phase.

  18. Influence of organic fertilization on the sorption mechanisms of {sup 241} Am in tropical soils; A influencia da adubacao organica nos mecanismos de sorcao do {sup 241} Am em solos tropicais

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Tatiane Rocha

    2009-07-01

    In this work the mechanisms involved in the sorption of {sup 241}Am were investigated depending on the physicochemical properties of some Brazilian soils and on alterations promoted by organic amendment. This experimental study was conducted in a controlled area, where pots containing different kinds of soils (histisol, ferralsol and nitisol), with different organic amendment doses (without amendment; 2 kg m{sup -2} and 4 kg m{sup -2}) were artificially contaminated by radioactive solution water, which contained {sup 241}Am. Migration studies, distribution (or partition) coefficient (KJ), bioavailability and organic matter were carried out in these soils, with ar without organic amendment. In order to evaluate the effective bioavailability of radionuclides, radish (Raphanus sativus L.) was cultivated in these pots, and later the concentration of {sup 241}Am in radish's roots was measured. The main results show that {sup 241}Am tends to be strongly attached to organic matter and that organic amendment in tropical soils minimizes the radionuclide studied desorption. Also, distribution (or partition) coefficient values for {sup 241}Am were generated and these values are smaller than those ones determined for soils from temperate zones. Physical and chemical fractioning of organic matter were carried out. (author)

  19. SAFETY ANALYSIS FOR TANK 241-AZ-101 MIXER PUMP PROCESS TEST

    Energy Technology Data Exchange (ETDEWEB)

    HAMMOND DM; HARRIS JP; MOUETTE P

    1997-06-09

    This document contains the completed safety analysis which establishes the safety envelope for performing the mixer pump process test in Tank 241-AZ-101. This process test is described in TF-210-OTP-001. All equipment necessary for the mixer pump test has been installed by Project W-151. The purpose of this document is to describe and analyze the mixer pump test for Aging Waste Facility (AWF) Tank 241-AZ-101 and to address the 'yes/maybe' responses marked for evaluation questions identified in Unreviewed Safety Question Evaluation (USQE) TF-94-0266. The scope of this document is limited to the performance of the mixer pump test for Tank 241-AZ-101. Unreviewed Safety Question Determination (USQD) TF-96-0018 verified that the installation of two mixer pumps into Tank 241-AZ-101 was within the current Tank Waste Remediation System (TWRS) Authorization Basis. USQDs TF-96-0461, TF-96-0448, and TF-96-0805 verified that the installation of the in-tank video camera, thermocouples, and Ultrasonic Interface Level Analyzer (URSILLA), respectively, were within the current TWRS Authorization Basis. USQD TF-96-1041 verified that the checkout testing of the installed equipment was within the current TWRS Authorization Basis. Installation of the pumps and equipment has been completed. An evaluation of safety considerations associated with operation of the mixer pumps for the mixer pump test is provided in this document. This document augments the existing AWF authorization basis as defined in the Interim Safety Basis (Stahl 1997), and as such, will use the existing Interim Operational Safety Requirements (IOSRs) of Heubach 1996 to adequately control the mixer pump test. The hazard and accident analysis is limited to the scope and impact of the mixer pump test, and therefore does not address hazards already addressed by the current AWF authorization basis. This document does not evaluate removal of the mixer pumps. Safety considerations for removal of the pumps will be

  20. Dose distributions around cylindrical 241Am sources for a clinical intracavitary applicator

    International Nuclear Information System (INIS)

    Encapsulated, cylindrical sources containing 2, 5, and 8 Ci of 241Am have been designed and fabricated for intracavitary irradiation of uterine cancers. Exposure rates in air and dose rates in water around these sources have been measured using an ionization chamber and a lithium fluoride thermoluminescent dosimetry system. Dose rates in water at a distance of 2.5 cm from the source center along a direction transverse to the source axis were found to be 10.4, 24.3, and 23.3 cGy/h for the 2-, 5-, and 8-Ci sources, respectively, using an ionization chamber. Under the same conditions, the thermoluminescent dosimetry system yielded the values of 10.3, 23.1, and 22.3 cGy/h. It was observed that the ratio of dose-to-water and exposure in air is sensitive to the scattering geometry and source geometry in the case of 241Am photons. This ratio was found to increase substantially as conditions of full scattering were approached. A three-dimensional integration model was employed for the determination of dose distributions around these sources. Results of this dose computation model have been compared against the measured data and were found to be in good agreement with each other. Average deviations of calculated data from measured data were in the range of 0.2 to 0.5 cGy/h and larger deviations were observed in the paraxial region, where the effects of oblique filtration are more severe. Computed dose rate tables were employed as reference source data in a modified version of a commercial treatment planning system in order to develop a facility for clinical dosimetry of 241Am intracavitary applications

  1. Scattering correction for {sup 241}Am-Be calibration of an individual albedo neutron dosemeter

    Energy Technology Data Exchange (ETDEWEB)

    Freitas, Bruno M.; Martins, Marcelo M.; Patrao, Karla C.S.; Fonseca, Evaldo S.; Pereira, Walsan W.; Mauricio, Claudia L.P., E-mail: brunofreitas@ird.gov.br, E-mail: marcelo@ird.gov.br, E-mail: karla@ird.gov.br, E-mail: evaldo@ird.gov.br, E-mail: walsan@ird.gov.br, E-mail: claudia@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The Instituto de Radioprotecao e Dosimetria (IRD), RJ, Brazil, runs an individual albedo neutron dosemeter service. The albedo dosemeter response varies strongly with neutron energy, falling down very steeply in the energy range of radionuclide neutron source. Moreover the largest number of workers exposed to neutrons in Brazil is exposed to scattered and moderated {sup 241}Am-Be fields. Therefore a study of the response of albedo dosemeter due to neutron scattering from {sup 241}Am-Be source is very important for IRD albedo dosemeter calibration. In this work, it has been evaluated the scattering neutron correction in the calibration of the albedo dosemeter from a {sup 241}Am-Be source in the Low Scattering Laboratory of the Neutron Laboratory of the Brazilian National Metrology Laboratory of Ionizing Radiations, where IRD albedo neutron dosemeter is calibrated. It was used the shadow cone technique and Bonner sphere spectrometer with the BUMS (Bonner sphere Unfolding Made Simple) unfolding software. Using the results obtained for the values of H{sub p}(10) and the reading of IRD albedo neutron dosemeter, new calibration factors, considering the scattering in the laboratory, were calculated. These calculated factors for irradiation without the shadow cone are approximately the same for both studied distances and similar with the one calculated without taking in account the scattering contribution for a source-detector distance of 1.00 m (7% difference), but about 20% higher at 2.25 m. For the neutron scattered beam (with shadow cone), the calibration factor values are about 30% and 25% lower, respectively, for 1.00 and 2.25 m. (author)

  2. Action plan for response to excessive temperature in high heat source waste tank 241-C-106 at the Hanford site. Revision 1

    International Nuclear Information System (INIS)

    This action plan identifies the responses that shall be implemented if anomalies in temperature measurements, or conditions that could lead to temperature anomalies (such as a leaking tank), are observed in tank 241-C-106 of the Hanford site C Tank Farm. This plan also summarizes (1) the criteria and specification limits required for ensuring that tank 241-C-106 is maintained in a safe condition; (2) the responsible organizations for tank 241-C-106; and (3) response actions to prevent or mitigate safety concerns. The main safety concern unique to tank 241-C-106 is the temperature rise due to heat generation by the waste content

  3. Evaluation of 241-AZ tank farm supporting phase 1 privatization waste feed delivery

    Energy Technology Data Exchange (ETDEWEB)

    CARLSON, A.B.

    1998-11-19

    This evaluation is one in a series of evaluations determining the process needs and assessing the adequacy of existing and planned equipment in meeting those needs at various double-shell tank farms in support of Phase 1 privatization. A number of tank-to-tank transfers and waste preparation activities are needed to process and feed waste to the private contractor in support of Phase 1 privatization. The scope of this evaluation is limited to process needs associated with 241-AZ tank farm during the Phase 1 privatization.

  4. Tank 241-AN-103, cores 166 and 167 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1997-05-15

    This document is the analytical laboratory report for tank 241-AN-103 [Hydrogen Watch Listed] push mode core segments collected between September 13, 1996 and September 23, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-AN-103 Push Mode Core Sampling and Analysis Plan (TSAP), the Safety Screening Data Quality Objective (DQO) and the Flammable Gas Data Quality Objective (DQO). The analytical results are included in the data summary table. The raw data are included in this document. None of the samples submitted for Total Alpha Activity (AT), Total Organic Carbon (TOC) and Plutonium analyses exceeded notification limits as stated in the TSAP. One sample submitted for Differential Scanning Calorimetry (DSC) analysis exceeded the notification limit of 480 Joules/g (dry weight basis) as stated in the Safety Screening DQO. Appropriate notifications were made. Statistical evaluation of results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. Appearance and Sample Handling Attachment 1 is a cross reference to relate the tank farm identification numbers to the 222-S Laboratory LabCore/LIMS sample numbers. The subsamples generated in the laboratory for analyses are identified in these diagrams with their sources shown. The diagrams identifying the core composites are also included. Core 166 Nineteen push mode core segments were removed from tank 241-AN-103 riser 12A between September 13, 1996 and September 17, 1996. Segments were received by the 222-S Laboratory between September 20, 1996 and September 30, 1996. Table 2 summarizes the extrusion information. Selected segments (2, 5 and 14) were sampled using the Retained Gas Sampler (RGS) and extruded by the Process Chemistry and Statistical Analysis Group. Core 167 Eighteen push mode core segments were removed from tank 241-AN-103 riser 21A between September 18, 1996 and September 23, 1996. Tank Farm Operations were

  5. Acceptance test report: Field test of mixer pump for 241-AN-107 caustic addition project

    International Nuclear Information System (INIS)

    The field acceptance test of a 75 HP mixer pump (Hazleton serial number N-20801) installed in Tank 241-AN-107 was conducted from October 1995 thru February 1996. The objectives defined in the acceptance test were successfully met, with two exceptions recorded. The acceptance test encompassed field verification of mixer pump turntable rotation set-up and operation, verification that the pump instrumentation functions within established limits, facilitation of baseline data collection from the mixer pump mounted ultrasonic instrumentation, verification of mixer pump water flush system operation and validation of a procedure for its operation, and several brief test runs (bump) of the mixer pump

  6. Tank 241-TX-104, cores 230 and 231 analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the analytical laboratory report for tank 241-TX-104 push mode core segments collected between February 18, 1998 and February 23, 1998. The segments were subsampled and analyzed in accordance with the Tank 241-TX-104 Push Mode Core Sampling and Analysis Plan (TSAP) (McCain, 1997), the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO) (Turner, et al., 1995) and the Safety Screening Data Quality Objective (DQO) (Dukelow, et.al., 1995). The analytical results are included in the data summary table. None of the samples submitted for Differential Scanning Calorimetry (DSC) and Total Alpha Activity (AT) exceeded notification limits as stated in the TSAP. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group in accordance with the Memorandum of Understanding (Schreiber, 1997) and are not considered in this report. Appearance and Sample Handling Attachment 1 is a cross reference to relate the tank farm identification numbers to the 222-S Laboratory LabCore/LIMS sample numbers. The subsamples generated in the laboratory for analyses are identified in these diagrams with their sources shown. Core 230: Three push mode core segments were removed from tank 241-TX-104 riser 9A on February 18, 1998. Segments were received by the 222-S Laboratory on February 19, 1998. Two segments were expected for this core. However, due to poor sample recovery, an additional segment was taken and identified as 2A. Core 231: Four push mode core segments were removed from tank 241-TX-104 riser 13A between February 19, 1998 and February 23, 1998. Segments were received by the 222-S Laboratory on February 24, 1998. Two segments were expected for this core. However, due to poor sample recovery, additional segments were taken and identified as 2A and 2B. The TSAP states the core samples should be transported to the laboratory within three

  7. Solid Phase Characterization of Tank 241-AY-102 Annulus Space Particulate

    Energy Technology Data Exchange (ETDEWEB)

    Cooke, G. A.

    2013-01-30

    The Special Analytical Studies Group at the 222-S Laboratory (222-S) examined the particulate recovered from a series of samples from the annular space of tank 241-AY-102 (AY-102) using solid phase characterization (SPC) methods. These include scanning electron microscopy (SEM) using the ASPEX®1 scanning electron microscope, X-ray diffraction (XRD) using the Rigaku®2 MiniFlex X-ray diffractometer, and polarized light microscopy (PLM) using the Nikon®3 Eclipse Pol optical microscope. The SEM is equipped with an energy dispersive X-ray spectrometer (EDS) to provide chemical information.

  8. 241-U-701 new compressor building and instrument air piping analyses

    International Nuclear Information System (INIS)

    Building anchorage analysis is performed to qualify the design of the new compressor building foundation given in the ECN ''241-U-701 New Compressor Building.'' Recommendations for some changes in the ECN are made accordingly. Calculations show that the 6-in.-slab is capable of supporting the pipe supports, and that the building foundation, air compressor and dryer anchorage, and electric rack are adequate structurally. Analysis also shows that the instrument air piping and pipe supports for the compressed air system meet the applicable code requirements and are acceptable. The building is for the U-Farm instrument air systems

  9. Evaluation of 241-AZ tank farm supporting phase 1 privatization waste feed delivery

    International Nuclear Information System (INIS)

    This evaluation is one in a series of evaluations determining the process needs and assessing the adequacy of existing and planned equipment in meeting those needs at various double-shell tank farms in support of Phase 1 privatization. A number of tank-to-tank transfers and waste preparation activities are needed to process and feed waste to the private contractor in support of Phase 1 privatization. The scope of this evaluation is limited to process needs associated with 241-AZ tank farm during the Phase 1 privatization

  10. Test Report for Permanganate and Cold Strontium Strike for Tank 241-AN-102

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, James B.; Huber, Heinz J.; Smalley, Colleen S.

    2013-11-27

    Tanks 241-AN-102 and 241-AN-107 supernatants contain soluble Sr-90 and transuranic elements that require removal prior to vitrification to comply with the Waste Treatment and Immobilization Plant immobilized low-activity waste specification (WTP Contract, DE-AC27-01RV 14136, Specification 2.2.2.8, "Radionuclide Concentration Limitations") and the U.S. Nuclear Regulatory Commission provisional agreement on waste incidental to reprocessing (letter, Paperiello, C. J., "Classification of Hanford Low-Activity Tank Waste Fraction"). These two tanks have high concentrations of organics and organic complexants and are referred to as complexant concentrate tanks. A precipitation process using sodium permanganate (NaMnO{sub 4}) and strontium nitrate (Sr(NO{sub 3}){sub 2}) was developed and tested with tank waste samples to precipitate Sr-90 and transuranic elements from the supernate (PNWD-3141, Optimization of Sr/TRU Removal Conditions with Samples of AN-102 Tank Waste). Testing documented in this report was conducted to further evaluate the use of the strontium nitrate/sodium permanganate process in tank farms with a retention time of up to 12 months. Previous testing was focused on developing a process for deployment in the ultrafiltration vessels in the Waste Treatment and Immobilization Plant. This environment is different from tank farms in two important ways: the waste is diluted in the Waste Treatment and Immobilization Plant to ~5.5 M sodium, whereas the supernate in the tank farms is ~9 M Na. Secondly, while the Waste Treatment and Immobilization Plant allows for a maximum treatment time of hours to days, the in-tank farms treatment of tanks 241-AN102 and 241-AN-107 will result in a retention time of months (perhaps up to12 months) before processing. A comparative compilation of separation processes for Sr/transuranics has been published as RPP-RPT-48340, Evaluation of Alternative Strontium and Transuranic Separation Processes. This report also listed the testing

  11. Inorganic, Radioisotopic, and Organic Analysis of 241-AP-101 Tank Waste

    Energy Technology Data Exchange (ETDEWEB)

    Fiskum, S.K.; Bredt, P.R.; Campbell, J.A.; Farmer, O.T.; Greenwood, L.R.; Hoppe, E.W.; Hoopes, F.V.; Lumetta, G.J.; Mong, G.M.; Ratner, R.T.; Soderquist, C.Z.; Steele, M.J.; Swoboda, R.G.; Urie, M.W.; Wagner, J.J.

    2000-10-17

    Battelle received five samples from Hanford waste tank 241-AP-101, taken at five different depths within the tank. No visible solids or organic layer were observed in the individual samples. Individual sample densities were measured, then the five samples were mixed together to provide a single composite. The composite was homogenized and representative sub-samples taken for inorganic, radioisotopic, and organic analysis. All analyses were performed on triplicate sub-samples of the composite material. The sample composite did not contain visible solids or an organic layer. A subsample held at 10 C for seven days formed no visible solids.

  12. DEM L241, A SUPERNOVA REMNANT CONTAINING A HIGH-MASS X-RAY BINARY

    Energy Technology Data Exchange (ETDEWEB)

    Seward, F. D. [Smithsonian Astrophysical Observatory, 60 Garden Street, Cambridge, MA 02138 (United States); Charles, P. A. [School of Physics and Astronomy, University of Southampton, Highfield, Southampton SO17 1BJ (United Kingdom); Foster, D. L. [South African Astronomical Observatory, P.O. Box 9, Observatory 7935, Cape Town (South Africa); Dickel, J. R.; Romero, P. S. [Department of Physics and Astronomy, University of New Mexico, 1919 Lomas Boulevard NE, Albuquerque, NM 87131 (United States); Edwards, Z. I.; Perry, M.; Williams, R. M. [Department of Earth and Space Sciences, Columbus State University, Coca Cola Space Science Center, 701 Front Avenue, Columbus, GA 31901 (United States)

    2012-11-10

    A Chandra observation of the Large Magellanic Cloud supernova remnant DEM L241 reveals an interior unresolved source which is probably an accretion-powered binary. The optical counterpart is an O5III(f) star making this a high-mass X-ray binary with an orbital period likely to be of the order of tens of days. Emission from the remnant interior is thermal and spectral information is used to derive density and mass of the hot material. Elongation of the remnant is unusual and possible causes of this are discussed. The precursor star probably had mass >25 M {sub Sun}.

  13. An assessment of the potential for a steam bump in Hanford Waste Tank 241-C-106

    International Nuclear Information System (INIS)

    This document is a preliminary assessment of the potential for a ''steam bump'' in Tank 241-C-106. The assessment is based on currently available data from significant transients which occurred in Tank C-106. Recommendations are made for additional data needs to clarify the current behavior of this tank. General criteria are provided for making decisions on removing or returning to work restrictions on Tank Farm operations. Also provided are additional actions which should be taken on C-106 to manage tank heat removal

  14. Tank characterization report for double-shell tank 241-AW-105

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, L.M.

    1997-06-05

    One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for double-shell tank 241-AW-105. The objectives of this report are to use characterization data in response to technical issues associated with tank 241-AW-105 waste; and to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order milestone Characterization. information presented in this report originated from sample analyses and known historical sources. While only the results of a recent sampling event will be used to fulfill the requirements of the data quality objectives (DQOs), other information can be used to support or question conclusions derived from these results. Historical information for tank 241-AW-105 is provided in Appendix A, including surveillance information, records pertaining to waste transfers and tank operations, and expected tank contents derived from a process knowledge model. The recent sampling event listed, as well as pertinent sample data obtained before 1996, are summarized in Appendix B along with the sampling results. The results of the 1996 grab sampling event satisfied the data requirements specified in the sampling and analysis plan (SAP) for this tank. In addition, the tank headspace flammability was measured, which addresses

  15. Electronic structure of polycrystalline Cd metal using {sup 241}Am radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Dhaka, M. S., E-mail: msdhaka75@yahoo.co.in [Department of Physics, University College of Science, M. L. S. University, Udaipur-313001 (India); Sharma, G. [Department of Pure and Applied Physics, University of Kota, Kota-324005 (India); Mishra, M. C. [Department of Physics, R. R. M. Government College, Jhunjhunu-333001 (India); Sharma, B. K. [Department of Physics, University of Rajasthan, Jaipur-302004 (India)

    2014-04-24

    Electronic structure study of the polycrystalline cadmium metal is reported. The experimental measurement is undertaken on a polycrystalline sheet sample using 59.54 keV radioisotope of {sup 241}Am. These results are compared with the ab initio calculations. The theoretical calculations are performed using linear combination of atomic orbitals (LCAO) method employing the density functional theories (DFT) and Hartree-Fock (HF) and augmented plane wave (APW) methods. The spherically averaged APW and LCAO based theoretical Compton profiles are in good agreement with the experimental measurement however the APW based theoretical calculations show best agreement.

  16. Performance comparison of an 241Am-Be neutron source-based PGNAA setup with the KFUPM PGNAA setup

    International Nuclear Information System (INIS)

    Monte Carlo calculations have been carried out to compare the performance of an 241Am-Be neutron source-based prompt gamma neutron activation analysis (PGNAA) setup with that of the 2.8 MeV neutron-based PGNAA setup at King Fahd University of Petroleum and Minerals (KFUPM) to analyze Portland cement samples. This work is a part of a wide Monte Carlo studies being conducted at KFUPM in search of a more efficient neutron source for its 2.8 MeV neutrons, from the D(d,n) reaction, based PGNAA facility. In this study an 241Am-Be neutron source-based PGNAA setup was simulated. For comparison, the diameter of a cylindrical external moderator of the 241Am-Be neutron source, based PGNAA setup, was assumed to be similar to that used in the KFUPM PGNAA setup. It was revealed that although the optimum geometry of the 241Am-Be neutron source-based setup is similar to that of the KFUPM PGNAA facility, the performance of the 241Am-Be neutron source-based setup is slightly poorer than that of the 2.8 MeV neutron-based setup. (author)

  17. Study of the {sup 241}Am in fresh water. Application to Rh e ecosystem; Etude des transferts de L'{sup 241}Am en eau douce. Application a l'ecosysteme rhodanien

    Energy Technology Data Exchange (ETDEWEB)

    Veran, M.P.; Garnier-Laplace, J.; Baudin, J.P. [CEA Cadarache, Inst. de Protection et de Surete Nucleaire (IPSN), 13 - Saint-Paul-lez-Durance (France)

    1999-07-01

    The {sup 241}Am transfers are quantified in the heart of a model ecosystem, representative of the aquatic medium downstream the site of Marcoule. The dominating phenomenon of adsorption governs the distribution of Am in the ecosystem. The capacities of bioaccumulation are more important for the primary producers, the zooplankton and the filter molluscs. The results show the key role of the benthic fauna able to mobilize {sup 241}Am fixed on the sediment and the importance of the feeding to explain the contamination of the omnivorous fishes. The dreissensia can be used as bio indicator of radio contamination by transuranium elements. (N.C.)

  18. The potential of coconut fibers in raw and treated forms to remove {sup 241}Am from aqueous solutions

    Energy Technology Data Exchange (ETDEWEB)

    Fonseca, Heverton C.O.; Jesus, Nella N.M. de; Nobre, Vanessa B.; Potiens Junior, Ademar; Sakata, Solange K., E-mail: sksakata@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    In the Radioactive Waste Management (GRR) at the Nuclear and Energy Research Institute (IPEN/CNEN-SP) vegetal biomass has been studied as adsorbent to remove radioisotopes from radioactive liquid wastes as part of the radioactive waste treatment program. In this work coconuts fiber was evaluate as biosorbent to remove {sup 241}Am from aqueous solutions and many different parameters were studied such as particle size (35 and 80 mesh) and contact time (between 5 and 60 minutes). In order to evaluate if the treated biomass could remove more {sup 241}Am the experiments were also performed using raw biomass and treated with H{sub 2}O{sub 2} in basic conditions. When the experiment was carried out using raw coconuts fiber with 80 mesh, neutral conditions after 5 minutes of contact time 99% of the radionuclide was removed from the aqueous solution. This result shows the potential of this biomass to remove {sup 241}Am from radioactive liquid wastes. (author)

  19. Development of the MICROMEGAS Detector for Measuring the Energy Spectrum of Alpha Particles by using a 241-Am Source

    CERN Document Server

    Kim, Do Yoon; Shin, Jae Won; Park, Tae-Sun; Hong, Seung-Woo; Andriamonje, Samuel; Kadi, Yacine; Tenreiro, Claudio

    2016-01-01

    We have developed MICROMEGAS (MICRO MEsh GASeous) detectors for detecting {\\alpha} particles emitted from an 241-Am standard source. The voltage applied to the ionization region of the detector is optimized for stable operation at room temperature and atmospheric pressure. The energy of {\\alpha} particles from the 241-Am source can be varied by changing the flight path of the {\\alpha} particle from the 241 Am source. The channel numbers of the experimentally-measured pulse peak positions for different energies of the {\\alpha} particles are associated with the energies deposited by the alpha particles in the ionization region of the detector as calculated by using GEANT4 simulations; thus, the energy calibration of the MICROMEGAS detector for {\\alpha} particles is done. For the energy calibration, the thickness of the ionization region is adjusted so that {\\alpha} particles may completely stop in the ionization region and their kinetic energies are fully deposited in the region. The efficiency of our MICROMEGA...

  20. 自发性气胸241例临床分析%Clinical analysis of 241 cases with spontaneous pneumothorax

    Institute of Scientific and Technical Information of China (English)

    李红娟; 陈维亚

    2001-01-01

    目的探讨自发性气胸的临床特点、处理及预后。方法收集1995年1月~2001年3月杭州市第一人民医院胸外科收治的自发性气胸病例共241例,对其临床资料进行回顾性调查分析。结果原发性自发性气胸发生率为69%,继发性自发性气胸发生率31%;在原发性自发性气胸中,16~45岁占85%,46~81岁占15%;在继发性自发性气胸中,16~45岁占13.5%,46~81岁占86.5%自发性气胸的发生中,男性较女性多见,男性占89%,女性占11%,男女比例为8.2∶1。结论自发性气胸中以原发性自发性气胸为多见,且多发于青壮年,继发性自发性气胸相对较少,多发于中老年;自发性气胸中,男性较女性多见。%Objective To investigate clinical characters,treatment and prognosis of spontaneous pneumothorax.Method 241 patients with spontaneous pneumothorax who were treated in Hangzhou First Hospital during Jan.1995-Mar.2001 were collected and their clinical materials were retrospectively analyzed.Result The incidence of the primary spontaneous pneumothorax was 69% and the incidence of the secondary spontaneous pneumothorax was 31%.Among the cases with primary spontaneous pneumothorax,85% of all cases were from 16 to 45 years old and 15% were from 46 to 81 years old;Among the cases with secondary spontaneous pneumothorax,13.5% were from 14 to 45 years old and 86.5% were from 46 to 81 years old.The male patients with spontaneous pneumothorax(89%) were more than the female patients (11%) and the ratio of the male to female patients was 8.2∶1.Conclusion The incidence of primary spontaneous pneumothorax was higher than that of the secondary spontaneous pneumothorax.

  1. Tank characterization report for Single-Shell Tank 241-T-107

    Energy Technology Data Exchange (ETDEWEB)

    Valenzuela, B.D.; Jensen, L.

    1994-09-01

    Single shell tank 241-T-107 is a Hanford Site Ferrocyanide Watch List tank most recently sampled in March 1993. Analyses of materials obtained from tank T-107 were conducted to support the Ferrocyanide Unreviewed Safety Question (USQ) and the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-06 as well as Milestones M-44-05 and M-44-07. Characterization of the tank waste T-107 will support the ferrocyanide safety issue in order to classify the tank as safe, conditionally safe, or unsafe. This tank characterization report expands on the data found in Ferrocyanide Safety Program: Data Interpretation Report for Tank 241-T-107 Core Samples. Analysis of core samples obtained from tank T-107 strongly indicate the cyanide and oxidizer (nitrate/nitrite) concentrations in the tank waste are not significant enough to support a self-sustaining exothermic reaction. Therefore, the contents of tank T-107 present no imminent threat to the workers at the Hanford Site, the public, or the environment. Because the possibility of an exothermic reaction is remote, the consequences of an accident scenario, as proposed by the General Accounting Office, are not applicable.

  2. Tank characterization report for single-shell tank 241-C-106

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.D.

    1996-09-25

    This tank characterization report summarizes information on the historical uses, current status, and sampling and analysis results of waste stored in single-shell underground tank 241-C-106. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09 (Ecology et al. 1996). Tank 241-C-106 is the only tank on the High-Heat Load Watch List. As a result of the analyses addressed by this report, the supernate and upper 60 percent of the sludge in the tank do not pose any safety concerns in addition to the high-heat load issue based on the decision limits of the safety screening data quality objective (DQO) (Dukelow et al. 1995). The lower 40 percent of the sludge was not sampled; therefore, no statements regarding the safety of this waste can be made. A portion of the tank sludge is scheduled to be retrieved in fiscal year 1997 in order to mitigate the high-heat load in the tank.

  3. Safety evaluation for packaging transportation of equipment for tank 241-C-106 waste sluicing system

    Energy Technology Data Exchange (ETDEWEB)

    Calmus, D.B.

    1994-08-25

    A Waste Sluicing System (WSS) is scheduled for installation in nd waste storage tank 241-C-106 (106-C). The WSS will transfer high rating sludge from single shell tank 106-C to double shell waste tank 241-AY-102 (102-AY). Prior to installation of the WSS, a heel pump and a transfer pump will be removed from tank 106-C and an agitator pump will be removed from tank 102-AY. Special flexible receivers will be used to contain the pumps during removal from the tanks. After equipment removal, the flexible receivers will be placed in separate containers (packagings). The packaging and contents (packages) will be transferred from the Tank Farms to the Central Waste Complex (CWC) for interim storage and then to T Plant for evaluation and processing for final disposition. Two sizes of packagings will be provided for transferring the equipment from the Tank Farms to the interim storage facility. The packagings will be designated as the WSSP-1 and WSSP-2 packagings throughout the remainder of this Safety Evaluation for Packaging (SEP). The WSSP-1 packagings will transport the heel and transfer pumps from 106-C and the WSSP-2 packaging will transport the agitator pump from 102-AY. The WSSP-1 and WSSP-2 packagings are similar except for the length.

  4. Tank Characterization report for single-shell tank 241-SX-103

    Energy Technology Data Exchange (ETDEWEB)

    WILMARTH, S.R.

    1999-05-20

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-103 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for fiscal year 1999'' (Adams et al. 1998).

  5. Tank characterization report for single-shell tank 241-T-105

    International Nuclear Information System (INIS)

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-105. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-105 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ''issue characterization deliverables consistent with the waste information requirements documents developed for 1998''

  6. Measurement of thermal neutron cross section for {sup 241}Am(n,f) reaction

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Katsuhei; Yamamoto, Shuji; Fujita, Yoshiaki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.; Miyoshi, Mitsuharu; Kimura, Itsuro; Kanno, Ikuo; Shinohara, Nobuo

    1997-03-01

    Making use of a standard neutron spectrum field with a pure Maxwellian distribution, the thermal neutron cross section for the {sup 241}Am(n,f) reaction has been measured relative to the reference value of 586.2b for the {sup 235U}(n,f) reaction. For the present measurement, electrodeposited layers of {sup 241}Am and {sup 235}U have been employed as back-to-back type double fission chambers. The present result at neutron energy of 0.0253 eV is 3.15 {+-} 0.097b. The ENDF/B-VI data is in good agreement with the present value, while the JENDL-3.2 data is lower by 4.2%. The evaluated data in JEF-2.2 and by Mughabghab are higher by 0.9% and 1.6%, respectively than the present result. The ratios of the earlier experimental data to the present value are distributed between 0.89 and 1.02. (author)

  7. Tank characterization report for single-shell tank 241-U-106

    International Nuclear Information System (INIS)

    One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-U-106. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-U-106 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 of this report summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations regarding safety status and additional sampling. The appendixes contain supporting data and information. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ikology et al. 1996), Milestone M-44-10

  8. Neutron capture and (n,2n) measurements on {sup 241}Am

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, D.J.; Jandel, M.; Bredeweg, T.A.; Bond, E.M.; Clement, R.R.; Couture, A.; Haight, R.C.; O' Donnell, J.M.; Reifarth, R.; Rundberg, R.S.; Ullmann, J.L.; Wilhelmy, J.B.; Wouters, J.M. [Los Alamos National Laboratory, NM (United States); Tonchev, A.P.; Hutcheson, A.; Angell, C.T.; Crowell, A.S.; Fallin, B.; Hammond, S.; Howell, C.R.; Karowowski, H.J.; Kelley, J.H.; Pedroni, R.; Tornow, W. [Triangle Univ. Nuclear Laboratory, Durham, NC (United States); Macri, R.A.; Agvaanluvsan, U.; Becker, J.A.; Dashdorj, D.; Stoyer, M.A.; Wu, C.Y. [Lawrence Livermore National Laboratory, Livermore, CA (United States)

    2008-07-01

    We report on a set of neutron-induced reaction measurements on {sup 241}Am which are important for nuclear forensics and advanced nuclear reactor design. Neutron capture measurements have been performed on the DANCE detector array at the Los Alamos Neutron Scattering Center (LANSCE). In general, good agreement is found with the most recent data evaluations up to an incident neutron energy of about 300 keV where background limits the measurement. Using mono-energetic neutrons produced in the {sup 2}H(d,n){sup 3}He reaction at the Triangle Universities Nuclear Laboratory (TUNL), we have measured the {sup 241}Am(n,2n) excitation function from 7.6 to 14.5 MeV using the activation method. Good agreement is found with previous measurements, with the exception of the three data points reported by Perdikakis et al. around 11 MeV, where we obtain a much lower cross section that is more consistent with theoretical estimates. (authors)

  9. Project management plan for Project W-320, Tank 241-C-106 sluicing. Revision 2

    International Nuclear Information System (INIS)

    A major mission of the US Department of Energy (DOE) is the permanent disposal of Hanford Site defense wastes by utilizing safe, environmentally acceptable, and cost-effective disposal methods that meet applicable regulations. The Tank Waste Remediation System (TWRS) Program was established at the Hanford Site to manage and control activities specific to the remediation of safety watch list tanks, including high-heat-producing tanks, and for the ultimate characterization, retrieval, pretreatment, and disposal of the low- and high-level fractions of the tank waste. Project W-320, Tank 241-C-106 Sluicing, provides the methodology, equipment, utilities, and facilities necessary for retrieving the high-heat waste from single-shell tank (SST) 24-C-106. Project W-320 is a fiscal year (FY) 1993 expense-funded major project, and has a design life of 2 years. Retrieval of the waste in tank 241-C-106 will be accomplished through mobilization of the sludge into a pumpable slurry using past-practice sluicing. The waste is then transferred directly to a double-shell tank for interim storage, subsequent pretreatment, and eventual disposal. A detailed description of the management organization and responsibilities of all participants is presented in this document

  10. Ultrasonic Examination of Double-Shell Tank 241-AP-107 Examination Completed February 2008

    Energy Technology Data Exchange (ETDEWEB)

    Pardini, Allan F.; Weier, Dennis R.; Anderson, Kevin K.

    2008-09-29

    AREVA Federal Services LLC (AFS), under a contract from CH2M HILL Hanford Group (CH2M HILL), has performed an ultrasonic examination of selected portions of Double-Shell Tank 241-AP-107. The purpose of this examination was to provide information that could be used to evaluate the integrity of the wall of the primary tank. The requirements for the ultrasonic examination of Tank 241-AP-107 were to detect, characterize (identify, size, and locate), and record measurements made of any wall thinning, pitting, or cracks that might be present in the wall of the primary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plan (ETP), RPP-Plan-34301 (Castleberry 2007) and summarized on page 1 of this document, are to be reported to CH2M HILL and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M HILL, all data is to be recorded on electronic media and paper copies of all measurements are provided to PNNL for third-party evaluation. PNNL is responsible for preparing a report(s) that describes the results of the AFS ultrasonic examinations.

  11. Incidence of liver tumors in beagles with body burdens of 239Pu or 241Am

    International Nuclear Information System (INIS)

    Tetravalent 239Pu or trivalent 241Am in a citrate buffer, given via a single intravenous injection to beagles, induced very pronounced liver changes, usually at relatively long postinjection times. The lesions consisted of cell injury or cell necrosis which was followed by nodular hyperplasia and a significant incidence of primary liver tumors. The most frequent neoplasm was the bile duct adenoma, followed by the bile duct carcinoma. A lesser number of sarcomas were also induced, especially fibrosarcomas. The number of hepatic cell tumors was low. An abnormally high incidence of both hyperplastic nodules and primary liver tumors occurred at long postinjection times and at average doses extending down to ∼10 rads. The various nodular lesions and liver tumors frequently occurred as incidental findings in dogs dying from other causes, especially bone cancer. In comparison to bone neoplasia, the liver was a much less important target organ in the high-dose level groups, but in some of the low-dose groups, especially in the 241Am groups, the risk of radiation-induced liver cancer was approximately equal to or exceeded the risk of skeletal tumors. However, in any projection of the risks observed in this animal model to man, one should be mindful that the beagle skeleton is approximately 25 times more sensitive to radiation-induced bone neoplasia than is the human skeleton (Mays et al., 1976) and that the radiosensitivity difference for the beagle and human liver is unknown. 41 refs., 8 figs., 5 tabs

  12. Tank characterization report for single-shell tank 241-U-103

    Energy Technology Data Exchange (ETDEWEB)

    SASAKI, L.M.

    1999-02-24

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-U-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-U-103 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with Waste Information Requirements Documents developed for 1998.''

  13. Tank characterization report for single-shell tank 241-T-105

    Energy Technology Data Exchange (ETDEWEB)

    Field, J.G.

    1998-06-18

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-105. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-105 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ``issue characterization deliverables consistent with the waste information requirements documents developed for 1998``.

  14. Tank characterization report for single-shell tank 241-SX-106

    Energy Technology Data Exchange (ETDEWEB)

    FIELD, J.G.

    1999-02-24

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-106. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-106 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Documents developed for 1998.''

  15. Tank characterization report for single-shell tank 241-BX-110

    Energy Technology Data Exchange (ETDEWEB)

    RASMUSSEN, J.H.

    1999-02-23

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-BX-110. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-BX-110 waste, and (2) to provide a standard characterization of the waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations about the tank's safety status and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for 1998.''

  16. XRCC3 Thr241Met gene polymorphisms and lung cancer risk: a meta-analysis

    Directory of Open Access Journals (Sweden)

    Zhan Ping

    2013-01-01

    Full Text Available Abstract Many studies have examined the association between the XRCC3 Thr241Met gene polymorphism and lung cancer risk in various populations, but their results have been inconsistent. To assess this relationship more precisely, a meta-analysis was performed. The PubMed, Embase, Web of Science, and CNKI database was searched for case–control studies published up to July 2012. Data were extracted and pooled odds ratios (OR with 95% confidence intervals (CI were calculated. Ultimately, 17 studies, comprising 4123 lung cancer cases and 5597 controls were included. Overall, for T allele carriers (TC + TT versus the wild-type homozygotes (CC, the pooled OR was 0.95 (95% CI = 0.87-1.04 P = 0.228 for heterogeneity, for TT versus CC the pooled OR was 0.99 (95% CI = 0.86-1.15 P = 0.315 for heterogeneity. In the stratified analysis by ethnicity, histological types of lung cancer and smoking status, no any significantly risks were found for (C/T + T/T vs C/C or T/T vs C/C. No publication bias was found by using the funnel plot and Egger's test. Overall, there is no evidence showing a significant correlation between XRCC3 Thr241Met polymorphism and lung cancer risk stratified analysis by ethnicity, histology and smoking status.

  17. Tank characterization report for single-shell tank 241-BX-110

    International Nuclear Information System (INIS)

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-BX-110. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-BX-110 waste, and (2) to provide a standard characterization of the waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations about the tank's safety status and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for 1998.''

  18. Tank Characterization report for single-shell tank 241-SX-103

    International Nuclear Information System (INIS)

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-103 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for fiscal year 1999'' (Adams et al. 1998)

  19. Tank characterization report for single-shell tank 241-U-103

    International Nuclear Information System (INIS)

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-U-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-U-103 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with Waste Information Requirements Documents developed for 1998.''

  20. Tank characterization report for single-shell tank 241-SX-106

    International Nuclear Information System (INIS)

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-106. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-106 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Documents developed for 1998.''

  1. Tank characterization report for single-shell tank 241-AX-102

    International Nuclear Information System (INIS)

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-AX-102. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-AX-102 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for FY 1999'' (Adams et al. 1998)

  2. Tank characterization report for single-shell tank 241-SX-115

    International Nuclear Information System (INIS)

    A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-SX-115. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-115 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for FY 1999'' (Adams et al. 1998)

  3. Chemical Characterization of an Envelope B/D Sample from Hanford Tank 241-AZ-102

    International Nuclear Information System (INIS)

    A sample from Hanford waste tank 241-AZ-102 was received at the Savannah River Technology Center (SRTC) and chemically characterized. The sample containing supernate and a small amount of sludge solids was analyzed as-received. The filtered supernatant liquid, the total dried solids of the sample, and the washed insoluble solids obtained from filtration of the sample were analyzed. A mass balance calculation of the three fractions of the sample analyzed indicate the analytical results appear relatively self-consistent for major components of the sample. However, some inconsistency was observed between results were more than one method of determination was employed and for species present in low concentrations. The actinides isotopes, plutonium, americium, and curium, present analytical challenges due to the low concentration of these species and the potential for introduction of small amounts of contamination during sampling handling resulting in large uncertainties. A direct comparison to previous analyses of material from tank 241-AZ-102 showed good agreement with the filtered supernatant liquid. However, the comparison of solids data showed poor agreement. The poor agreement shown between the current results for the solids samples and previous analyses most likely results from the uncertainties associated with obtaining small solids samples from a large non-homogenized waste tank

  4. Tank characterization report for Single-Shell Tank 241-T-107

    International Nuclear Information System (INIS)

    Single shell tank 241-T-107 is a Hanford Site Ferrocyanide Watch List tank most recently sampled in March 1993. Analyses of materials obtained from tank T-107 were conducted to support the Ferrocyanide Unreviewed Safety Question (USQ) and the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-06 as well as Milestones M-44-05 and M-44-07. Characterization of the tank waste T-107 will support the ferrocyanide safety issue in order to classify the tank as safe, conditionally safe, or unsafe. This tank characterization report expands on the data found in Ferrocyanide Safety Program: Data Interpretation Report for Tank 241-T-107 Core Samples. Analysis of core samples obtained from tank T-107 strongly indicate the cyanide and oxidizer (nitrate/nitrite) concentrations in the tank waste are not significant enough to support a self-sustaining exothermic reaction. Therefore, the contents of tank T-107 present no imminent threat to the workers at the Hanford Site, the public, or the environment. Because the possibility of an exothermic reaction is remote, the consequences of an accident scenario, as proposed by the General Accounting Office, are not applicable

  5. The determination of Pu-241 by liquid scintillation counting in the environment of the Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    A procedure was developed to measure Pu-241 by liquid scintillation counting. Sample preparation was performed by electroplating of plutonium on stainless steel planchets. To correct the selfabsorption the linear dependence of counting efficiency in the liquid scintillation counter and the resolution in the α-spectrometer was used. The determination of Pu-238, Pu-239+240 and Pu-241 was performed in soil and plant samples and in depth profiles in soil in the second main-wind direction as measured near the WAK. The dilution of plutonium isotopes in the River Old Rhine was measured until 13.5 km downstreams from the release of liquid effluents of the Karlsruhe Nuclear Research Center. The Pu-241 concentrations in soil ranged from <80 until 35000 fCi/g dry. In plant values up till 8100 fCi/g dry were measured. In the River Old Rhine the Pu-241 concentrations were between <110 and 16.200 fCi/l. The activity ratios Pu-241/Pu-239+240 in soil samples were about 12 near the WAK and about 61 in larger distances. The first value agrees very well with the ration expected in plutonium from nuclear weapon fallout. The higher value represents an additional contamination by nuclear installations. The mean value in plants was 33 and in the River Old Rhine 56. The standard deviations of the measured activity ratios are very large. The dose exposure of the environmental population of the Karlsruhe Nuclear Research Center caused be released Pu-241 is negligible low. (orig./HP)

  6. Tank 241-SY-102 January 2000 Compatibility Grab Samples Analytical Results for the Final Report [SEC 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    BELL, K.E.

    2000-05-11

    This document is the format IV, final report for the tank 241-SY-102 (SY-102) grab samples taken in January 2000 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank SY-102 samples were performed as directed in Comparability Grab Sampling and Analysis Plan for Fiscal Year 2000 (Sasaki 1999). No notification limits were exceeded. Preliminary data on samples 2SY-99-5, -6, and -7 were reported in ''Format II Report on Tank 241-SY-102 Waste Compatibility Grab Samples Taken in January 2000'' (Lockrem 2000). The data presented here represent the final results.

  7. Determination of {sup 238}Pu, {sup 239+240}Pu, {sup 241}Pu and {sup 241}Am in radioactive waste from IPEN reactor

    Energy Technology Data Exchange (ETDEWEB)

    Geraldo, Bianca; Taddei, Maria Helena T.; Cheberle, Sandra M.; Ferreira, Marcelo T., E-mail: bgeraldo@cnen.gov.b, E-mail: mhtaddei@cnen.gov.b, E-mail: scsantos@cnen.gov.b, E-mail: ferreira@cnen.gov.b [Brazilian Nuclear Energy Commission (LAPOC/CNEN-MG), Pocos de Caldas, MG (Brazil). Lab. of Pocos de Caldas; Marumo, Julio T., E-mail: jtmarumo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Ion exchange resin is a common type of radioactive waste arising from treatment of coolant water of the main circuit of research and nuclear power reactors. This waste contains high concentrations of fission and activation products. The management of this waste includes its characterization in order to determine and quantify specific radionuclides including those known as difficult-to-measure radionuclides (RDM). The analysis of RDMs generally involves expensive and time-consuming complex radiochemical analysis for purification and separation of the radionuclides. The objective of this work is to show an easy methodology for quantifying plutonium and americium isotopes in spent ion exchange resin, used for purification of the cooling water of the IEA-R1 reactor located at the Nuclear and Energy Research Institute, IPEN-CNEN/SP. The resins were destroyed by acid digestion, followed by purification and separation of the Pu and Am isotopes with anionic and chromatographic resins. {sup 238}Pu, {sup 239}+{sup 24}'0Pu, and {sup 24}'1Am isotopes were analyzed in an alpha spectrometer equipped with surface barrier detectors. {sup 241}Pu isotope was analyzed by liquid scintillation counting. Chemical recovery yield ranged from 73 to 98% for Pu and 77 to 98% for Am, demonstrating that the methodology is suitable for identification and quantification of the isotopes studied in spent resins. (author)

  8. Estimates of dose to systematic organs and GI tract based on data from miniature swine orally intubated with a single dose of Am-241 citrate

    International Nuclear Information System (INIS)

    A model is presented for the internal radiation dose to the small intestine wall of miniature swine given Americium 241 citrate by oral intubation. The model incorporates the uptake of the Am-241 by the intestinal wall. About equal contributions of dose to the small intestine were observed from the intestinal contents and the wall itself

  9. Determination of (241)Pu by the method of disturbed radioactive equilibrium using 2πα-counting and precision gamma-spectrometry.

    Science.gov (United States)

    Alekseev, I; Kuzmina, T

    2016-04-01

    A simple technique is proposed for the determination of the content of (241)Pu, which is based on disturbance of radioactive equilibrium in the genetically related (237)U←(241)Pu→(241)Am decay chain of radionuclides, with the subsequent use of 2πα-counting and precision gamma-spectroscopy for monitoring the process of restoration of that equilibrium. It has been shown that the data on dynamics of accumulation of the daughter (241)Am, which were obtained from the results of measurements of α- and γ-spectra of the samples, correspond to the estimates calculated for the chain of two genetically related radionuclides, the differences in the estimates of (241)Pu radioactivity not exceeding 2%. Combining the different methods of registration (2πα-counting, semiconductor alpha- and gamma-spectrometry) enables the proposed method to be efficiently applied both for calibration of (241)Pu-sources (from several hundreds of kBq and higher) and for radioisotopic analysis of plutonium mixtures. In doing so, there is a deep purification of (241)Pu from its daughter decay products required due to unavailability of commercial detectors that could make it possible, based only on analysis of alpha-spectra, to conduct quantitative analysis of the content of (238)Pu and (241)Am.

  10. Nuclear structure of 241Pu from neutron-capture, (d,p)-, and (d,t)-reaction measurements

    International Nuclear Information System (INIS)

    We report experimental measurements in 241Pu of the following: primary and secondary γ rays and conversion electrons from thermal neutron capture in 240Pu;γ rays from 245Cm α decay; proton and triton spectra, respectively, from (d,p) and (d,t) reactions on 240Pu and 242Pu targets. From these data and those of other investigations, we have identified 53 excited levels in 241Pu below 1400 keV. Of these, 44 are placed in 10 rotational bands (with connecting transitions) that have been assigned Nilsson configurations. For the bands below 1 MeV in 241Pu that are largely of single-particle character, there is good correspondence with similar bands in 239U and with the theoretical model of Gareev et al. For those bands in 241Pu where there is mixing between single-particle and vibrational modes, we find some significant deviations from theoretical predictions. For example, the (5) /(2) [622]circle-times 0- state at 519 keV appears to mix less with other states than predicted, while a trio of Kπ= (1) /(2) - bands show unexpected mixing patterns. copyright 1998 The American Physical Society

  11. Transport of Tank 241-SY-101 Waste Slurry: Effects of Dilution and Temperature on Critical Pipeline Velocity

    International Nuclear Information System (INIS)

    This report presents the methods and results of calculations performed to predict the critical velocity and pressure drop required for the two-inch pipeline transfer of solid/liquid waste slurry from underground waste storage Tank 241-SY-101 to Tank 241-SY- 102 at the Hanford Site. The effects of temperature and dilution on the critical velocity were included in the analysis. These analyses show that Tank 241-SY-101 slurry should be diluted with water prior to delivery to Tank 241-SY-102. A dilution ratio of 1:1 is desirable and would allow the waste to be delivered at a critical velocity of 1.5 ft/sec. The system will be operated at a flow velocity of 6 ft/sec or greater therefore, this velocity will be sufficient to maintain a stable slurry delivery through the pipeline. The effect of temperature on the critical velocity is not a limiting factor when the slurry is diluted 1:1 with water. Pressure drop at the critical velocity would be approximately two feet for a 125-ft pipeline (or 250-ft equivalent straight pipeline). At 6 ft/sec, the pressure drop would be 20 feet over a 250-ft equivalent straight pipeline

  12. Simulation and rheological analysis of Hanford Tank 241-SY-101. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sams, E.C.; Tennant, R.A.; Piccola, J.P. Jr.

    1993-10-01

    Rheological characterization and small scale simulation of Hanford Tank 241-SY-101 has been initiated to aid in the remediation efforts for the Department of Energy Hanford Site. The study has been initiated in response to growing concerns about the potential flammability hazard pertaining to the periodic release of up to 10,000 cubic feet of hydrogen, nitrous oxide, nitrogen, and ammonia gases. Various stimulants emulating the radioactive waste stored in this tank have been used to ascertain the rheological parameters of the waste, simulate the ongoing processes of gas generation and release phenomenon inside the tank, and determine the feasibility of jet mixing to achieve a controlled release of the gas mixture.

  13. Characterization of the neutron field of the 241AmBe in a calibration room

    International Nuclear Information System (INIS)

    The field of neutrons produced by an isotopic source of neutrons of 241 Am Be had been characterized. The characterization was carried out modeling those relevant details of the calibration room and simulating the neutron transport at different distances of the source. The calculated spectra were used to determine the equivalent environmental dose rate. A series of experiments were carried out with the Bonner sphere spectrometric system to measure the spectra in the same points where the calculations were carried out and with these spectra the rates of environmental dose were calculated. By means of a one sphere dosemeter type Berthold the rates of environmental dose were measured. To the one to compare the calculated spectra and measured its were found small differences in the group of the thermal neutrons due to the elementary composition used during the simulation. When comparing the derived rates starting from the calculated spectra with those measured it was found a maxim difference smaller to 13%. (Author)

  14. Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

    Energy Technology Data Exchange (ETDEWEB)

    Conner, J.C.

    1994-10-18

    This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue.

  15. Waste compatibility safety issues and final results for Tank 241-AP-103 grab samples

    International Nuclear Information System (INIS)

    Three grab samples (3AP-97-2, 3AP-97-3, and 3AP-97-4) were taken from Riser 1 of Tank 241-AP-103 on August 21, 1997, and received by 222-S Laboratory on August 22, 1997. These samples were analyzed in accordance with Compatibility Grab Sampling and Analysis Plan for Fiscal Year 1997 (TSAP) (Field, 1997) and Data Quality Objectives for Tank Farms Waste and Compatibility Program (Mulkey et. al., 1995) (DQO) in support of the Waste Compatibility Program. No notifications were required based on sample results. Appearance and Sample Breakdown Attachment 1 illustrates subsamples generated in the laboratory for analyses and identifies their sources. Furthermore, this reference relates tank farm identification numbers to their corresponding 222-S Laboratory Information Management System sample numbers. Table 1 summarizes appearance information and over-the-top (OTR) dose readings performed on each sample. For each sample, two 20 ml subsamples were created for inorganic and radiochemical analyses

  16. Solid Phase Characterization of Tank 241-C-108 Residual Waste Solids Samples

    Energy Technology Data Exchange (ETDEWEB)

    Cooke, Gary A.; Pestovich, John A.; Huber, Heinz J.

    2013-05-29

    This report presents the results for solid phase characterization (SPC) of solid samples removed from tank 241-C-108 (C-108) on August 12-13,2012, using the off-riser sampler. Samples were received at the 222-S Laboratory on August 13 and were described and photographed. The SPC analyses that were performed include scanning electron microscopy (SEM) using the ASPEX(R)l scanning electron microscope, X-ray diffraction (XRD) using the Rigaku(R) 2 MiniFlex X-ray diffractometer, and polarized light microscopy (PLM) using the Nikon(R) 3 Eclipse Pol optical microscope. The SEM is equipped with an energy dispersive X-ray spectrometer (EDS) to provide chemical information. Gary A. Cooke conducted the SEM analysis, John A. Pestovich performed the XRD analysis, and Dr. Heinz J. Huber performed the PLM examination. The results of these analyses are presented here.

  17. Hanford Tank 241-C-106: Residual Waste Contaminant Release Model and Supporting Data

    International Nuclear Information System (INIS)

    This report was revised in May 2007 to correct values in Section 3.4.1.7, second paragraph, last sentence; 90Sr values in Tables 3.22 and 3.32; and 99Tc values Table 4.3 and in Chapter 5. In addition, the tables in Appendix F were updated to reflect corrections to the 90Sr values. The rest of the text remains unchanged from the original report issued in May 2005. CH2M HILL is producing risk/performance assessments to support the closure of single-shell tanks at the DOE's Hanford Site. As part of this effort, staff at PNNL were asked to develop release models for contaminants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. This report provides the information developed by PNNL.

  18. Hanford Tank 241-C-106: Residual Waste Contaminant Release Model and Supporting Data

    Energy Technology Data Exchange (ETDEWEB)

    Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

    2007-05-23

    This report was revised in May 2007 to correct values in Section 3.4.1.7, second paragraph, last sentence; 90Sr values in Tables 3.22 and 3.32; and 99Tc values Table 4.3 and in Chapter 5. In addition, the tables in Appendix F were updated to reflect corrections to the 90Sr values. The rest of the text remains unchanged from the original report issued in May 2005. CH2M HILL is producing risk/performance assessments to support the closure of single-shell tanks at the DOE's Hanford Site. As part of this effort, staff at PNNL were asked to develop release models for contam¬inants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. This report provides the information developed by PNNL.

  19. In situ determination of 241Am on Enewetak Atoll. Date of survey: July 1977-December 1979

    International Nuclear Information System (INIS)

    An in situ gamma ray spectrometer system was operated at Enewetak Atoll from July 1977 to December 1979 in support of the Enewetak Cleanup Project. The system employed a high purity germanium planar detector suspended at a height of 7.4 m above ground. Conversion factors were established to relate measured photopeak count rate data to source concentration in the soil. Data obtained for 241Am, together with plutonium-to-americium ratios obtained from soil sample analyses, were used to establish area-averaged surface (0 to 3 cm) transuranic concentration values. In areas which exceeded cleanup criteria, measurements were made in an iterative fashion to guide soil removal until levels were reduced below the cleanup criteria. Final measurements made after soil removal had been completed were used to document remaining surface transuranic concentration values and to establish external exposure rate levels due to 137Cs and 60Co

  20. Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

    International Nuclear Information System (INIS)

    This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue

  1. Final report for tank 241-BX-104 push mode core 126 and 127

    International Nuclear Information System (INIS)

    This is the final sample analysis report for tank 241-BX-104 (BX-104), cores 126 and 127. Two segments from each core yielded a total of 11 samples which were analyzed. The data quality objectives (DQOs) applicable to this sampling event were the Safety Screening DQO (Dukelow et al. 1995) and the Organic Safety DQO (Turner et al. 1995). The samples were received, extruded and analyzed at PNNL 325 Analytical Chemistry Laboratory (ACL). The analyses were performed in accordance with the Sample Analysis Plan (Gretsinger 1996) and indicated that the tank is safe with respect to the criteria in the Safety Screening and Organic DQO. Detailed analytical results were described in the analytical laboratory 45-day Report (Attachment 1, WHC-SD-WM-DP-171, REV. 0) and final report (Attachment 2, PNL-BX-104 REV.1) prepared by PNNL, 325 Laboratory. Corrections and/or exceptions to the PNNL final report are provided

  2. Tank 241-SY-101 push mode core sampling and analysis plan

    International Nuclear Information System (INIS)

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for push mode core samples from tank 241-SY-101 (SY-101). It is written in accordance with Data Quality Objective to Support Resolution of the Flammable Gas Safety Issue (Bauer 1998), Low Activity Waste Feed Data Quality Objectives (Wiemers and Miller 1997 and DOE 1998), Data Quality Objectives for TWRS Privatization Phase I: Confirm Tank T is an Appropriate Feed Source for Low-Activity Waste Feed Batch X (Certa 1998), and the Tank Safety Screening Data Quality Objective (Dukelow et al. 1995). The Tank Characterization Technical Sampling Basis document (Brown et al. 1998) indicates that these issues apply to tank SY-101 for this sampling event. Brown et al. also identifies high-level waste, regulatory, pretreatment and disposal issues as applicable issues for this tank. However, these issues will not be addressed via this sampling event

  3. Attenuation studies near K-absorption edges using Compton scattered 241Am gamma rays

    Indian Academy of Sciences (India)

    K K Abdullah; N Ramachandran; K Karunakaran Nair; B R S Babu; Antony Josephm; Rajive Thomas; K M Varier

    2008-04-01

    We have carried out photon attenuation measurements at several energies in the range from 49.38 keV to 57.96 keV around the K-absorption edges of the rare earth elements Sm, Eu, Gd, Tb, Dy and Er using 59.54 keV gamma rays from 241Am source after Compton scattering from an aluminium target. Pellets of oxides of the rare earth elements were chosen as mixture absorbers in these investigations. A narrow beam good geometry set-up was used for the attenuation measurements. The scattered gamma rays were detected by an HPGe detector. The results are consistent with theoretical values derived from the XCOM package.

  4. Tank 241-AZ-101 prototype corrosion probe four month status report

    Energy Technology Data Exchange (ETDEWEB)

    Edgemon, G.L., Westinghouse Hanford

    1996-12-12

    High-level nuclear wastes at the Hanford Site are stored underground in carbon steel double-shell and single-shell tanks. The installation of a prototype corrosion monitoring system into double-shell tank 241-AZ-101 was completed in August, 1996. The system monitors fluctuations in corrosion current and potential (electrochemical noise) occurring on three electrode arrays immersed in the waste liquid and in the vapor space above the waste. The system also supports the use of Tafel and linear polarization resistance testing. By monitoring and analyzing the data from these techniques, changes in the corrosive characteristics of the waste have been rapidly detected and correlated with operational changes in the tank.

  5. 241-SY-101 strain concentration factor development via nonlinear analysis. Volume 1 of 1

    International Nuclear Information System (INIS)

    The 241-SY-101 waste storage tank at the Hanford-Site has been known to accumulate and release significant quantities of hydrogen gas. An analysis was performed to assess the tank's structural integrity when subjected to postulated hydrogen deflagration loads. The analysis addressed many nonlinearities and appealed to a strain-based failure criteria. The model used to predict the global response of the tank was not refined enough to confidently predict local peak strains. Strain concentration factors were applied at structural discontinuities that were based on steel-lined reinforced-concrete containment studies. The discontinuities included large penetrations, small penetrations, springline geometries, stud/liner connections, and the 1/2 inch to 3/8 inch liner thickness transition. The only tank specific strain concentration factor applied in the evaluation was for the 1/2 inch to 3/8 inch liner thickness change in the dome. Review of the tank drawings reveals the possibility that a 4 inches Sch. 40 pipe penetrates the dome thickness transition region. It is not obvious how to combine the strain concentration factors for a small penetration with that of a thickness transition to arrive at a composite strain concentration factor. It is the goal of this effort to make an approximate determination of the relative significance of the 4 inch penetration and the 1/2 inch to 3/8 inch thickness transition in the 241-SY-101 dome geometry. This is accomplished by performing a parametric study with three general finite-element models. The first represents the thickness transition only, the second represents a 4 inch penetration only, and the third combines the thickness transition with a penetration model

  6. Process Control Plan for Tank 241-SY-101 Surface Level Rise Remediation

    International Nuclear Information System (INIS)

    The tank 241-SY-101 transfer system was conceived and designed to address the immediate needs presented by rapidly changing waste conditions in tank 241-SY-101. Within approximately the last year, the waste in this tank has exhibited unexpected behavior (Rassat et al. 1999) in the form of rapidly increasing crust growth. This growth has been brought about by a rapidly increasing rate of gas entrapment within the crust. It has been conceived that the lack of crust agitation beginning upon the advent of mixer pump operations may have set-up a more consolidated, gas impermeable barrier when compared to a crust regularly broken up by the prior buoyant displacement events within the tank. The interim goals of the project are to: (1) protect the mixer pump operability (2) begin releasing gas from the crust, and (3) begin dissolving the crust and solids in the slurry layer. The final goals of the project (Final State) are to solve both the level growth and BD-GRE safety issues in this tank by achieving a condition of the waste such that no active measures are required to safely store the waste, i.e., crust and non convective layer are mostly dissolved, and therefore the mixer pump will no longer be needed to prevent BD-GREs in excess of 100% LFL. Transfers (which are designed to create space in the tank) and dilution (which will dissolve the solids) will accomplish this. Dissolution of solids will result in a release of gas retained by those solids and remove that volume of solids as a future retention site

  7. Process Control Plan for Tank 241-SY-101 Surface Level Rise Remediation

    Energy Technology Data Exchange (ETDEWEB)

    ESTEY, S.D.

    1999-11-01

    The tank 241-SY-101 transfer system was conceived and designed to address the immediate needs presented by rapidly changing waste conditions in tank 241-SY-101. Within approximately the last year, the waste in this tank has exhibited unexpected behavior (Rassat et al. 1999) in the form of rapidly increasing crust growth. This growth has been brought about by a rapidly increasing rate of gas entrapment within the crust. It has been conceived that the lack of crust agitation beginning upon the advent of mixer pump operations may have set-up a more consolidated, gas impermeable barrier when compared to a crust regularly broken up by the prior buoyant displacement events within the tank. The interim goals of the project are to: (1) protect the mixer pump operability (2) begin releasing gas from the crust, and (3) begin dissolving the crust and solids in the slurry layer. The final goals of the project (Final State) are to solve both the level growth and BD-GRE safety issues in this tank by achieving a condition of the waste such that no active measures are required to safely store the waste, i.e., crust and non convective layer are mostly dissolved, and therefore the mixer pump will no longer be needed to prevent BD-GREs in excess of 100% LFL. Transfers (which are designed to create space in the tank) and dilution (which will dissolve the solids) will accomplish this. Dissolution of solids will result in a release of gas retained by those solids and remove that volume of solids as a future retention site.

  8. Development and Demonstration of a Sulfate Precipitation Process for Hanford Waste Tank 241-AN-107

    Energy Technology Data Exchange (ETDEWEB)

    SK Fiskum; DE Kurath; BM Rapko

    2000-08-16

    A series of precipitation experiments were conducted on Hanford waste tank 241-AN-107 samples in an effort to remove sulfate from the matrix. Calcium nitrate was added directly to AN-107 sub-samples to yield several combinations of Ca:CO{sub 3} mole ratios spanning a range of 0:1 to 3:1 to remove carbonate as insoluble CaCO{sub 3}. Similarly barium nitrate was added directly to the AN-107 aliquots, or to the calcium pretreated AN-107 aliquots, giving of Ba:SO{sub 4} mole ratios spanning a range of 1:1 to 5:1 to precipitate sulfate as BaSO{sub 4}. Initial bulk carbonate removal was required for successful follow-on barium sulfate precipitation. A {ge} 1:1 mole ratio of Ca:CO{sub 3} was found to lower the carbonate concentration such that Ba would react preferentially with the sulfate. A follow-on 1:1 mole ratio of Ba:SO{sub 4} resulted in 70% sulfate removal. The experiment was scaled up with a 735-mL aliquot of AN-107 for more complete testing. Calcium carbonate and barium sulfate settling rates were determined and fates of selected cations, anions, and radionuclides were followed through the various process steps. Seventy percent of the sulfate was removed in the scale-up test while recovering 63% of the filtrate volume. Surprisingly, during the scale-up test a sub-sample of the CaCO{sub 3}/241-AN-107 slurry was found to lose fluidity upon standing for {le} 2 days. Metathesis with BaCO{sub 3} at ambient temperature was also evaluated using batch contacts at various BaCO{sub 3}:SO{sub 4} mole ratios with no measurable success.

  9. Development and Demonstration of a Sulfate Precipitation Process for Hanford Waste Tank 241-AN-107

    International Nuclear Information System (INIS)

    A series of precipitation experiments were conducted on Hanford waste tank 241-AN-107 samples in an effort to remove sulfate from the matrix. Calcium nitrate was added directly to AN-107 sub-samples to yield several combinations of Ca:CO3 mole ratios spanning a range of 0:1 to 3:1 to remove carbonate as insoluble CaCO3. Similarly barium nitrate was added directly to the AN-107 aliquots, or to the calcium pretreated AN-107 aliquots, giving of Ba:SO4 mole ratios spanning a range of 1:1 to 5:1 to precipitate sulfate as BaSO4. Initial bulk carbonate removal was required for successful follow-on barium sulfate precipitation. A ge 1:1 mole ratio of Ca:CO3 was found to lower the carbonate concentration such that Ba would react preferentially with the sulfate. A follow-on 1:1 mole ratio of Ba:SO4 resulted in 70% sulfate removal. The experiment was scaled up with a 735-mL aliquot of AN-107 for more complete testing. Calcium carbonate and barium sulfate settling rates were determined and fates of selected cations, anions, and radionuclides were followed through the various process steps. Seventy percent of the sulfate was removed in the scale-up test while recovering 63% of the filtrate volume. Surprisingly, during the scale-up test a sub-sample of the CaCO3/241-AN-107 slurry was found to lose fluidity upon standing for le 2 days. Metathesis with BaCO3 at ambient temperature was also evaluated using batch contacts at various BaCO3:SO4 mole ratios with no measurable success

  10. Structural analysis of multiport riser 5A installation on tank 241SY101

    Energy Technology Data Exchange (ETDEWEB)

    Strehlow, J.P.

    1994-09-16

    The Tank 101-SY multiport riser assembly in the 241-SY-101 waste tank will replace the existing 42 inch riser with four smaller ports. Each smaller port can be used independently to access the tank interior with equipment and instruments needed to mitigate the concentration of hydrogen in the tank. This document provides a design report on the structural evaluation of the multiport riser assembly as well as its anchorage. The multiport riser assembly is a steel structure installed directly above the 42-inch riser and sealed at the existing riser flange. The assembly is structurally supported by the concrete pad placed around the 42 inch riser. The multiport riser assembly will provide two 8-inch penetrations, one 12-inch penetration and one 24-inch penetration. Each penetration will have a shielding plate. These penetrations will be used to insert equipment such as a sonic probe into the tank. In addition to normal loads, non-reactor Safety Class 1 structures, systems and components are to withstand the effects of extreme environmental loads including Design Basis Earthquake (DBE), Design Basis Wind (DBW), Design Basis Flood, Volcanic Eruptions and other abnormal loads considered on a case by case basis. Non-reactor Safety Class 2, 3 and 4 structures, systems and components are those that are not Safety Class 1 and are respectively specified as onsite safety related, occupational safety related and non-safety related items. The 241-SY-101 tank is considered as a non-reactor Safety Class 1 structure. The multiport riser assembly is considered as a non-reactor Safety Class 2 structure since it serves to contain the radioactive and toxic materials under normal operating conditions. However, the pressure relief doors provided on the assembly are considered as Safety Class 1 structures.

  11. Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 2 testing

    International Nuclear Information System (INIS)

    This document summarizes the results of the Phase 2 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the test mixer pump currently installed in Tank 241-SY-101. The purpose of this acceptance test is to verify the strength of the containment bag and bag bottom cinching mechanism. It is postulated that 68 gallons of waste could be trapped inside the pump internals. The bag must be capable of supporting this waste if it shakes loose and drains to the bottom of the bag after the bag bottom has been cinched closed. This acceptance test was performed at the Maintenance and Storage Facility (MASF) Facility in the 400 area on January 23, 1995. The bag assembly supported the weight of 920 kg (2,020 lbs) of water with no leakage or damage to the bag. This value meets the acceptance criteria of 910 kg of water and therefore the results were found to be acceptable. The maximum volume of liquid expected to be held up in the pump internals is 258 L (68 gallons), which corresponds to 410 kg. This test weight gives just over a safety factor of 2. The bag also supported a small shock load while it was filled with water when the crane hoisted the bag assembly up and down. Based on the strength rating of the bag components, the bag assembly should support 2--3 times the test weight of 910 kg

  12. Characterization of 241Am and 134Cs bioaccumulation in the king scallop Pecten maximus: investigation via three exposure pathways

    International Nuclear Information System (INIS)

    In order to understand the bioaccumulation of 241Am and 134Cs in scallops living in sediments, the uptake and depuration kinetics of these two elements were investigated in the king scallop Pecten maximus exposed via seawater, food, or sediment under laboratory conditions. Generally, 241Am accumulation was higher and its retention was stronger than 134Cs. This was especially obvious when considering whole animals exposed through seawater with whole-body concentration factors (CF7d) of 62 vs. 1, absorption efficiencies (A0l) of 78 vs. 45 for seawater and biological half-lives (Tb1/2l) of 892 d vs. 22 d for 241Am and 134Cs, respectively. In contrast, following a single feeding with radiolabelled phytoplankton, the assimilation efficiency (AE) and Tb1/2l of 134Cs were higher than those of 241Am (AE: 28% vs. 20%; Tb1/2l: 14 d vs. 9 d). Among scallop tissues, the shells always contained the higher proportion of the total body burden of 241Am whatever the exposure pathway. In contrast, the whole soft parts presented the major fraction of whole-body burden of 134Cs, which was generally associated with muscular tissues. Our results showed that the two radionuclides have contrasting behaviors in scallops, in relation to their physico-chemical properties. - Highlights: → We determined Am and Cs uptake and depuration kinetics following seawater, food and sediment exposures. → We determined radionuclide tissue distribution after exposure and after depuration periods. → Am was mainly associated to the shell whatever the exposure pathway was. → Transfer processes occurred between soft and hard tissues for Am.

  13. 241Am distribution and retention in pregnant mice, in their offspring and in non-pregnant mice: comparison between continuous Am administration and single injection

    International Nuclear Information System (INIS)

    Pregnant BALB/c mice and age and sex matched nulliparous controls were contaminated with 241Am (13 kBq per mouse). Five days after the termination of contamination, 241Am incorporation was measured in the tissues of adults and in the liver an the femur of newborn and one-month-old mice. Pregnancy resulted in higher 241Am concentrations in bone but lower concentrations in the liver of the mothers. Protracted administration of 241Am compared to a single injection resulted in a lower concentration of 241Am in the livers of pregnant mice, their nulliparous controls and from newborn mice. The higher 241Am concentration in the femur at birth after protected exposure before 14 days of gestation compared to protracted exposure after 14 days of gestation could reflect the increased placental transfer of 241Am with advancing gestational age. Radiation doses to the femur were estimated between 4 and 20 mGy. Haemopoietic changes were noticed at these dose levels in all groups until at least 6 months after birth. (author)

  14. Spatial distribution of {sup 241}Am, {sup 137}Cs, {sup 238}Pu, {sup 239,240}Pu and {sup 241}Pu over 17 year periods in the Ravenglass saltmarsh, Cumbria, UK

    Energy Technology Data Exchange (ETDEWEB)

    Oh, J.-S. [GAU-Radioanalytical, School of Ocean and Earth Science, National Oceanography Centre, Southampton SO14 3ZH (United Kingdom)], E-mail: jsoh@noc.soton.ac.uk; Warwick, P.E. [GAU-Radioanalytical, School of Ocean and Earth Science, National Oceanography Centre, Southampton SO14 3ZH (United Kingdom)], E-mail: pew@noc.soton.ac.uk; Croudace, I.W. [GAU-Radioanalytical, School of Ocean and Earth Science, National Oceanography Centre, Southampton SO14 3ZH (United Kingdom)], E-mail: iwc@noc.soton.ac.uk

    2009-07-15

    Ninety five surface scrape samples were collected at the Ravenglass saltmarsh and analysed for radionuclides by alpha spectrometry ({sup 238}Pu and {sup 239,240}Pu), gamma spectrometry ({sup 241}Am and {sup 137}Cs) and liquid scintillation counting ({sup 241}Pu). Both {sup 241}Am and {sup 137}Cs activities are compared with those reported by Horrill [1983. Concentrations and spatial distribution of radioactivity in an ungrazed saltmarsh. In: Coughtrey, P.J. (Ed.), Ecological Aspects of Radionuclide Release. British Ecological Society Special Publication No. 3. Blackwell, Oxford, pp. 119-215.] Significant decreases in activities for both radionuclides were observed which is caused by the declining levels of discharges from the Sellafield nuclear reprocessing plant since the 1980s. It has been concluded that the spatial distribution of these radionuclides are controlled by the tidal currents and the clay contents in the sediments. There is evidence of surface erosion of the saltmarsh and redistribution of radionuclides in the saltmarsh using isotopic ratios of measured Pu.

  15. REPORT ON THE EFFECT OF TEMPERATURE AND AMMONIA CONCENTRATION ON A515 CARBON STEEL IN TANK 241 AY 101 SIMULANT

    Energy Technology Data Exchange (ETDEWEB)

    DUNCAN JB; FRYE DP; WYRWAS RB

    2008-11-20

    This report documents the results from RPP-PLAN-38676, Effect of Temperature and Ammonia Concentration on A515 Carbon Steel in Tank 241-AY-101 Simulant. The purpose of this test plan was to investigate the simulant formulated for the double-shell tank (DST) 241 AY 101 (AY 101) with the addition of ammonia. The simulant was formulated from the AY-101 condensate surface layer recipe used by CC Technologies{reg_sign} in the investigation of Hanford DST chemistry, under the Expert Panel on Corrosion. AY-101 is constructed from A515 grade 60 steel. The laboratory investigation used a cylindrical corrosion coupon from this steel formulation with a surface area of 5.64 square centimeters.

  16. Autosomal inheritance of diabetes in two families characterized by obesity and a novel H241Q mutation in NEUROD1

    DEFF Research Database (Denmark)

    Gonsorcíková, Lucie; Pruhová, Stepánka; Cinek, Ondrej;

    2008-01-01

    BACKGROUND: The aim of the study was to search for mutations in the NEUROD1 and IPF-1 genes in patients with clinical characteristics of maturity-onset diabetes of the young (MODY) but with no mutations in the HNF-4A (MODY1), GCK (MODY2) and TCF1 (MODY3) genes. METHODS: We studied 30 unrelated...... Czech probands with a clinical diagnosis of MODY (median age at testing, 18 yr; median age at the recognition of hyperglycaemia, 16 yr). The promoter, exons and exon/intron boundaries of the NEUROD1 and IPF-1 genes were examined by polymerase chain reaction-denaturing high performance liquid...... chromatography and direct sequencing. RESULTS: While no mutations were found in the IPF-1 gene, a novel H241Q substitution of NEUROD1 gene was identified in two unrelated families. In the first proband, the H241Q mutation led to early diagnosed (20 yr) hyperglycaemia followed by development of diabetic...

  17. The influence of impurities for cross section measurement of {sup 241,243}Am(n,f) reactions

    Energy Technology Data Exchange (ETDEWEB)

    Kai, Tetsuya; Kobayashi, Katsuhei; Yamamoto, Shuji; Fujita, Yoshiaki; Kimura, Itsuro; Miyoshi, Mitsuharu; Yamamoto, Hideki [Kyoto Univ. (Japan); Shinohara, Nobuo

    1997-03-01

    The influence of the impurities on the fission cross section measurements for {sup 241}Am and {sup 243}Am has been investigated with the practical results. Following cases have been considered as the influence of impurities; (a) experiments with the {sup 241}Am sample that contains impurities originally, and (b) experiments with the {sup 243}Am sample that contains impurities produced by {alpha}, {beta} decays after the chemical purification. The present study has demonstrated the usefulness of pure samples by the comparison of the experiments using the sample on the market with those using the pure sample processed by the authors. Particularly on the case (b), the correction of the impurity through the periodical measurements was experimentally performed (about 18% around 0.3 eV in 4 weeks after the chemical purification). (author)

  18. Preparation and measurement of 241Am solutions to establish traceability of counting equipment to the National Physical Laboratory

    International Nuclear Information System (INIS)

    Measurement of the 241Am activity in ampoules prepared from a stock solution has established direct traceability of the Harwell low geometry counters numbers 12 and 13 to the 4π alpha/gamma coincidence counting equipment at the National Physical Laboratory. The mean values obtained from measurements on three ampoules at each establishment agree to within 0.2%; the difference lies within the respective experimental errors. (author)

  19. Comparison of evaluations for 235U, 239Pu, 240Pu, 241Pu and 242Pu with integral measurements

    International Nuclear Information System (INIS)

    The evaluations for 235U, 239Pu, 240Pu, 241Pu and 242Pu are considered. Intercomparison is made of the neutron cross section data from INDL/A, ENDL-84, ENDF/B-5 and ENDF/B-6 (where applicable). Integral measurements of the spectrum averaged cross sections are compared to the values derived from evaluated data libraries. (author). 40 refs, 49 figs, 11 tabs

  20. Headspace vapor characterization of Hanford Waste Tank 241-U-112: Results from samples collected on 7/09/96

    Energy Technology Data Exchange (ETDEWEB)

    Evans, J.C.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-112 at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company.

  1. Human-machine interface (HMI) report for 241-SY-101 data acquisition system (DACS) upgrade study

    International Nuclear Information System (INIS)

    This report provides an independent evaluation of information for a Windows based Human Machine Interface (HMI) to replace the existing DOS based Iconics HMI currently used in the Data Acquisition and Control System (DACS) used at Tank 241-SY-101. A fundamental reason for this evaluation is because of the difficulty of maintaining the system with obsolete, unsupported software. The DACS uses a software operator interface (Genesis for DOS HMI) that is no longer supported by its manufacturer, Iconics. In addition to its obsolescence, it is complex and difficult to train additional personnel on. The FY 1997 budget allocated $40K for phase 1 of a software/hardware upgrade that would have allowed the old DOS based system to be replaced by a current Windows based system. Unfortunately, budget constraints during FY 1997 has prompted deferral of the upgrade. The upgrade needs to be performed at the earliest possible time, before other failures render the system useless. Once completed, the upgrade could alleviate other concerns: spare pump software may be able to be incorporated into the same software as the existing pump, thereby eliminating the parallel path dilemma; and the newer, less complex software should expedite training of future personnel, and in the process, require that less technical time be required to maintain the system

  2. Safety equipment list for 241-C-106 waste retrieval, Project W-320: Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Conner, J.C.

    1994-11-15

    The goals of the C-106 sluicing operation are: (1) to stabilize the tank by reducing the heat load in the tank to less than 42 MJ/hr (40,000 Btu/hour), and (2) to initiate demonstration of single-shell tank (SST) retrieval technology. The purpose of this supporting document (SD) is as follows: (1) to provide safety classifications for items (systems, structures, equipment, components, or parts) for the waste retrieval sluicing system (WRSS), and (2) to document and methodology used to develop safety classifications. Appropriate references are made with regard to use of existing systems, structures, equipments, components, and parts for C-106 single-shell transfer tank located in the C Tank Farm, and 241-AY-102 (AY-102) double shell receiver tanks (DST) located in the Aging Waste Facility (AWF). The Waste Retrieval Sluicing System consists of two transfer lines that would connect the two tanks, one to carry the sluiced waste slurry to AY-102, and the other to return the supernatant liquid to C-106. The supernatant, or alternate fluid, will be used to mobilize waste in C-106 for the sluicing process. The equipment necessary for the WRSS include pumps in each tank, sluicers to direct the supernatant stream in C-106, a slurry distributor in AY-102, HVAC for C-106, instrumentation and control devices, and other existing components as required.

  3. Neutron transmission and capture cross section measurements for 241Am at the GELINA facility

    International Nuclear Information System (INIS)

    Resonance parameters for neutron-induced reactions on 241Am below 110 eV have been determined. The parameters result from a resonance shape analysis of transmission and capture data measured at the time-of-flight facility GELINA, with the accelerator operating at a 50 Hz repetition rate. The transmission experiments were carried out at a 25 m station using a Li glass scintillator. The capture experiments were performed at a 12.5 m station by applying the total energy detection principle in combination with the pulse height weighting technique using a pair of C6D6 detectors. The normalization of the capture data was determined by a combined least squares adjustment of the transmission and capture data. From the adjusted resonance parameters a capture cross section of 749 ± 35 b for a neutron energy of 0.0253 eV and an average radiation width of Γγ = 42.0 meV for s-wave resonances were obtained. A missing-level analysis for s-wave neutron resonances within the statistical model results in compatible values with previous estimates. The neutron widths obtained in this work are approximately 22% larger compared to other experimental data and evaluated data libraries. Also the thermal capture cross section is larger than most of the recommended values. However, the resonance parameter file presented in this work is consistent with results of both integral experiments and of the experimentally determined resonance integrals. (authors)

  4. Probabilistic safety assessment for Hanford high-level waste tank 241-SY-101

    International Nuclear Information System (INIS)

    Los Alamos National Laboratory (Los Alamos) is performing a comprehensive probabilistic safety assessment (PSA), which will include consideration of external events for the 18 tank farms at the Hanford Site. This effort is sponsored by the Department of Energy (DOE/EM, EM-36). Even though the methodology described herein will be applied to the entire tank farm, this report focuses only on the risk from the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases (open-quotes burpsclose quotes) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed first because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is being conducted in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. At the Hanford Site there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/salt cake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is about 60 million gal., which contains approximately 120 million Ci of radioactivity

  5. Study of biosorbents application on the treatment of radioactive liquid wastes with americium-241

    International Nuclear Information System (INIS)

    The use of nuclear energy for many different purposes has been intensified and highlighted by the benefits that it provides. Medical diagnosis and therapy, agriculture, industry and electricity generation are examples of its application. However, nuclear energy generates radioactive wastes that require suitable treatment ensuring life and environmental safety. Biosorption and bioaccumulation represent an emergent alternative for the treatment of radioactive liquid wastes, providing volume reduction and physical state change. This work aimed to study biosorbents for the treatment of radioactive liquid wastes contaminated with americium-241 in order to reduce the volume and change the physical state from liquid to solid. The biosorbents evaluated were Saccharomyces cerevisiae immobilized in calcium alginate beads, inactivated and free cells of Saccharomyces cerevisiae, calcium alginate beads, Bacillus subtilis, Cupriavidus metallidurans and Ochrobactrum anthropi. The results were quite satisfactory, achieving 100% in some cases. The technique presented in this work may be useful and viable for implementing at the Waste Management Laboratory of IPEN - CNEN/SP in short term, since it is an easy and low cost method. (author)

  6. Features of the {sup 241}AmBe-based UPM neutron facility

    Energy Technology Data Exchange (ETDEWEB)

    Gallego, E.; Lorente, A. [Universidad Politecnica de Madrid, Laboratorio de Ingenieria Nuclear, Jose Gutierrez Abascal No. 2, 28006 Madrid (Spain); Mendez, R. [CIEMAT, Ionizing Radiation Standard Laboratory, Av. Complutense 40, 28040 Madrid (Spain); Bedogni, R.; Esposito, A. [Laboratori Nazionali di Frascati, Istituto Nazionali di Fisica Nucleare, U.F. Fisica Sanitaria, Via E. Fermi 40, 00040 Frascati, Roma (Italy); Amgarou, K.; Domingo, C. [Universitat Autonoma de Barcelona, Grup de Fisica de les Radiacions, Campus de Bellaterra, 08193 Barcelona (Spain); Vega C, H. R., E-mail: eduardo.gallego@upm.es [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Apdo. Postal 336, 98000 Zacatecas (Mexico)

    2012-10-15

    A new automated bench for irradiation, using a {sup 241}AmBe neutron source, has been installed in the neutronics hall at the Universidad Politecnica de Madrid (UPM). In order to determine the neutron field features on the bench a neutron spectrometry, using the Bonner sphere spectrometer, campaign was carried out with the participation of four research teams. Each team used their own spectrometer with different unfolding codes. The UPM-UAZ spectrometer has seven spheres with a {sup 6}Lil(Eu) scintillator, for unfolding this team used the BUNKIUT code. The INFN-LNF spectrometer has 10 spheres with a {sup 6}Lil(Eu) scintillator and the Fruit code was used for unfolding. The UAB team spectrometer has 11 with a {sup 3}He proportional counter, for unfolding this team used the Fruit code. The CIEMAT team spectrometer is 12 spheres with a {sup 3}He Sp 9 counter, for unfolding this team used the UMG code. The paper shows the main results obtained in terms of neutron spectra at fixed distances from the source as well as the total neutron fluence rate and ambient dose equivalent rate H(10) determined from the spectra. The H(10) are compared with the readings of a neutron area monitor Lb 6411. (Author)

  7. Safety equipment list for 241-C-106 waste retrieval, Project W-320: Revision 1

    International Nuclear Information System (INIS)

    The goals of the C-106 sluicing operation are: (1) to stabilize the tank by reducing the heat load in the tank to less than 42 MJ/hr (40,000 Btu/hour), and (2) to initiate demonstration of single-shell tank (SST) retrieval technology. The purpose of this supporting document (SD) is as follows: (1) to provide safety classifications for items (systems, structures, equipment, components, or parts) for the waste retrieval sluicing system (WRSS), and (2) to document and methodology used to develop safety classifications. Appropriate references are made with regard to use of existing systems, structures, equipments, components, and parts for C-106 single-shell transfer tank located in the C Tank Farm, and 241-AY-102 (AY-102) double shell receiver tanks (DST) located in the Aging Waste Facility (AWF). The Waste Retrieval Sluicing System consists of two transfer lines that would connect the two tanks, one to carry the sluiced waste slurry to AY-102, and the other to return the supernatant liquid to C-106. The supernatant, or alternate fluid, will be used to mobilize waste in C-106 for the sluicing process. The equipment necessary for the WRSS include pumps in each tank, sluicers to direct the supernatant stream in C-106, a slurry distributor in AY-102, HVAC for C-106, instrumentation and control devices, and other existing components as required

  8. Tank 241-S-106, cores 183, 184 and 187 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Esch, R.A.

    1997-06-30

    This document is the final laboratory report for tank 241-S-106 push mode core segments collected between February 12, 1997 and March 21, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (TSAP), the Tank Safety Screening Data Quality Objective (Safety DQO), the Historical Model Evaluation Data Requirements (Historical DQO) and the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO). The analytical results are included in Table 1. Six of the twenty-four subsamples submitted for the differential scanning calorimetry (DSC) analysis exceeded the notification limit of 480 Joules/g stated in the DQO. Appropriate notifications were made. Total Organic Carbon (TOC) analyses were performed on all samples that produced exotherms during the DSC analysis. All results were less than the notification limit of three weight percent TOC. No cyanide analysis was performed, per agreement with the Tank Safety Program. None of the samples submitted for Total Alpha Activity exceeded notification limits as stated in the TSAP. Statistical evaluation of results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. No core composites were created because there was insufficient solid material from any of the three core sampling events to generate a composite that would be representative of the tank contents.

  9. Dynamics of Crust Dissolution and Gas Release in Tank 241-SY-101

    Energy Technology Data Exchange (ETDEWEB)

    Rassat, Scot D.; Stewart, Charles W.; Wells, Beric E.; Kuhn, William L.; Antoniak, Zenen I.; Cuta, Judith M.; Recknagle, Kurtis P.; Terrones, Guillermo; Viswanathan, Vilayanur V.; Sukamto, Johanes H.; Mendoza, Donaldo P.

    2000-01-24

    Due primarily to an increase in floating crust thickness, the waste level in Tank 241-SY-101 has grown appreciably and the flammable gas volume stored in the crust has become a potential hazard. To remediate gas retention in the crust and the potential for buoyant displacement gas releases from the nonconvective layer at the bottom of the tank, SY-101 will be diluted to dissolve a large fraction of the solids that allow the waste to retain gas. The plan is to transfer some waste out and back-dilute with water in several steps. In this work, mechanisms and rates of waste solids dissolution and gas releases are evaluated theoretically and experimentally. Particular emphasis is given to crust dissolution processes and associated gas releases, although dissolution and gas release from the mixed-slurry and nonconvective layers are also considered. The release of hydrogen gas to the tank domespace is modeled for a number of scenarios. Under the tank conditions expected at the time of back-dilution, no plausible continuous or sudden gas release scenarios resulting in flammable hydrogen concentrations were identified.

  10. Transient grating spectroscopy in photosynthetic purple bacteria Rhodobacter sphaeroides 2.4.1

    Energy Technology Data Exchange (ETDEWEB)

    Sugisaki, Mitsuru, E-mail: mitsuru@sci.osaka-cu.ac.j [CREST-JST and Graduate School of Science, Osaka City University, 3-3-138 Sugimoto, Sumiyoshi, Osaka 558-8585 (Japan); Fujiwara, Masazumi; Fujii, Ritsuko [CREST-JST and Graduate School of Science, Osaka City University, 3-3-138 Sugimoto, Sumiyoshi, Osaka 558-8585 (Japan); Nakagawa, Katsunori; Nango, Mamoru [CREST-JST and Graduate School of Engineering, Nagoya Institute of Technology, Gokiso, Showa, Nagoya 466-8555 (Japan); Cogdell, Richard J. [Glasgow Biomedical Research Centre, IBLS, University of Glasgow, 126 University Place, Glasgow G12 8TA, Scotland (United Kingdom); Hashimoto, Hideki [CREST-JST and Graduate School of Science, Osaka City University, 3-3-138 Sugimoto, Sumiyoshi, Osaka 558-8585 (Japan)

    2009-12-15

    The vibronic coherence of photosynthetic pigment-protein complexes has been investigated by means of transient grating spectroscopy using sub 20 fs optical pulses. In the present work, we focus our attention on the LH2 antenna complexes from Rhodobacter sphaeroides 2.4.1 because the information about their structure investigated by the electron and atomic force microscopy is available and the electric levels of pigments are well resolved, resulting in clear absorption spectrum. The vibronic coherent oscillations with a period of a few tens of femtoseconds have been clearly observed. We found that the temporal change of the coherent oscillations reflects the vibrational relaxation in the ground state. Calculations based on the Brownian oscillator model were performed under the impulsive excitation limit. The spectral density has been determined from the Raman measurement of spheroidene. Good agreement between the calculation and the experimental results has been achieved in the linear absorption spectrum and transient grating signal, which strongly supports the validity of our model.

  11. Distribution of 239Pu and 241Am in the human skeleton

    International Nuclear Information System (INIS)

    The 241Am and 239Pu distribution in the skeletons of two former nuclear workers has been measured. The skeletons of both individuals appear to be within normal limits for Caucasian men about 50 y old. Both had lower limb bones that were heavier than the age controls and Case I had upper-body bones that were lighter than the age control group. The distribution of americium in the skeleton of Case I, 25 years post exposure, indicated that a more rapid turnover of initially deposited americium on the bone surfaces of cancellous bone, as compared to that deposited on the bone surfaces of compact bone, had occurred. This resulted in a larger proportion of americium located in the compact bone of the extremities and a lesser quantity in the more cancellous bones of the vertebral column, pelvis and rib cage. A similar shift in the distribution of plutonium occurred in Case II in the 35 y since initial deposition, but at a slower rate than that for americium. The ratio of each actinide in the liver to that in the systemic system (liver content/systemic system content) was 0.065 and 0.436, for americium and plutonium, respectively, suggesting that a much more rapid turnover of americium in the liver, compared to plutonium, provided a much larger fraction of that nuclide for circulatory feedback to the remodeling skeletal system. 8 references, 3 tables

  12. Hanford Tank 241-C-106: Impact of Cement Reactions on Release of Contaminants from Residual Waste

    Energy Technology Data Exchange (ETDEWEB)

    Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

    2006-09-01

    The CH2M HILL Hanford Group, Inc. (CH2M HILL) is producing risk/performance assessments to support the closure of single-shell tanks at the U.S. Department of Energy's Hanford Site. As part of this effort, staff at Pacific Northwest National Laboratory were asked to develop release models for contaminants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. Initial work to produce release models was conducted on residual tank sludge using pure water as the leaching agent. The results were reported in an earlier report. The decision has now been made to close the tanks after waste retrieval with a cementitious grout to minimize infiltration and maintain the physical integrity of the tanks. This report describes testing of the residual waste with a leaching solution that simulates the composition of water passing through the grout and contacting the residual waste at the bottom of the tank.

  13. Tank waste remediation system (TWRS) privatization contractor samples waste envelope D material 241-C-106

    Energy Technology Data Exchange (ETDEWEB)

    Esch, R.A.

    1997-04-14

    This report represents the Final Analytical Report on Tank Waste Remediation System (TWRS) Privatization Contractor Samples for Waste Envelope D. All work was conducted in accordance with ''Addendum 1 of the Letter of Instruction (LOI) for TWRS Privatization Contractor Samples Addressing Waste Envelope D Materials - Revision 0, Revision 1, and Revision 2.'' (Jones 1996, Wiemers 1996a, Wiemers 1996b) Tank 241-C-1 06 (C-106) was selected by TWRS Privatization for the Part 1A Envelope D high-level waste demonstration. Twenty bottles of Tank C-106 material were collected by Westinghouse Hanford Company using a grab sampling technique and transferred to the 325 building for processing by the Pacific Northwest National Laboratory (PNNL). At the 325 building, the contents of the twenty bottles were combined into a single Initial Composite Material. This composite was subsampled for the laboratory-scale screening test and characterization testing, and the remainder was transferred to the 324 building for bench-scale preparation of the Privatization Contractor samples.

  14. Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-103

    Energy Technology Data Exchange (ETDEWEB)

    Hassan, N.M.

    2000-07-27

    The pretreatment process for BNFL, Inc.'s Hanford River Protection Project is to provide decontaminated low activity waste and concentrated eluate streams for vitrification into low activity and high level waste glass, respectively. The pretreatment includes sludge washing, filtration, precipitation, and ion exchange processes to remove entrained solids, cesium, transuranics, technetium, and strontium. The ion exchange removal of cesium (Cs) and technetium (Tc) ions is accomplished by using SuperLig 644, and 639 resins from IBC Advanced Technologies, American Fork, Utah. The resins were shown to selectively remove cesium and technetium (as pertechnetate), from alkaline salt solutions. The efficiency of ion exchange column loading and elution is a complex function involving feed compositions, equilibrium and kinetic behavior of ion exchange resins, diffusion, and the ionic strength and pH of the aqueous solution. A previous experimental program completed at the Savannah River Technology Center demonstrated the conceptualized flow sheet parameters with a similar Hanford tank sample (241-AW-101). Those experiments included determination of Cs and Tc batch distribution coefficients by SuperLig 644 and 639 resins and demonstration of small-scale column breakthrough and elution. The experimental findings were used in support of preliminary design bases and pretreatment flow sheet development by BNFL, Inc.

  15. Laboratory testing of ozone oxidation of Hanford Site waste from Tank 241-SY-101

    Energy Technology Data Exchange (ETDEWEB)

    Delegard, C.H.; Stubbs, A.M.; Bolling, S.D.

    1993-12-14

    Ozone was investigated as a reagent to oxidize and destroy organic species present in simulated and genuine waste from Hanford Site Tank 241-SY-101 (Tank 101-SY). Two high-shear mixing apparatus were tested to perform the gas-to-solution mass transfer necessary to achieve efficient use of the ozone reagent. Oxidations of nitrite (to form nitrate) and organic species were observed. The organics oxidized to form carbonate and oxalate as well as nitrate and nitrogen gas from nitrogen associated with the organic. oxidations of metal species also were observed directly or inferred by solubilities. The chemical reaction stoichiometries were consistent with reduction of one oxygen atom per ozone molecule. Acetate, oxalate, and formate were found to comprise about 40% of the genuine waste`s total organic carbon (TOC) concentration. Ozonation was found to be chemically feasible for destroying organic species (except oxalate) present in the wastes in Tank 101-SY. The simulated waste formulation used in these studies credibly modelled the ozonation behavior of the genuine waste.

  16. Laboratory testing of ozone oxidation of Hanford Site waste from Tank 241-SY-101

    International Nuclear Information System (INIS)

    Ozone was investigated as a reagent to oxidize and destroy organic species present in simulated and genuine waste from Hanford Site Tank 241-SY-101 (Tank 101-SY). Two high-shear mixing apparatus were tested to perform the gas-to-solution mass transfer necessary to achieve efficient use of the ozone reagent. Oxidations of nitrite (to form nitrate) and organic species were observed. The organics oxidized to form carbonate and oxalate as well as nitrate and nitrogen gas from nitrogen associated with the organic. oxidations of metal species also were observed directly or inferred by solubilities. The chemical reaction stoichiometries were consistent with reduction of one oxygen atom per ozone molecule. Acetate, oxalate, and formate were found to comprise about 40% of the genuine waste's total organic carbon (TOC) concentration. Ozonation was found to be chemically feasible for destroying organic species (except oxalate) present in the wastes in Tank 101-SY. The simulated waste formulation used in these studies credibly modelled the ozonation behavior of the genuine waste

  17. Results Of Physicochemical Characterization And Caustic Dissolution Tests On Tank 241-C-108 Heel Solids

    International Nuclear Information System (INIS)

    Based on an ENRAF waste surface measurement taken February 1, 2009, double-shell tank (DST) 241-AN-106 (AN-106) contained approximately 278.98 inches (793 kgal) of waste. A zip cord measurement from the tank on February 1, 2009, indicated a settled solids layer of 91.7 inches in height (280 kgal). The supernatant layer in February 2009, by difference, was approximately 187 inches deep (514 kgal). Laboratory results from AN-106 February 1, 2009 (see Table 2) grab samples indicated the supernatant was below the chemistry limit that applied at the time as identified in HNF-SD-WM-TSR-006, Tank Farms Technical Safety Requirements, Administrative Control (AC) 5.16, 'Corrosion Mitigation Controls.' (The limits have since been removed from the Technical Safety Requirements (TSR) and are captured in OSD-T-151-00007, Operating Specifications for the Double-Shell Storage Tanks.) Problem evaluation request WRPS-PER-2009-0218 was submitted February 9, 2009, to document the finding that the supernatant chemistry for grab samples taken from the middle and upper regions of the supernatant was noncompliant with the chemistry control limits. The lab results for the samples taken from the bottom region of the supernatant met AC 5.16 limits.

  18. RESULTS OF PHYSICOCHEMICAL CHARACTERIZATION AND CAUSTIC DISSOLUTION TESTS ON TANK 241-C-108 HEEL SOLIDS

    Energy Technology Data Exchange (ETDEWEB)

    CALLAWAY WS; HUBER HJ

    2010-07-01

    Based on an ENRAF waste surface measurement taken February 1, 2009, double-shell tank (DST) 241-AN-106 (AN-106) contained approximately 278.98 inches (793 kgal) of waste. A zip cord measurement from the tank on February 1, 2009, indicated a settled solids layer of 91.7 inches in height (280 kgal). The supernatant layer in February 2009, by difference, was approximately 187 inches deep (514 kgal). Laboratory results from AN-106 February 1, 2009 (see Table 2) grab samples indicated the supernatant was below the chemistry limit that applied at the time as identified in HNF-SD-WM-TSR-006, Tank Farms Technical Safety Requirements, Administrative Control (AC) 5.16, 'Corrosion Mitigation Controls.' (The limits have since been removed from the Technical Safety Requirements (TSR) and are captured in OSD-T-151-00007, Operating Specifications for the Double-Shell Storage Tanks.) Problem evaluation request WRPS-PER-2009-0218 was submitted February 9, 2009, to document the finding that the supernatant chemistry for grab samples taken from the middle and upper regions of the supernatant was noncompliant with the chemistry control limits. The lab results for the samples taken from the bottom region of the supernatant met AC 5.16 limits.

  19. Evaluation of the thermal cross sections of 239Pu and 241Pu

    International Nuclear Information System (INIS)

    The thermal neutron cross sections of the isotopes 239Pu and 241Pu have been evaluated in the thermal neutron energy region below 1.0 eV. The method of evaluation fitted energy-dependent data constrained by a modified Adler-Adler multilevel resonance fission and capture formalism and multilevel Breit-Wigner scattering theory. The energy dependence of the number of neutrons per fission was prescribed in the theory by introducing nu as fitted resonance spin-dependent values. The data were fitted in a resonance parameter fitting code, RPFC, using the method of maximum likelihood. The code fits simultaneously the total and partial energy-dependent cross section data to the theory. The types of data explicitly fitted are total, fission, capture, total scattering, coherent scattering, and absorption cross sections plus the quantities alpha, total nu and eta. Relative energy-dependent data with precision errors are fitted along with absolute values and errors at chosen energies. RPFC also allows energy-scale adjustment and Doppler broadening of selected data sets, and fits correlated data of two isotopes simultaneously. Reference experimental data bases of original data plus condensed and modified data were assembled for the evaluation for each isotope. 19 figures, 9 tables

  20. Solubilization of 241AmO2 in alveolar macrophage cultures

    International Nuclear Information System (INIS)

    Cultured rabbit alveolar macrophages were used to study the effect of phagocytosis on the solubilization of 241AmO2. A comparison was made of the solubility of phagocytized AmO2 and AmO2 in cell-free media, in the presence and absence of 0.1 mM DTPA. A time-dependent increase of 26% in the soluble (0.1-μm filtrate) intracellular americium fraction was seen in macrophages cultured for 3 days. The addition of 0.1mM DTPA to culture medium resulted in an increase of 36% over the same time period. In contrast, cell-free media without DTPA resulted in less than a 2% increase in solubility after 4 days of incubation, while addition of 0.1mM DTPA resulted in a 5% increase over the same time period. These results indicate cell-mediated solbuilization of phagocytized AmO2 by macrophages

  1. Transient grating spectroscopy in photosynthetic purple bacteria Rhodobacter sphaeroides 2.4.1

    International Nuclear Information System (INIS)

    The vibronic coherence of photosynthetic pigment-protein complexes has been investigated by means of transient grating spectroscopy using sub 20 fs optical pulses. In the present work, we focus our attention on the LH2 antenna complexes from Rhodobacter sphaeroides 2.4.1 because the information about their structure investigated by the electron and atomic force microscopy is available and the electric levels of pigments are well resolved, resulting in clear absorption spectrum. The vibronic coherent oscillations with a period of a few tens of femtoseconds have been clearly observed. We found that the temporal change of the coherent oscillations reflects the vibrational relaxation in the ground state. Calculations based on the Brownian oscillator model were performed under the impulsive excitation limit. The spectral density has been determined from the Raman measurement of spheroidene. Good agreement between the calculation and the experimental results has been achieved in the linear absorption spectrum and transient grating signal, which strongly supports the validity of our model.

  2. Probabilistic safety assessment for Hanford high-level waste tank 241-SY-101

    Energy Technology Data Exchange (ETDEWEB)

    MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W. [Los Alamos National Lab., NM (United States); Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J. [PLG, Inc., Newport Beach, CA (United States)

    1994-05-01

    Los Alamos National Laboratory (Los Alamos) is performing a comprehensive probabilistic safety assessment (PSA), which will include consideration of external events for the 18 tank farms at the Hanford Site. This effort is sponsored by the Department of Energy (DOE/EM, EM-36). Even though the methodology described herein will be applied to the entire tank farm, this report focuses only on the risk from the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases ({open_quotes}burps{close_quotes}) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed first because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is being conducted in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. At the Hanford Site there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/salt cake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is about 60 million gal., which contains approximately 120 million Ci of radioactivity.

  3. Soil structure interaction analysis for the Hanford Site 241-SY-101 double-shell waste storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Giller, R.A.; Weiner, E.O.

    1991-09-01

    The 241-SY-101 tank is a double-shell waste storage tank buried in the 241-SY tank farm in the 200 West Area of the Hanford Site. This analysis addresses the effects of seismic soil-structure interaction on the tank structure and includes a parametric soil-structure interaction study addressing three configurations: two-dimensional soil structure, a two-dimensional structure-soil-structure, and a three-dimensional soil-structure interaction. This study was designed to determine an optimal method for addressing seismic-soil effects on underground storage tanks. The computer programs calculate seismic-soil pressures on the double-steel tank walls and seismic acceleration response spectra in the tank. The results of this soil-structure interaction parametric study as produced by the computer programs are given in terms of seismic soil pressures and response spectra. The conclusions of this soil-structure interaction evaluation are that dynamically calculated soil pressures in the 241-SY-101 tank are significantly reduced from those using standard hand calculation methods and that seismic evaluation of underground double-shell waste storage tanks must consider soil-structure interaction effects in order to predict conservative structural response. Appendixes supporting this study are available in Volume 2 of this report.

  4. Soil structure interaction analysis for the Hanford Site 241-SY-101 double-shell waste storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Giller, R.A.; Weiner, E.O.

    1991-09-01

    The 241-SY-101 tank is a double-shell waste storage tank buried in the 241-SY tank farm in the 200 West Area of the Hanford Site. This analysis addresses the effects of seismic soil-structure interaction on the tank structure and includes a parametric soil-structure interaction study addressing three configurations: two-dimensional soil structure, a two-dimensional structure-soil-structure, and a three-dimensional soil-structure interaction. This study was designed to determine an optimal method for addressing seismic-soil effects on underground storage tanks. The computer programs calculate seismic-soil pressures on the double-shell tank walls and and seismic acceleration response spectra in the tank. The results of this soil-structure interaction parametric study as produced by the computer programs are given in terms of seismic soil pressures and response spectra. The conclusions of this soil-structure interaction evaluation are that dynamically calculated soil pressures in the 241-SY-101 tank are significantly reduce from those using standard hand calculation methods and that seismic evaluation of underground double-shell waste storage tanks must consider soil-structure interaction effects in order to predict conservative structural response. Appendixes supporting this study are available in Volume 2 of this report.

  5. Influence of self-absorption corrections in the quantification of 210Pb and 241Am for sediment dating

    Science.gov (United States)

    González, J. Carrazana; Vargas, M. Jurado; Castillo, R. Gil

    2016-10-01

    The nuclides 210Pb and 241Am are used in geochronological studies. In this work, we examine the influence of the sediment chemical composition on the self-attenuation corrections needed for the accurate determination of specific activities for 210Pb and 241Am used for sediment dating. A theoretical exercise was carried out evaluating the relative bias obtained by four different analytical laboratories in the quantification of the 210Pb and 241Am activity concentration by gamma-ray spectrometry. The laboratories considered the same density for the sediment sample, but each one used a different chemical composition in the Monte Carlo calculations, and six different HPGe detectors (including n and p-types). An estimate of the impact that would have the relative biases found in the estimation of the 210Pb sediment ages, applying the Constant Rate of Supply (CRS) dating model, is also given. In addition, the performance scores that the laboratories would have obtained in a hypothetical IAEA proficiency test are also presented.

  6. Structural analysis of Hanford's single-shell 241-C-106 tank a first step toward waste-tank remediation

    International Nuclear Information System (INIS)

    The buried single-shell waste tank 241-C-106, located at the U.S. Department of Energy's Hanford Site, has been a repository for various liquid radioactive waste materials since its construction in 1943. A first step toward waste tank remediation is demonstrating that remediation activities can be performed safely. Determination of the current structural capacity of this high-heat tank is an important element in this assessment. A structural finite-element model of tank 241-C-106 has been developed to assess the tank's structural integrity with respect to in situ conditions and additional remediation surface loads. To predict structural integrity realistically, the model appropriately addresses two complex issues: (1) surrounding soil-tank interaction associated with thermal expansion cycling and surcharge load distribution and (2) concrete-property degradation and creep resulting from exposure to high temperatures generated by the waste. This paper describes the development of the 241-C-106 structural model, analysis methodology, and tank-specific structural acceptance criteria

  7. Absorption cross section measurements of oxygen in the wavelength region 195-241 nm of the Herzberg continuum

    Science.gov (United States)

    Cheung, A. S.-C.; Yoshino, K.; Parkinson, W. H.; Freeman, D. E.; Guberman, S. L.

    1986-01-01

    The continuous absorption cross section of oxygen in the region 205-241 nm is studied as a function of path length and oxygen pressure. The technique used to study the continuous absorption cross section is described. Cross section measurements of oxygen in the wavelength region 193-205 nm obtained by Cheung et al. (1984) are applied in this experiment. The measured cross section is analyzed in terms of a Herzberg continuum and a pressure-dependent continuum. The total measured continuum cross section, the cross section involving two molecules of O2, and the Herzberg continuum absorption cross section values are calculated. It is observed that the Herzberg continuum cross section of oxygen values measured at 1 nm intervals in the region 195-241 nm, increase from 6.3 x 10 to the -24th sq cm at 195 nm to a maximum of 6.6 x 10 to the -24th sq cm at 201 nm and then decrease to 0.85 x 10 to the -24th sq cm at 241 nm. The Herzberg values are compared with data from previous investigations and the values correlate well.

  8. Soil structure interaction analysis for the Hanford Site 241-SY-101 double-shell waste storage tanks

    International Nuclear Information System (INIS)

    The 241-SY-101 tank is a double-shell waste storage tank buried in the 241-SY tank farm in the 200 West Area of the Hanford Site. This analysis addresses the effects of seismic soil-structure interaction on the tank structure and includes a parametric soil-structure interaction study addressing three configurations: two-dimensional soil structure, a two-dimensional structure-soil-structure, and a three-dimensional soil-structure interaction. This study was designed to determine an optimal method for addressing seismic-soil effects on underground storage tanks. The computer programs calculate seismic-soil pressures on the double-shell tank walls and and seismic acceleration response spectra in the tank. The results of this soil-structure interaction parametric study as produced by the computer programs are given in terms of seismic soil pressures and response spectra. The conclusions of this soil-structure interaction evaluation are that dynamically calculated soil pressures in the 241-SY-101 tank are significantly reduce from those using standard hand calculation methods and that seismic evaluation of underground double-shell waste storage tanks must consider soil-structure interaction effects in order to predict conservative structural response. Appendixes supporting this study are available in Volume 2 of this report

  9. Influence of the environmental conditions on the transfer factors of Am-241, Co-60 and Cs-137 in fluvisol soil

    International Nuclear Information System (INIS)

    Full text: Transfer factors (TFs) of the radionuclides are used to evaluate the biological uptake and the distribution of radioactive contaminants from soil to vegetation. They are defined as the ratio of the specific activity (Bq/g) of the radionuclide in a given plant species and its specific activity in the soil. TFs depend on the geochemical properties of the radionuclides and on the soil characteristics. The sharp variations of the environmental temperature and precipitations may alter the soil properties and influence the geochemical fractionation of the radionuclides, thus changing their TFs. This paper presents the changes of the geochemical fractionation of 241Am, 60Co and 137Cs in Fluvisol soil as a result of temperature increase, freezing and water deficiency. The fractionation of 241Am and 60Co under different conditions was studied using two sequential extraction procedures. The exchangeable 137Cs was determined after extraction with 1 M NH4NO3. The influence of the environmental temperature and soil drought on the TFs of the radionuclides from the Fluvisol soil to grass was evaluated. The radioactivity of the leachants was measured by gamma-spectrometry. The results showed that the conditioning at higher temperature or soil drought increased the mobility of 241Am and 137Cs. The temperature raise caused decrease of the mobile and bioavailable forms of 60Co. The conditioning at sharp temperature increase led to higher values of the TFs of the studied radionuclides. This effect was highest for 137Cs. key words: transfer factors, radionuclides, Fluvisol soil

  10. New source moderator geometry to improve performance of 252Cf and 241Am Be source-based PGNAA setups

    Science.gov (United States)

    Naqvi, A. A.; Abdelmonem, M. S.; Al-Misned, Ghada; Al-Ghamdi, Hanan

    2006-06-01

    The gamma ray yield from a 252Cf and a 241Am-Be source-based Prompt Gamma Ray Activation Analysis (PGNAA) setup has been observed to increase with enclosing their neutrons sources in a high-density polyethylene moderator. The prompt gamma rays yield from both setups depends upon the moderator length and the source position in it. For both setups, the optimum moderator length is found to be 7 cm. The optimum position of the neutron source inside moderator of the 252Cf and the 241Am-Be source-based PGNAA setups was found to be at a distance of 0.5 and 0.75 cm from the moderator-end facing the sample, respectively. Due to enclosure of the source in the moderator, about three-fold increase has been observed in the yield of prompt gamma rays from a Portland cement sample of a 252Cf and a 241Am-Be source-based PGNAA setups.

  11. Characterization of genes encoding dimethyl sulfoxide reductase of Rhodobacter sphaeroides 2.4.1T: an essential metabolic gene function encoded on chromosome II.

    OpenAIRE

    Mouncey, N J; Choudhary, M.; Kaplan, S.

    1997-01-01

    Rhodobacter sphaeroides 2.4.1T is a purple nonsulfur facultative phototrophic bacterium which exhibits remarkable metabolic diversity as well as genomic complexity. Under anoxic conditions, in the absence of light and the presence of dimethyl sulfoxide (DMSO) or trimethylamine N-oxide (TMAO), R. sphaeroides 2.4.1T utilizes DMSO or TMAO as the terminal electron acceptor for anaerobic respiration, which is mediated by the molybdoenzyme DMSO reductase. Sequencing of a 13-kb region of chromosome ...

  12. Discovery of the First Leaking Double-Shell Tank - Hanford Tank 241-AY-102

    Energy Technology Data Exchange (ETDEWEB)

    Harrington, Stephanie J.; Sams, Terry L.

    2013-11-06

    A routine video inspection of the annulus space between the primary tank and secondary liner of double-shell tank 241-AY-102 was performed in August 2012. During the inspection, unexpected material was discovered. A subsequent video inspection revealed additional unexpected material on the opposite side of the tank, none of which had been observed during inspections performed in December 2006 and January 2007. A formal leak assessment team was established to review the tank's construction and operating histories, and preparations for sampling and analysis began to determine the material's origin. A new sampling device was required to collect material from locations that were inaccessible to the available sampler. Following its design and fabrication, a mock-up test was performed for the new sampling tool to ensure its functionality and capability of performing the required tasks. Within three months of the discovery of the unexpected material, sampling tools were deployed, material was collected, and analyses were performed. Results indicated that some of the unknown material was indicative of soil, whereas the remainder was consistent with tank waste. This, along with the analyses performed by the leak assessment team on the tank's construction history, lead to the conclusion that the primary tank was leaking into the annulus. Several issues were encountered during the deployment of the samplers into the annulus. As this was the first time samples had been required from the annulus of a double-shell tank, a formal lessons learned was created concerning designing equipment for unique purposes under time constraints.

  13. Tank 241C106 structural evaluation in support of Project W320 retrieval

    International Nuclear Information System (INIS)

    Tank 241C106 structural evaluation to support W320. It includes ACI code input and riser evaluations. This work uses the in situ conditions established by Julyk to develop a three-dimensional model of the tank. Non-axisymmetric loads associated with retrieval activities are applied to assess their influence on structural integrity of the tank. This study addresses loads associated with normal opertion and credible accident scenarios. The concrete structure of tank C106 is classified as a Safety Class I non-reactor structure in accordance with the definition given in SDC 4.1. The operating specifications document (OSD) limits applicable to tank C106 include a live load limit for the C Tank Farm of 100 tons. For the technical basis of this limit, the OSD references SD-RE-TI-012, which qualifies the 100 tons as that distributed over a 10-ft radius. However, there is no specification for a uniform live load that would accompany natural hazard phenomena such as snow or ash fall. There is no specific guidance on crane loads applied at the surface outside the tank radius. Further, there is no record of any seismic analysis of tanks in the C Tank Farm. The analysis documented in this report evaluates nonseismic conditions that include a concentrated live load, a uniform live load, and a crane load, in addition to the in situ loads. The model documented in this study also is used to provide the nonseismic stress contribution to the seismic load combination documented by Wallace

  14. Tank 241-AZ-101 criticality assessment resulting from pump jet mixing: Sludge mixing simulation

    International Nuclear Information System (INIS)

    Tank 241-AZ-101 (AZ-101) is one of 28 double-shell tanks located in the AZ farm in the Hanford Site's 200 East Area. The tank contains a significant quantity of fissile materials, including an estimated 9.782 kg of plutonium. Before beginning jet pump mixing for mitigative purposes, the operations must be evaluated to demonstrate that they will be subcritical under both normal and credible abnormal conditions. The main objective of this study was to address a concern about whether two 300-hp pumps with four rotating 18.3-m/s (60-ft/s) jets can concentrate plutonium in their pump housings during mixer pump operation and cause a criticality. The three-dimensional simulation was performed with the time-varying TEMPEST code to determine how much the pump jet mixing of Tank AZ-101 will concentrate plutonium in the pump housing. The AZ-101 model predicted that the total amount of plutonium within the pump housing peaks at 75 g at 10 simulation seconds and decreases to less than 10 g at four minutes. The plutonium concentration in the entire pump housing peaks at 0.60 g/L at 10 simulation seconds and is reduced to below 0.1 g/L after four minutes. Since the minimum critical concentration of plutonium is 2.6 g/L, and the minimum critical plutonium mass under idealized plutonium-water conditions is 520 g, these predicted maximums in the pump housing are much lower than the minimum plutonium conditions needed to reach a criticality level. The initial plutonium maximum of 1.88 g/L still results in safety factor of 4.3 in the pump housing during the pump jet mixing operation

  15. New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography (Presentation)

    International Nuclear Information System (INIS)

    Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237Np a 241Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239Np a 237Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242Pu and 239Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239Np was obtained by separation from the parent radionuclide 243Am, which is in radioactive equilibrium to 239Np. The average yield of chemical separation was 69,3% for 239Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240Pu (95,0 ± 3,5)% and 237Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

  16. New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography

    International Nuclear Information System (INIS)

    Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237Np a 241Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239Np a 237Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242Pu and 239Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239Np was obtained by separation from the parent radionuclide 243Am, which is in radioactive equilibrium to 239Np. The average yield of chemical separation was 69,3% for 239Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240Pu (95,0 ± 3,5)% and 237Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

  17. Evaluation of the contamination risk by 241AM from lightning rods disposed at uncontrolled garbage dump

    International Nuclear Information System (INIS)

    Radioactive lightning rods were manufactured in Brazil until 1989, when the licenses for using radioactive sources in these products were lifted by the national nuclear authority. Since then, radioactive devices have been replaced by Franklin type one and collected as radioactive waste. However, only 23 percent of the estimated total number of installed rods was delivered to Brazilian Nuclear Commission (Comissao Nacional de Energia Nuclear - CNEN). This situation is of concern as there is a possibility of the rods being discarded as domestic waste, considering that in Brazil, 63.6 percent of the municipal solid waste is disposed at uncontrolled garbage dump, according to Instituto Brasileiro de Geografia e Estatistica (IBGE) in 2000. In addition, americium, the most common employed radionuclide, is classified as a high toxicity element, when ingested or inhaled. In the present study, it was performed migration experiments of Am-241 by lysimeter system in order to evaluate the risk of contamination caused by radioactive lightning rods disposed as a common solid waste. Sources removed from lightning rods were placed inside lysimeters filled with organic waste, collected at the restaurant of Instituto de Pesquisas Energeticas e Nucleares, IPEN-CNEN/SP, and the generated leachate was periodically analyzed to determine its characteristics such as pH, redox potential, solid content and concentration of the radioactive material. Microbial growth was also evaluated by counting the number of colony forming units. The equivalent dose to members of the public has been calculated considering the ingestion of drinking water, the most probable mode of exposure. The final result was about 145 times below the effective dose limit of 1 mSv.year-1 for members of the public, established by the International Commission on Radiological Protection (ICRP), demonstrating that the risk caused by lightning rods disposed at uncontrolled garbage dump is low. (author)

  18. Origins of volatile organic compounds emerging from tank 241-C-106 during sluicing

    Energy Technology Data Exchange (ETDEWEB)

    STAUFFER, L.A.

    1999-06-02

    Unexpectedly high concentrations of inorganic gases and volatile organic compounds (VOC) were released from the ventilation stack of tank 241-C-106 during sluicing operations on November 18, 1998. Workers experienced serious discomfort. They reported an obnoxious acrid odor and the 450 ppm VOC in ventilation stack 296-C-006 exceeded the level approved in the air discharge permit. Consequently, the operation was terminated. Subsequent analyses of samples collected opportunistically from the stack indicated many organic compounds including heptenes, heptanones, and normal paraffin hydrocarbons (NPH) and their remnants were present. Subsequently, a process test designed to avoid unnecessary worker exposure and enable collection of analytical samples from the stack, the breathing area, and the receiver tank was conducted on December 16, 1998. The samples obtained during that operation, in which the maximum VOC content of the stack was approximately 35 ppm, have been analyzed by teams at Pacific Northwest National Laboratory and Special Analytic Services (SAS). This report examines the results of these investigations. Future revisions of the report will examine the analytical results obtained for samples collected during sluicing operations in March. This report contains the available evidence about the source term for these emissions. Chapter 2 covers characterization work, including historical information about the layers of waste in the tank, the location of organic compounds in these layers, the total organic carbon (TOC) content and the speciation of organic compounds. Chapter 3 covers the data for the samples from the ventilation stack, which has the highest concentrations of organic compounds. Chapter 4 contains an interpretation of the information connecting the composition of the organic emissions with the composition of the original source term. Chapter 5 summarizes the characterization work, the sample data, and the interpretation of the results.

  19. Tank characterization report for Single-Shell Tank 241-BX-107

    Energy Technology Data Exchange (ETDEWEB)

    Raphael, G.F.

    1994-09-01

    This study examined and assessed the status, safety issues, composition, and distribution of the wastes contained in the tank 241-BX-107. Historical and most recent information, ranging from engineering structural assessment experiments, process history, monitoring and remediation activities, to analytical core sample data, were compiled and interpreted in an effort to develop a realistic, contemporary profile for the tank BX-107 contents. The results of this is study revealed that tank BX-107, a 2,006,050 L (530,000 gal) cylindrical single-shell, dished-bottom carbon-steel tank in the 200 East Area of the Hanford Site, was classified as sound. It has been interim stabilized and thus contains less than 189,250 L (50,000 gal) of interstitial liquid, and less than 18,925 L (5,000 gal) of supernatant. It has also been partially interim isolated, whereby all inlets to the tank are sealed to prevent inadvertent addition of liquid. At a residual waste level of {approximately}3.07 m (120.7 {+-} 2 in. from sidewall bottom or {approximately}132.9 in. from center bottom), it is estimated that the tank BX-107 contents are equivalent to 1,305,825 L (345,000 gal). The vapor space pressure is at atmospheric. The latest temperature readings, which were taken in July 1994, show a moderate temperature value of 19{degrees}C (66{degrees}F). Two supernatant samples were collected in 1974 and 1990, prior to interim stabilization. Sludge core samples were obtained in 1979 and 1992.

  20. Results of Characterization and Retrieval Testing on Tank 241-C-109 Heel Solids

    Energy Technology Data Exchange (ETDEWEB)

    Callaway, William S.

    2013-09-26

    Eight samples of heel solids from tank 241-C-109 were delivered to the 222-S Laboratory for characterization and dissolution testing. After being drained thoroughly, one-half to two-thirds of the solids were off-white to tan solids that, visually, were fairly evenly graded in size from coarse silt (30-60 μm) to medium pebbles (8-16 mm). The remaining solids were mostly strongly cemented aggregates ranging from coarse pebbles (16-32 mm) to fine cobbles (6-15 cm) in size. Solid phase characterization and chemical analysis indicated that the air-dry heel solids contained ≈58 wt% gibbsite [Al(OH){sub 3}] and ≈37 wt% natrophosphate [Na{sub 7}F(PO{sub 4}){sub 2}·19H{sub 2}O]. The strongly cemented aggregates were mostly fine-grained gibbsite cemented with additional gibbsite. Dissolution testing was performed on two test samples. One set of tests was performed on large pieces of aggregate solids removed from the heel solids samples. The other set of dissolution tests was performed on a composite sample prepared from well-drained, air-dry heel solids that were crushed to pass a 1/4-in. sieve. The bulk density of the composite sample was 2.04 g/mL. The dissolution tests included water dissolution followed by caustic dissolution testing. In each step of the three-step water dissolution tests, a volume of water approximately equal to 3 times the initial volume of the test solids was added. In each step, the test samples were gently but thoroughly mixed for approximately 2 days at an average ambient temperature of 25 °C. The caustic dissolution tests began with the addition of sufficient 49.6 wt% NaOH to the water dissolution residues to provide ≈3.1 moles of OH for each mole of Al estimated to have been present in the starting composite sample and ≈2.6 moles of OH for each mole of Al potentially present in the starting aggregate sample. Metathesis of gibbsite to sodium aluminate was then allowed to proceed over 10 days of gentle mixing of the

  1. Results of Characterization and Retrieval Testing on Tank 241-C-109 Heel Solids

    Energy Technology Data Exchange (ETDEWEB)

    Callaway, William S.

    2013-09-26

    Eight samples of heel solids from tank 241-C-109 were delivered to the 222-S Laboratory for characterization and dissolution testing. After being drained thoroughly, one-half to two-thirds of the solids were off-white to tan solids that, visually, were fairly evenly graded in size from coarse silt (30-60 μm) to medium pebbles (8-16 mm). The remaining solids were mostly strongly cemented aggregates ranging from coarse pebbles (16-32 mm) to fine cobbles (6-15 cm) in size. Solid phase characterization and chemical analysis indicated that the air-dry heel solids contained ≈58 wt% gibbsite [Al(OH){sub 3}] and ≈37 wt% natrophosphate [Na{sub 7}F(PO{sub 4}){sub 2}·19H{sub 2}O]. The strongly cemented aggregates were mostly fine-grained gibbsite cemented with additional gibbsite. Dissolution testing was performed on two test samples. One set of tests was performed on large pieces of aggregate solids removed from the heel solids samples. The other set of dissolution tests was performed on a composite sample prepared from well-drained, air-dry heel solids that were crushed to pass a 1/4-in. sieve. The bulk density of the composite sample was 2.04 g/mL. The dissolution tests included water dissolution followed by caustic dissolution testing. In each step of the three-step water dissolution tests, a volume of water approximately equal to 3 times the initial volume of the test solids was added. In each step, the test samples were gently but thoroughly mixed for approximately 2 days at an average ambient temperature of 25 °C. The caustic dissolution tests began with the addition of sufficient 49.6 wt% NaOH to the water dissolution residues to provide ≈3.1 moles of OH for each mole of Al estimated to have been present in the starting composite sample and ≈2.6 moles of OH for each mole of Al potentially present in the starting aggregate sample. Metathesis of gibbsite to sodium aluminate was then allowed to proceed over 10 days of gentle mixing of the

  2. Results of Characterization and Retrieval Testing on Tank 241-C-110 Heel Solids

    Energy Technology Data Exchange (ETDEWEB)

    Callaway, William S.

    2013-09-30

    Nine samples of heel solids from tank 241-C-110 were delivered to the 222-S Laboratory for characterization and dissolution testing. After being drained thoroughly, the sample solids were primarily white to light-brown with minor dark-colored inclusions. The maximum dimension of the majority of the solids was <2 mm; however, numerous pieces of aggregate, microcrystalline, and crystalline solids with maximum dimensions ranging from 5-70 mm were observed. In general, the larger pieces of aggregate solids were strongly cemented. Natrophosphate [Na{sub 7}F(PO{sub 4}){sub 2}°19H{sub 2}O] was the dominant solid phase identified in the heel solids. Results of chemical analyses suggested that 85-87 wt% of the heel solids were the fluoridephosphate double salt. The average bulk density measured for the heel solids was 1.689 g/mL; the reference density of natrophosphate is 1.71 g/mL. Dissolution tests on composite samples indicate that 94 to 97 wt% of the tank 241-C-110 heel solids can be retrieved by dissolution in water. Dissolution and recovery of the soluble components in 1 kg (0.59 L) of the heel solids required the addition of ≈9.5 kg (9.5 L) of water at 15 °C and ≈4.4 kg (4.45 L) of water at 45 °C. Calculations performed using the Environmental Simulation Program indicate that dissolution of the ≈0.86 kg of natrophosphate in each kilogram of the tank 241-C-110 heel solids would require ≈9.45 kg of water at 15 °C and ≈4.25 kg of water at 45 °C. The slightly larger quantities of water determined to be required to retrieve the soluble components in 1 kg of the heel solids are consistent with that required for the dissolution of solids composed mainly of natrophosphate with a major portion of the balance consisting of highly soluble sodium salts. At least 98% of the structural water, soluble phosphate, sodium, fluoride, nitrate, carbonate, nitrite, sulfate, oxalate, and chloride in the test composites was dissolved and recovered in the

  3. Role of ICAM-1 polymorphisms (G241R, K469E) in mediating its single-molecule binding ability: Atomic force microscopy measurements on living cells

    Energy Technology Data Exchange (ETDEWEB)

    Bai, Rui [Chinese (301) General Hospital, 28 Fuxing Road, Haidian District, Beijing 100853 (China); Yi, Shaoqiong [Beijing Institute of Biotechnology, 20 Dongdajie, Fengtai, Beijing 100071 (China); Zhang, Xuejie [Beijing National Laboratory for Molecular Sciences, Key Laboratory of Molecular Nanostructure and Nanotechnology, Institute of Chemistry Chinese Academy of Sciences, 2 Zhongguancun North 1st Street, Beijing 100190 (China); Liu, Huiliang, E-mail: lhl518@vip.sina.com [Department of Cardiology, The General Hospital of Chinese People’s Armed Police Forces, Beijing 100039 (China); Fang, Xiaohong, E-mail: xfang@iccas.ac.cn [Beijing National Laboratory for Molecular Sciences, Key Laboratory of Molecular Nanostructure and Nanotechnology, Institute of Chemistry Chinese Academy of Sciences, 2 Zhongguancun North 1st Street, Beijing 100190 (China)

    2014-06-13

    Highlights: • We evaluated both single molecule binding ability and expression level of 4 ICAM-1 mutations. • AFM was used to measure single-molecule binding ability on living cells. • The SNP of ICAM-1 may induce changes in expressions rather than single-molecule binding ability. - Abstract: Atherosclerosis (As) is characterized by chronic inflammation and is a major cause of human mortality. ICAM-1-mediated adhesion of leukocytes in vessel walls plays an important role in the pathogenesis of atherosclerosis. Two single nucleotide polymorphisms (SNPs) of human intercellular adhesion molecule-1 (ICAM-1), G241R and K469E, are associated with a number of inflammatory diseases. SNP induced changes in ICAM-1 function rely not only on the expression level but also on the single-molecule binding ability which may be affected by single molecule conformation variations such as protein splicing and folding. Previous studies have shown associations between G241R/K469E polymorphisms and ICAM-1 gene expression. Nevertheless, few studies have been done that focus on the single-molecule forces of the above SNPs and their ligands. In the current study, we evaluated both single molecule binding ability and expression level of 4 ICAM-1 mutations – GK (G241/K469), GE (G241/E469), RK (R241/K469) and RE (R241/E469). No difference in adhesion ability was observed via cell adhesion assay or atomic force microscopy (AFM) measurement when comparing the GK, GE, RK, or RE genotypes of ICAM-1 to each other. On the other hand, flow cytometry suggested that there was significantly higher expression of GE genotype of ICAM-1 on transfected CHO cells. Thus, we concluded that genetic susceptibility to diseases related to ICAM-1 polymorphisms, G241R or K469E, might be due to the different expressions of ICAM-1 variants rather than to the single-molecule binding ability of ICAM-1.

  4. Effect of bone-status on retention and distribution of americium-241 in bones of small rodents

    International Nuclear Information System (INIS)

    Forced physical exercise before and after application of americium-241 resulted in only small changes in bone-structure and behaviour of the radionuclide in bone. Feeding of a low phosphorus or low calcium diet resulted in an increased excretion of americium from bone, whereby Zn-DTPA as chelating agent removed an additional fraction of the radionuclide from bone. Low calcium diet and simultaneous continuous infusion of pharmacological doses of vitamin D-hormones didn't increase the excretion of americium more than the low calcium diet alone. (orig.)

  5. Parameter uncertainty analysis in the task of internal dose reconstruction based on 241Am organ activity measurements

    International Nuclear Information System (INIS)

    Retrospective individual dose assessment of workers chronically exposed to plutonium is an important task in investigation of possible health effects from internal plutonium depositions. In most cases inhalation is the primary mode of the plutonium exposures, though an additional route of plutonium intake through wounds (pinpricks) also occurs in some cases. Estimating of systemic and total body deposition of plutonium from urinalysis is usually used to carry out the task of individual dose assessment. But this technique used alone gives no information about the routes of intake and solubility of aerosol particles, which could result in wrong lung dose calculations. Direct in vivo measurements of 241Am content in lungs, skeleton and liver by whole-body counting technique allow one to improve the estimation of the organ deposition of plutonium and the estimation of the individual lung doses. Our method of plutonium dose calculating uses the fact that plutonium of reactor origin is accompanied by 241Am that is grown in from decay of the 241Pu parent. The algorithm applies the new ICRP Publication 66/67 models and takes into account such parameters as 241Pu/239Pu ratio, the activity ratio of 239Pu to the sum of alpha emitting plutonium isotopes, effective aging time of mixed fission products and actinides, particle size distribution of plutonium aerosols (AMAD) and a rate of intake within the period of employment. The purpose of this paper is to quantify the reliability of the model's prediction and retrospective dose calculations by the parameter uncertainty analysis. It takes into account the uncertainty of all parameters describing the components of the plutonium aerosol, AMAD and the rate of intake. The parameter uncertainty analysis involved assigning probability distributions to each parameter and the use of Monte Carlo simulation technique to produce a quantitative statement of confidence in the model's prediction. It is shown that cumulative distribution

  6. Tank 241-AP-103 08/1999 Compatibility Grab Samples and Analytical Results for the Final Report

    Energy Technology Data Exchange (ETDEWEB)

    BELL, K.E.

    1999-12-09

    This document is the format IV, final report for the tank 241-AP-103 (AP-103) grab samples taken in August 1999 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank AP-103 samples were performed as directed in ''Compatibility Grub Sampling and Analysis Plan for Fiscal Year 1999'' (Sasaki 1999a). Any deviations from the instructions provided in the tank sampling and analysis plan (TSAP) were discussed in this narrative. No notification limits were exceeded.

  7. Revised final report for tank 241-C-203, auger samples 95-AUG-20 and 95-AUG-21. Revision 1

    International Nuclear Information System (INIS)

    Two auger samples from tank 241-C-203 (C-203) were received at the 222-S Laboratories and underwent safety screening analyses, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. No notification limits were exceeded for the analyses. Two samples were submitted for a density determination at the request of Characterization Plant Engineering. SCOPE This document is the revised final report for the tank C-203 auger samples collected on April 5, 1995 (samples 95-AUG-20 and 95-AUG-021)

  8. Headspace vapor characterization of Hanford waste tank 241-U-108: Results from samples collected on 8/29/95

    International Nuclear Information System (INIS)

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-108 (Tank U-108) at the Hanford Site in Washington State. The results described in the report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC

  9. Effects of Crust Ingestion on Mixer Pump Performance in Tank 241-SY-101: Workshop Results

    International Nuclear Information System (INIS)

    In August 1999, a workshop was held at Pacific Northwest National Laboratory to discuss the effects of crust ingestion on mixer pump performance in Hanford Waste Tank 241-SY-101. The main purpose of the workshop was to evaluate the potential for crust ingestion to degrade mixing and/or damage the mixer pump. The need for a previously determined 12-inch separation between the top of the mixer pump inlet and the crust base was evaluated. Participants included a representative from the pump manufacturer, an internationally known expert in centrifugal pump theory, Hanford scientists and engineers, and operational specialists representing relevant fields of expertise. The workshop focused on developing an understanding of the pump design, addressing the physics of entrainment of solids and gases into the pump, and assessing the effects of solids and gases on pump performance. The major conclusions are summarized as follows: (1) Entrainment of a moderate amount of solids or gas from the crust should not damage the pump or reduce its lifetime, though mixing effectiveness will be somewhat reduced. (2) Air binding should not damage the pump. Vibrations due to ingestion of gas, solids, and objects potentially could cause radial loads that might reduce the lifetime of bearings and seals. However, significant damage would require extreme conditions not associated with the small bubbles, fine solids, and chunks of relatively weak material typical of the crust. (3) The inlet duct extension opening, 235 inches from the tank bottom, should be considered the pump inlet, not the small gap at 262 inches. (4) A suction vortex exists at the inlet of all pumps. The characteristics of the inlet suction vortex in the mixer pump are very hard to predict, but its effects likely extend upward several feet. Because of this, the current 12-inch limit should be replaced with criteria based on actual monitored pump performance. The most obvious criterion (in addition to current operational

  10. Solid Phase Characterization Of Heel Samples From Tank 241-C-110

    International Nuclear Information System (INIS)

    During sluicing operations of tank 241-C-110, a significant amount of solids were unable to be retrieved. These solids (often referred to as the tank 'heel') were sampled in 2010 and chemically and mineralogically analyzed in the 222-S Laboratory. Additionally, dissolution tests were performed to identify the amount of undissolvable material after using multiple water contacts. This report covers the solid phase characterization of six samples from these tests using scanning electron microscopy, polarized light microscopy, and X-ray diffraction. The chemical analyses, particle size distribution analysis, and dissolution test results are reported separately. Two of the samples were from composites created from as-received material - Composite A and Composite B. The main phase in these samples was sodium-fluoride-phosphate hydrate (natrophosphate) - in the X-ray diffraction spectra, this phase was the only phase identifiable. Polarized light microscopy showed the presence of minor amounts of gibbsite and other phases. These phases were identified by scanning electron microscopy - energy dispersive X-ray spectroscopy as sodium aluminosilicates, sodium diuranate, and sodium strontium phosphate hydrate (nastrophite) crystals. The natrophosphate crystals in the scanning electron microscopy analysis showed a variety of erosive and dissolution features from perfectly shaped octahedral to well-rounded appearance. Two samples were from water-washed Composites A and B, with no change in mineralogy compared to the as-received samples. This is not surprising, since the water wash had only a short period of water contact with the material as opposed to the water dissolution tests. The last two samples were residual solids from the water dissolution tests. These tests included multiple additions of water at 15 C and 45 C. The samples were sieved to separate a coarser fraction of > 710 μm and a finer fraction of < 710 μm. These two fractions were analyzed separately. The coarser

  11. Dynamics of Crust Dissolution and Gas Release in Tank 241-SY-101

    Energy Technology Data Exchange (ETDEWEB)

    SD Rassat; CW Stewart; BE Wells; WL Kuhn; ZI Antoniak; JM Cuta; KP Recknagle; G Terrones; VV Viswanathan; JH Sukamto; DP Mendoza

    2000-01-26

    Due primarily to an increase in floating crust layer thickness, the waste level in Hanford Tank 241-SY-101 (SY-101) has grown appreciably, and the flammable gas volume stored in the crust has become a potential hazard. To remediate gas retention in the crust and the potential for buoyant displacement gas releases from the nonconnective layer at the bottom of the tank, SY-101 will be diluted to dissolve a large fraction of the solids that allow the waste to retain gas. In this work we develop understanding of the state of the tank waste and some of its physical properties, investigate how added water will be distributed in the tank and affect the waste, and use the information to evaluate mechanisms and rates of waste solids dissolution and gas release. This work was completed to address these questions and in support of planning and development of controls for the SY-101 Surface Level Rise Remediation Project. Particular emphasis is given to dissolution of and gas release from the crust, although the effects of back-dilution on all waste layers are addressed. The magnitude and rates of plausible gas release scenarios are investigated, and it is demonstrated that none of the identified mechanisms of continuous (dissolution-driven) or sudden gas release, even with conservative assumptions, lead to domespace hydrogen concentrations exceeding the lower flammability limit. This report documents the results of studies performed in 1999 to address the issues of the dynamics, of crust dissolution and gas release in SY-101. It contains a brief introduction to the issues at hand; a summary of our knowledge of the SY-101 crust and other waste properties, including gas fractions, strength and volubility; a description of the buoyancy and dissolution models that are applied to predict the crust response to waste transfers and back dilution; and a discussion of the effectiveness of mixing for water added below the crust and the limited potential for significant stratification

  12. Levels in 237Pu populated by 237Am (electron capture) and 241Cm(α) decays

    International Nuclear Information System (INIS)

    The electron capture decay scheme of 237Am (73 min) has been investigated by measuring the γ-ray and conversion-electron spectra of mass-separated 237Am samples. The γ-ray spectra were measured with a Ge(Li) spectrometer and the conversion-electron spectra were measured with a cooled Si(Li) detector and a magnetic β-ray spectrometer. Thirty-five γ rays were identified and the multipolarities of most of the transitions were deduced. The half-life of 237Am was determined by following the decay of the 280.2 keV photopeak and was found to be 73.0 plus-or-minus 1.0 min. The α-particle energy and α branching were measured to be 6.042 plus-or-minus 0.005 MeV and (2.5 plus-or-minus 0.3) times 10-2%, respectively. On the basis of the present investigation the following single-particle states have been identified in 237Pu: 7/2-743, 0; 1/2+631, 145.5; 5/2+622, 280.2; 3/2+631, 370.4; 5/2+633, 407.8; 7/2+624, 473.5; 5/2-752, 655.3; and 7/2+613, 908.8 keV. The ground state of 237Am has been deduced to be the 5/2-523 Nilsson orbital. The logft values for electron capture transitions to the observed states were derived. The α-particle spectrum of a mass-separated 241Cm sample was measured with the Argonne double focusing magnetic spectrometer. Eleven α groups identified in this spectrum populate the members of the ground state, 1/2+631, and 3/2+631 bands. The α-decay hindrance factors are consistent with the Nilsson-state assignments deduced from 237Am electron capture decay

  13. SOLID PHASE CHARACTERIZATION OF HEEL SAMPLES FROM TANK 241-C-110

    Energy Technology Data Exchange (ETDEWEB)

    PAGE JS; COOKE GA; PESTOVICH JA; HUBER HJ

    2011-12-01

    During sluicing operations of tank 241-C-110, a significant amount of solids were unable to be retrieved. These solids (often referred to as the tank 'heel') were sampled in 2010 and chemically and mineralogically analyzed in the 222-S Laboratory. Additionally, dissolution tests were performed to identify the amount of undissolvable material after using multiple water contacts. This report covers the solid phase characterization of six samples from these tests using scanning electron microscopy, polarized light microscopy, and X-ray diffraction. The chemical analyses, particle size distribution analysis, and dissolution test results are reported separately. Two of the samples were from composites created from as-received material - Composite A and Composite B. The main phase in these samples was sodium-fluoride-phosphate hydrate (natrophosphate) - in the X-ray diffraction spectra, this phase was the only phase identifiable. Polarized light microscopy showed the presence of minor amounts of gibbsite and other phases. These phases were identified by scanning electron microscopy - energy dispersive X-ray spectroscopy as sodium aluminosilicates, sodium diuranate, and sodium strontium phosphate hydrate (nastrophite) crystals. The natrophosphate crystals in the scanning electron microscopy analysis showed a variety of erosive and dissolution features from perfectly shaped octahedral to well-rounded appearance. Two samples were from water-washed Composites A and B, with no change in mineralogy compared to the as-received samples. This is not surprising, since the water wash had only a short period of water contact with the material as opposed to the water dissolution tests. The last two samples were residual solids from the water dissolution tests. These tests included multiple additions of water at 15 C and 45 C. The samples were sieved to separate a coarser fraction of > 710 {mu}m and a finer fraction of < 710 {mu}m. These two fractions were analyzed

  14. Studying of distribution of 137Cs, 90Sr, 239+240Pu, 241Am and 244Cm according to the organic acids fractions of the alienation zone soils

    International Nuclear Information System (INIS)

    The paper deals with data of research on the distribution of the radionuclides 137Cs, 90Sr, 239+240Pu, 241Am and 244Cm of ''the Chornobyl rains'' by the fractions of the organic matters of derno-podzolic sandy, derno-meadow and peat soils sampled in the alienation zone of the Chornobyl NPP. Functioning of organic matters was carried according to Tyurin's method. It is stressed that, independently on soil type, 137Cs is connected with the mineral contituent by 80-95%. It is found out that, independently on the soil type, 50-70% 137Sr and 15-45% 241Am are associated with fulvic acid fractions. The 241Am and 244Cm distribution according to organic acids taking into account deviations while carrying out determinations is unambiguous. It is found out that in all the soils tested the main quality of 239+24Pu is connected with humic acids

  15. Common variation at 1q24.1 (ALDH9A1 is a potential risk factor for renal cancer.

    Directory of Open Access Journals (Sweden)

    Marc Y R Henrion

    Full Text Available So far six susceptibility loci for renal cell carcinoma (RCC have been discovered by genome-wide association studies (GWAS. To identify additional RCC common risk loci, we performed a meta-analysis of published GWAS (totalling 2,215 cases and 8,566 controls of Western-European background with imputation using 1000 Genomes Project and UK10K Project data as reference panels and followed up the most significant association signals [22 single nucleotide polymorphisms (SNPs and 3 indels in eight genomic regions] in 383 cases and 2,189 controls from The Cancer Genome Atlas (TCGA. A combined analysis identified a promising susceptibility locus mapping to 1q24.1 marked by the imputed SNP rs3845536 (Pcombined =2.30x10-8. Specifically, the signal maps to intron 4 of the ALDH9A1 gene (aldehyde dehydrogenase 9 family, member A1. We further evaluated this potential signal in 2,461 cases and 5,081 controls from the International Agency for Research on Cancer (IARC GWAS of RCC cases and controls from multiple European regions. In contrast to earlier findings no association was shown in the IARC series (P=0.94; Pcombined =2.73x10-5. While variation at 1q24.1 represents a potential risk locus for RCC, future replication analyses are required to substantiate our observation.

  16. New search for correlated e{sup +}e{sup -} pairs in the {alpha} decay of {sup 241}Am

    Energy Technology Data Exchange (ETDEWEB)

    Bernabei, R.; Belli, P.; Di Marco, A. [INFN, Sezione Roma ' ' Tor Vergata' ' , Rome (Italy); Universita di Roma ' ' Tor Vergata' ' , Dipartimento di Fisica, Rome (Italy); Cappella, F.; D' Angelo, A.; Incicchitti, A. [INFN, Sezione Roma, Rome (Italy); Universita di Roma ' ' La Sapienza' ' , Dipartimento di Fisica, Rome (Italy); Caracciolo, V.; Castellano, S.; Cerulli, R.; Laubenstein, M. [Laboratori Nazionali del Gran Sasso, INFN, Assergi (Italy); Dai, C.J.; He, H.L.; Ma, X.H.; Sheng, X.D.; Wang, R.G. [Chinese Academy, IHEP, Beijing (China); Montecchia, F. [INFN, Sezione Roma ' ' Tor Vergata' ' , Rome (Italy); Universita di Roma ' ' Tor Vergata' ' , Dipartimento di Ingegneria Civile e Ingegneria Informatica, Rome (Italy); Tretyak, V.I. [Institute for Nuclear Research, Kyiv (Ukraine); Ye, Z.P. [Chinese Academy, IHEP, Beijing (China); University of Jing Gangshan, Jiangxi (China)

    2013-05-15

    A new search for production of correlated e{sup +}e{sup -} pairs in the {alpha} decay of {sup 241}Am has been carried out deep underground at the Gran Sasso National Laboratory of the INFN by using pairs of NaI(Tl) detectors of the DAMA/LIBRA set-up. The experimental data show an excess of double coincidences of events with energy around 511keV in faced pairs of detectors, which are not explained by known side reactions. This measured excess gives a relative activity {lambda} = (4.70{+-}0.63) x 10{sup -9} for the Internal Pair Production (IPP) with respect to the alpha decay of {sup 241}Am; this value is of the same order of magnitude as previous determinations. In a conservative approach the upper limit {lambda} < 5.5 x 10{sup -9} (90% C.L.) can be derived. It is worth noting that this is the first result on IPP obtained in an underground experiment, and that the {lambda} value obtained in the present work is independent of the live-time estimate. (orig.)

  17. A genome-wide association analysis identified a novel susceptible locus for pathological myopia at 11q24.1.

    Directory of Open Access Journals (Sweden)

    Hideo Nakanishi

    2009-09-01

    Full Text Available Myopia is one of the most common ocular disorders worldwide. Pathological myopia, also called high myopia, comprises 1% to 5% of the general population and is one of the leading causes of legal blindness in developed countries. To identify genetic determinants associated with pathological myopia in Japanese, we conducted a genome-wide association study, analyzing 411,777 SNPs with 830 cases and 1,911 general population controls in a two-stage design (297 cases and 934 controls in the first stage and 533 cases and 977 controls in the second stage. We selected 22 SNPs that showed P-values smaller than 10(-4 in the first stage and tested them for association in the second stage. The meta-analysis combining the first and second stages identified an SNP, rs577948, at chromosome 11q24.1, which was associated with the disease (P = 2.22x10(-7 and OR of 1.37 with 95% confidence interval: 1.21-1.54. Two genes, BLID and LOC399959, were identified within a 200-kb DNA encompassing rs577948. RT-PCR analysis demonstrated that both genes were expressed in human retinal tissue. Our results strongly suggest that the region at 11q24.1 is a novel susceptibility locus for pathological myopia in Japanese.

  18. Valuation of contamination of Am-241 by smear test and characterization of waste by scintillation liquid medium

    Energy Technology Data Exchange (ETDEWEB)

    Cardoso, Gabriella Souza [Pontificia Universidade Catolica de Goias (PUC-GO), Goiania, GO (Brazil). Dept. Matematica, Fisica, Quimica e Engenharia de Alimentos; Santos, Eliane Eugenia dos; Mingote, Raquel Maia; Barbosa, Rugles Cesar, E-mail: esantos@cnen.gov.b, E-mail: mingote@cnen.gov.b, E-mail: rbarbosa@cnen.gov.b [Centro Regional de Ciencias Nucleares do Centro Oeste (CRCN-CO/CNEN-GO), Abadia de Goias, GO (Brazil). Lab. de Radioprotecao

    2011-07-01

    The radioactive lightning rods Interim storage facility receives Midwest Regional Center for Nuclear Science - CRCN-CO, and contains the majority of devices called radioactive lightning rods, and so is our main study object with an interest in be adapt of Interim storage facility (ID) Radiation Protection requirements and management of radioactive waste. The radioactive lightning rods are devices that contain Americium 241 that fall under the categorization of radioactive sources (IAEA-TECDOC-1191) in category 4 (same device category of the static Eliminator type). The handling, transportation, maintenance, segregation and disposal of accessories and devices emitting ionizing radiation in which involve procedures require: special types of packaged, storage techniques, cleaning/hygiene and inventoried and equipment for Radiation Protection. Cleaning and hygiene as well as the disposition criterion of accessories makes it necessary for the introduction of safe cleanup criterion and more specific that the criterion for exemption. The radioactive lightning rods have brackets that represent physical danger in shipping and handling as well as liabilities of contamination as well as in the case of being contaminated, agents in the transfer of contaminants (Am-241) it is necessary to adopt analysis methodologies and procedures and criterion for the management of radioactive and nonradioactive materials. (author)

  19. Measurement of mass yields from the 241Am(2nth,f reaction at the Lohengrin Spectrometer

    Directory of Open Access Journals (Sweden)

    Köster U.

    2013-03-01

    Full Text Available The study of fission yields has a major impact on the characterization and understanding of the fission process and is mandatory for reactor applications. While the yields are known for the major actinides (235U, 239Pu in the thermal neutron-induced fission, only few measurements have been performed on 242Am. The interest of 242Am concerns the reduction of radiotoxicity of 241Am in nuclear wastes using transmutation reactions. This paper presents the measurement of the fission mass yields from the reaction 241Am(2nth,f performed at the Lohengrin mass spectrometer (ILL, France for both the light and the heavy peaks: a total of 41 mass yields have been measured. The experiment was also meant to determine whether there is a difference in mass yields between the isomeric state and the ground state as it exists in fission and capture cross sections. The method used to address this question is based on a repeated measurement of a set of fission mass yields as a function of the ratio between the 242gAm and the 242mAm fission rates. The presented experiment is also a first step towards the measurement of the isotopic fission yields of 242Am.

  20. TEST PLAN AND PROCEDURE FOR THE EXAMINATION OF TANK 241-AY-101 MULTI-PROBE CORROSION MONITORING SYSTEM

    Energy Technology Data Exchange (ETDEWEB)

    WYRWAS RB; PAGE JS; COOKE GS

    2012-04-19

    This test plan describes the methods to be used in the forensic examination of the Multi-probe Corrosion Monitoring System (MPCMS) installed in the double-shell tank 241-AY-101 (AY-101). The probe was designed by Applied Research and Engineering Sciences (ARES) Corporation. The probe contains four sections, each of which can be removed from the tank independently (H-14-107634, AY-101 MPCMS Removable Probe Assembly) and one fixed center assembly. Each removable section contains three types of passive corrosion coupons: bar coupons, round coupons, and stressed C-rings (H-14-l07635, AY-101 MPCMS Details). Photographs and weights of each coupon were recorded and reported on drawing H-14-107634 and in RPP-RPT-40629, 241-AY-101 MPCMS C-Ring Coupon Photographs. The coupons will be the subject of the forensic analyses. The purpose of this examination will be to document the nature and extent of corrosion of the 29 coupons. This documentation will consist of photographs and photomicrographs of the C-rings and round coupons, as well as the weights of the bar and round coupons during corrosion removal. The total weight loss of the cleaned coupons will be used in conjunction with the surface area of each to calculate corrosion rates in mils per year. The bar coupons were presumably placed to investigate the liquid-air-interface. An analysis of the waste level heights in the waste tank will be investigated as part of this examination.