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. Extraction of tetravalent berkelium and cerium by aliquate-336-S-NO3 quaternary ammonium salt

    International Nuclear Information System (INIS)

    Extraction of tetravalent berkelium and cerium by aliquate-336-S-NO3 quaternary ammonium salt from nitric acid solutions is investigated. The effect of concentrations of nitric acid and extracting agent, nature of an oxidant (potassium bromate, potassium bichromate, mixture of AgNO3 and (NH4)2S2O8) and solvent on the distribution coefficient of berkelium(4) and cerium(4) is studied. It is established that solutions of aliquate-336-S-NO3 in carbon tetrachloride and dichloroethane extract quantitatively tetravalent berkelium from 10-12 M nitric acid solutions and cerium - from 1-10 M nitric acid solutions containing potassium bichromate as an oxidant. It is shown that the value of distribution coefficient for berkelium and cerium depends on the nature of an oxidant and extracting agent concentration. It is established that in the case of extraction by quaternary ammonium salt with one berkelium(4) mole four aliquate-336-SNO3 moles are associated and 1.5-1.6 mole of extracting agent are associated with one cerium(4) mole. It permits to make a conclusion that stoichiometry of extraction reactions by quaternary ammonium salt is not the same for tetravalent berkelium and cerium. It is shown that trivalent transplutonium and rare earth elements are not practically extracted by aliquate-336-S-NO3 from nitric acid solutions

  4. 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)

  5. Americium-241 - ED 4308

    International Nuclear Information System (INIS)

    This sheet presents the characteristics of Americium-241, its origin, and its radio-physical and biological properties. It briefly describes its use in nuclear medicine. It indicates its dosimetric parameters for external exposure, cutaneous contamination, and internal exposure due to acute contamination or to chronic contamination. It indicates and comments the various exposure control techniques: ambient dose rate measurement, surface contamination measurement, atmosphere contamination. It addresses the means of protection: premise design, protection against external exposure and against internal exposure. It describes how areas are delimited and controlled within the premises: regulatory areas, controls to be performed. It addresses the personnel classification, training and medical survey. It addresses the issue of wastes and effluents. It briefly recalls the administrative procedures related to the authorization and declaration of possession and use of sealed and unsealed sources. It indicates regulatory aspects related to the road transport of Americium-241, describes what is to be done in case of incident or accident (for the different types of contamination or exposure)

  6. Beneficial uses of 241Am

    International Nuclear Information System (INIS)

    This report assesses the uses of 241Am and the associated costs and supply. The study shows that 241Am-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 241Am can produce 97% pure 238Pu at $21,000/g. Using a pyro-metallurgical process, 241Am 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 241Am contained in the MSE residues

  7. Decision Document for the Low Activity Waste Retrieval Strategy for Tanks 241-AN-103 and 241-AN-104 and 241-AN-105 and 241-AW-101

    International Nuclear Information System (INIS)

    This report documents the preferred approach (retrieval strategy) to prepare and transfer waste from low-activity waste source tanks containing soluble solids (Tanks 241-AN-103, 241-AN-104, 241-AN-105 and 241-AW-101) to the vitrification plant. Several opportunities to further refine the selected retrieval strategy were identified; these were recommended for follow-on studies

  8. 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...

  9. 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.

  10. 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.

  11. 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...

  12. 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...

  13. 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—...

  14. 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...

  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. 10 CFR 600.241 - Financial reporting.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Financial reporting. 600.241 Section 600.241 Energy DEPARTMENT OF ENERGY (CONTINUED) ASSISTANCE REGULATIONS FINANCIAL ASSISTANCE RULES Uniform Administrative....241 Financial reporting. (a) General. (1) Except as provided in paragraphs (a) (2) and (5) of...

  17. 15 CFR 241.5 - Standard dimensions.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Standard dimensions. 241.5 Section 241..., VEGETABLES AND OTHER DRY COMMODITIES, AND FOR CRANBERRIES § 241.5 Standard dimensions. Whenever in the rules and regulations in this part the error on a dimension is mentioned, this error shall be determined...

  18. 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...

  19. 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...

  20. 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...

  1. 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... CONSUMER INFORMATION Soybean Promotion and Research Order Reports, Books, and Records § 1220.241 Reports... to report to the Board periodically such information as may be required by the...

  2. Am-241 buildup in nematode organisms

    International Nuclear Information System (INIS)

    The process of Am-241 intake into earthworm organisms from chernozem leached in their presence in soil contaminated with this radionuclide is studied. The data on Am-241 buildup values during long-time radionuclide intake into earthworm organisms from soil are given. It s shown that Am-241 buildup in earthworm organisms do not exceed its concentration in soil for the whole observation period (as Am-241 presents in soil in state unavailable for animals). Intensive extraction of the radionuclide from the organisms is observed when earthworm contacts with soil are stopped

  3. 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

  4. 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...

  5. Tank 241-U-204 tank characterization plan

    International Nuclear Information System (INIS)

    This document is the tank characterization plan for Tank 241-U-204 located in the 200 Area Tank Farm on the Hanford Reservation in Richland, Washington. This plan describes Data Quality Objectives (DQO) and presents historical information and scheduled sampling events for tank 241-U-204

  6. 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 §...

  7. 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... DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES... Without a HUD-Insured or HUD-Held Mortgage Premiums § 241.805 Insurance premiums. (a) First premium....

  8. 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,...

  9. Determination of 241Am in reindeer bone

    International Nuclear Information System (INIS)

    The purpose of this work was to develop a procedure to separate americium from other alpha active nuclides present in reindeer bone samples, especially 228Th and its daughter nuclides. The 241Am-spectrum of a reindeer bone sample analyzed using the proposed method is given. The α-spectrum was measured one week after electrodeposition. The absence of the alpha peak of 224Ra, the daughter nuclide of 228Th, indicates that no 228Th was electrodeposited onto the platinum disc. Four reindeer bone samples were analyzed for 241Am using the method developed. The 241Am/239240Pu activity ratio in reindeer bone was 0.9 :- 0.4. These results indicate that compared to plutonium, americium is accumulated in reindeer bone more heavily than in liver. All 241Am values presented are concentrations at the time of radioassay, and no correction has been made for the ingrowth of 241Am formed by the decay of 241Pu during stockpilling. However, all 241Am determinations were made 1 to 3 yrs after sample collection, and thus the corrections due to the ingrowth can be considered slight. About 60% of plutonium body burden is located in liver and 20% in skeleton. The activity ratio 241Am/239240Pu in these animals was about 0.2 and 1.0 in liver and skeleton, respectively. This indicates that about 60% of the 241Am body burden is located in skeleton and about 30% in liver. It can be roughly estimated that the whole-body activity of 241Am is thus about 40% of the 239240Pu body burden

  10. ELECTROCHEMICAL CORROSION TESTING OF TANKS 241-AN-102 & 241-AP-107 & 241-AP-108 IN SUPPORT OF ULTRASONIC TESTING

    Energy Technology Data Exchange (ETDEWEB)

    WYRWAS RB; DUNCAN JB

    2008-11-20

    This report presents the results of the corrosion rates that were measured using electrochemical methods for tanks 241-AN-102 (AN-102), 241-AP-107 (AP 107), and 241-AP-108 (AP-108) performed under test plant RPP-PLAN-38215. The steel used as materials of construction for AN and AP tank farms was A537 Class 1. Test coupons of A537 Class 1 carbon steel were used for corrosion testing in the AN-107, AP-107, and AP-108 tank waste. Supernate will be tested from AN-102, AP-107, and Ap-108. Saltcake testing was performed on AP-108 only.

  11. Tank 241-C-103 headspace flammability

    International Nuclear Information System (INIS)

    Information regarding flammable vapors, gases, and aerosols is presented for the purpose of resolving the tank 241-C-103 headspace flammability issue. Analyses of recent vapor and liquid samples, as well as visual inspections of the tank headspace, are discussed in the context of tank dynamics. This document is restricted to issues regarding the flammability of gases, vapors, and an aerosol that may exist in the headspace of tank 241-C-103. While discussing certain information about the organic liquid present in tank 241-C-103, this document addresses neither the potential for, nor consequences of, a pool fire involving this organic liquid; they will be discussed in a separate report

  12. 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

  13. 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

  14. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-09-01

    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.

  16. 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

  17. Plant uptake and transport of 241Am

    International Nuclear Information System (INIS)

    We conducted several experiments with 241Am to obtain a more complete understanding of how this transuranium element is absorbed and transported in plants. In a plant species (Tamarix pentandra Pall.) that has salt glands in the leaves excreting NaCl and other ions, 241Am was not pumped through these glands. Cyanide, which forms complexes with any metals, when applied to a calcareous soil, greatly increased the transport of 241Am into stems and leaves of bush bean plants. Radioactive cyanide (14C) was also transported to leaves and stems. When radish was grown in both calcareous and noncalcareous soils, 241Am appeared to be fixed on the peel so firmly that it was resistant to removal by HNO3 washing. The chelating agent DTPA induced increased transport of 241Am to leaves and into the fleshy roots of the radish. Data for Golden Cross hybrid corn grown in solution culture showed at least seven times as much 241Am transport to the xylem exudatields are corrected by recovery of added tracers

  18. 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

  19. 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.

  20. 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

  1. 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

  2. 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

  3. 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...

  4. 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...

  5. 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. 24.241 Section 24.241 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX AND TRADE BUREAU, DEPARTMENT OF THE TREASURY LIQUORS WINE Storage, Treatment and Finishing of Wine § 24.241 Decolorizing juice or wine. (a) Conditions...

  6. 48 CFR 252.241-7001 - Government access.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Government access. 252.241... Clauses 252.241-7001 Government access. As prescribed in 241.501-70(b), use the following clause: Government Access (DEC 1991) Authorized representatives of the Government may have access to the...

  7. Tank 241-TY-101 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-TY-101

  8. Tank 241-C-101 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-101

  9. 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

  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-AX-102 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-AX-102

  12. Tank 241-S-111: 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, ORNL, and PNL tank vapor program. Scope of this plan is to provide guidance for sampling and analysis of vapor samples from tank 241-S-111 (this tank is on the organic and flammable gas watch list). This tank received Redox plant waste, among other wastes

  13. Tank 241-U-103 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-103

  14. Tank 241-BY-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, PNL 325 Analytical Chemistry Laboratory, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-105

  15. Tank 241-BX-103 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, 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

  16. Tank 241-SX-103 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-SX-103

  17. Tank 241-C-102 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-102

  18. Tank 241-AP-107 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-AP-107

  19. Tank 241-S-111: Tank characterization plan

    Energy Technology Data Exchange (ETDEWEB)

    Homi, C.S.

    1995-03-07

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, ORNL, and PNL tank vapor program. Scope of this plan is to provide guidance for sampling and analysis of vapor samples from tank 241-S-111 (this tank is on the organic and flammable gas watch list). This tank received Redox plant waste, among other wastes.

  20. 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.

  1. 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...

  2. Tank 241-BX-104 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-BX-104

  3. Tank 241-T-107 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-T-107

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. Tank 241-BY-106 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, PNL 325 Analytical Chemistry Laboratory, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-106

  12. Tank 241-SX-115 tank characterization plan

    International Nuclear Information System (INIS)

    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

  13. 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.

  14. 49 CFR 241.5 - Definitions.

    Science.gov (United States)

    2010-10-01

    ... TRANSPORTATION UNITED STATES LOCATIONAL REQUIREMENT FOR DISPATCHING OF UNITED STATES RAIL OPERATIONS § 241.5... railroad operation, or by establishing a route through the use of a railroad signal or train control system... working limits); or (ii) Operating a function of a signal system designed for use by those...

  15. Tank 241-BY-103 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, Oak Ridge National Laboratory, and PNL 329 Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-BY-103

  16. Tank 241-T-111 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-T-111

  17. Tank 241-TX-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, 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-TX-105

  18. 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

  19. 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.

  20. Gamma-ray spectra of 241Am

    International Nuclear Information System (INIS)

    The γ-spectrum of 241Am was reinvestigated by using intense sources (100 and 25 mCi) for the energy range of Eγ>60 keV, and purified solution source of about 10 μCi for the low energy and to make sure that the γ-lines present in the spectrum come from the α-decay of 241Am. The study was divided into three parts. The γ-spectrometers consists of 40 and 10% relative efficiency Hp Ge detectors and 8192 channel ADC for normal spectra, and Si-Li for low energy. Outs of 169 γ-lines that are presented in the spectrum 47 are new. The major part of the new gamma lines was observed in the energy range of Eγ≥200 keV. (author)

  1. 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.

  2. Characterization of strong 241Am sources

    International Nuclear Information System (INIS)

    Gamma ray spectra of strong 241Am sources may reveal information about the source composition as there may be other radioactive nuclides such as progeny and radioactive impurities present. In this work the possibility to use gamma spectrometry to identify inherent signatures in 241Am sources in order to differentiate sources from each other, is investigated. The studied signatures are age, i.e. time passed since last chemical separation, and presence of impurities. The spectra of some sources show a number of Doppler broadened peaks in the spectrum which indicate the presence of nuclear reactions on light elements within the sources. The results show that the investigated sources can be differentiated between by age and/or presence of impurities. These spectral features would be useful information in a national nuclear forensics library (NNFL) in cases when the visual information on the source, e.g. the source number, is unavailable. - Highlights: • Age and impurities can be used as a signature for 241Am sources. • Nuclear reactions take place in sources with low Z impurities. • Some sources contain 243Am as an impurity

  3. 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

  4. Thermal and Radiolytic Gas Generation Tests on Material from Tanks 241-U-103, 241-AW-101, 241-S-106, and 241-S-102: Status Report

    International Nuclear Information System (INIS)

    This report summarizes progress in evaluating thermal and radiolytic flammable gas generation in actual Hanford single-shell tank wastes. The work described was conducted at Pacific Northwest National Laboratory (PNNL) for the Flammable Gas Safety Project, whose purpose is to develop information to support DE and S Hanford (DESH) and Project Management Hanford Contract (PHMC) subcontractors in their efforts to ensure the safe interim storage of wastes at the Hanford Site. This work is related to gas generation studies performed by Numatec Hanford Corporation (formerly Westinghouse Hanford Company). This report describes the results of laboratory tests of gas generation from actual convective layer wastes from Tank 241-U-103 under thermal and radiolytic conditions. Accurate measurements of gas generation rates from highly radioactive tank wastes are needed to assess the potential for producing and storing flammable gases within the tanks. The gas generation capacity of the waste in Tank 241-U-103 is a high priority for the Flammable Gas Safety Program due to its potential for accumulating gases above the flammability limit (Johnson et al, 1997). The objective of this work was to establish the composition of gaseous degradation products formed in actual tank wastes by thermal and radiolytic processes as a function of temperature. The gas generation tests on Tank 241-U-103 samples focused first on the effect of temperature on the composition and rate of gas generation Generation rates of nitrogen, nitrous oxide, methane, and hydrogen increased with temperature, and the composition of the product gas mixture varied with temperature

  5. Pu-241 in samples of forest soil from Poland

    International Nuclear Information System (INIS)

    241Pu activity measurements in coniferous forest soil samples from Poland are presented. The results were obtained in two ways: by alpha spectrometric remeasurements of the plutonium sources 3-4 years after their preparation (i.e. by the 241Am ingrowth) and by direct measurements of 241Pu using liquid scintillation (LS) spectrometry. Both methods gave consistent results. The maximum observed activity concentration obtained by the 241Am ingrowth was (254±43) Bq/kg, and by direct measurements it was (284±31) Bq/kg (the same sample, activities calculated for May 1, 1986). Enhanced levels of 241Pu were observed in all samples from the farthest north-eastern Poland. The estimated 241Pu maximum deposition from Chernobyl fallout in this area (sum of deposition for two examined layers of one site) was (1.025±0.110) kBq/m2. This will result after 70 years in an additional 241Am activity of about (30.1±3.2) Bq/m2. The average ratio for 241Pu to total 238,239,240Pu was of the order of 25. The obtained average Chernobyl ratios for 241Pu to 239,240Pu were about 86, and those for 241Pu to 238,239,240Pu were 56

  6. Organic end state analysis of tank 241-S-106

    International Nuclear Information System (INIS)

    This document provides a record of the organic end state analysis of tank 241-S-106. Tank 241-S-106 is one of twelve 22.9-meter (75-feet) diameter single-shell tanks in the 241-S Tank Farm in the 200 West Area of Hanford. This tank was built in 1951 and has a capacity of 2870 kiloliter (kL) (758 kilogallon [kgal]). According to Hanlon (1999), tank 241-S-106 currently contains 1813 kL (479 kgal) of waste comprised of 1613 kL (426 kgal) saltcake, 200 kL (53 kgal) supernatant. Included in those volumes is 719 kL (190 kgal) drainable interstitial liquid. The pumpable volume is estimated at 920 kL (243 kgal). The waste is designated as non-complexed (NCPLX). Tank 241-S-106 is not a Watch List tank. Tank 241-S-106 has not been declared as a leaker

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

    International Nuclear Information System (INIS)

    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

  8. 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.

  9. 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

  10. Delayed neutron yield of 238U and 241Pu

    International Nuclear Information System (INIS)

    The total delayed neutron yield for 238U and 241Pu were observed as a function of the incident neutron energy. The measurements extend from 2.5 to 5 MeV for 238U and from 0.15 to 5 MeV for 241Pu. The average ratio of the 241Pu delayed neutron yield to that of 238U is 0.292 +- 0.022

  11. 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.

  12. Measurement of contamination by 241Am

    International Nuclear Information System (INIS)

    In relation to the fact that four employees at the Danish Isotope Center who had regularly cleaned the smoke detectors used for control measurements were found to be contaminated with 241Am, the aim was to investigate the suitability of the Phoswich detector system for measurement of contamination of humans by 241Am. It was also wished to compare this measuring method with other selected ones. The measurement results are presented in detail. It was found that measurements taken on the cranium with the Phoswich detectors were more suitable for measurement of contamination by 241Am than the use of a Ge detector on the liver, - because of the first-named method's greater degree of measuring efficiency, (0.013 cps/Bq compared with 0.0001 cps/Bq in the case of Ge detector measurement) and lower minimum detectable activity in relation to that activity that was measured on A1 (one of the employees). It was found that Phoswich-detector measurement and measuring of urine samples supplemented each other in a satisfactory way. The Phoswich detector enables a quick measurement of the degree of seriousness of the contamination of a person and a relatively accurate determination of the calculated intake of contamination which has a size of at least twice the annual limit of intake size. Measurements of urine samples enable smaller amounts of contamination to be revealed, but this takes ca. 32 weeks and is less accurate than Phoswich measurement especially if a long time has elapsed after the intake. (AB) (34 refs.)

  13. 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.

  14. Tank 241-AZ-101 and tank 241-AZ-102, airlift circulator operation 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 the tank 241-AZ-101 and 241-AZ-102 airlift circulators (ALCs). The purpose of the ALC operation is to support portions of the operational test procedure (OTP) for Project W-030 (OTP-W030-001) and to perform functional test in support of Project W-151. Project W-030 is the 241-A-702 ventilation upgrade project (241-AZ-702) and Project W-151 is the 241-AZ-101 Mixer Pump Test. The functional tests will check the operability of the tank 241-AZ-101 ALCs. Process Memo's No.2E98-082 and No.2E99-001 (LMHC 1999a, LMHC 1999b) direct the operation of the ALCs and the Industrial Hygiene monitoring respectively. A series of tests will be conducted in which the ALCs in tanks 241-AZ-101 and 241-AZ-102 will be operated at different air flow rates. Vapor samples will be obtained to determine constituents that may be present in the tank headspace during ALC operation at tanks 241-AZ-101 and 241-AZ-102 as the waste is disturbed. During the testing, vapor samples will be obtained from the headspace of tanks 241-AZ-101 and 241-AZ-102 via the unused port on the standard hydrogen monitoring system (SHMS). Results will be used to provide the waste feed delivery program with environmental air permitting data for tank waste disturbing activities. Because of radiological concerns, the samples will be filtered for particulates. It is recognized that this may remove some organic compounds

  15. 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

  16. 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

    International Nuclear Information System (INIS)

    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 .. 10-6 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

  17. 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.

  18. 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.

  19. Dicty_cDB: VSJ241 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available ATAATAATAATAATAATAATA ATAATAATAATAATAATAATAATAATAATAATCACAATAAAAAAAAAGA Length of 3' end seq. 159 Connect...ed seq. ID VSJ241P Connected seq. >VSJ241P.Seq AAAAATAGTAATAGTTAATTATGACAACAACATATTT...TAATAATAATAATAATCACAATAAAAAAAAAGA Length of connected seq. 750 Full length Seq ID - Full length Seq. - Length of full length seq. - ... ...nydnnifwtlvnqtirnifyyriifcig*fetctsrsrismskknctks*rfnkr rih*slvirsknficcrrtfqw*wnnicnsgwkecrsncrtct...rnifyyriifcig*fetctsrsrismskknctks*rfnkr rih*slvirsknficcrrtfqw*wnnicnsgwkecrsncrtcty

  20. Dicty_cDB: VHN241 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available VH (Link to library) VHN241 (Link to dictyBase) - - - Contig-U15754-1 VHN241P (Link to Original ... RGPVWFAVNYLMIQSLRTYHEYYGDEFQIEYPTNSW* prnfgyrsr*yl*tsh *ylpresrwy*kicww*tnfrkktwkdhilfneyfhgdsgavwa shq Tr ... RGPVWFAVNYLMIQSLRTYHEYYGDEFQIEYPTNSW* prnfgyrsr*yl*tsh *ylpresrwy*kicww*tnfrkktwkdhilfneyfhgdsgavwa shq Fr ...

  1. 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...

  2. 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...

  3. Dicty_cDB: SSD241 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SS (Link to library) SSD241 (Link to dictyBase) - - - Contig-U15628-1 SSD241Z (Link to Original ... 000653_2... 33 3.7 EF392845_1( EF392845 |pid:none) Salicornia ... veneta photosynthetic o... 33 4.8 CP001357_947( CP ...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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.

  9. 7 CFR 58.241 - Packaging, repackaging and storage.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Packaging, repackaging and storage. 58.241 Section 58... Service 1 Operations and Operating Procedures § 58.241 Packaging, repackaging and storage. (a) Containers. Packages or containers used for the packaging of nonfat dry milk or other dry milk products shall be...

  10. 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.

  11. CCRI(II) activity comparison of 241Pu: CCRI(II)-K2.Pu-241

    International Nuclear Information System (INIS)

    In 2010, seven laboratories took part in the CCRI(II) key comparison of activity concentration measurements of 241Pu, CCRI(II)-K2.Pu-241, using seven different methods. The spread of all results except one is 4 * 10-2 in relative terms. The results based on the CIEMAT/NIST efficiency tracing method are shown to be dependent on the beta spectrum shape selected and further work is proposed. The KCRV has been determined as the arithmetic mean of six independent results based on four different methods. The results of the comparison have been analysed with respect to the KCRV. The degrees of equivalence with the KCRV have been approved by the CCRI(II) and are published in the BIPM key comparison database. (authors)

  12. 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)

  13. Software configuration management plan, 241-AY and 241-AZ tank farm MICON automation system

    International Nuclear Information System (INIS)

    This document establishes a Computer Software Configuration Management Plan (CSCM) for controlling software for the MICON Distributed Control System (DCS) located at the 241-AY and 241-AZ Aging Waste Tank Farm facilities in the 200 East Area. The MICON DCS software controls and monitors the instrumentation and equipment associated with plant systems and processes. A CSCM identifies and defines the configuration items in a system (section 3.1), controls the release and change of these items throughout the system life cycle (section 3.2), records and reports the status of configuration items and change requests (section 3.3), and verifies the completeness and correctness of the items (section 3.4). All software development before initial release, or before software is baselined, is considered developmental. This plan does not apply to developmental software. This plan applies to software that has been baselined and released. The MICON software will monitor and control the related instrumentation and equipment of the 241-AY and 241-AZ Tank Farm ventilation systems. Eventually, this software may also assume the monitoring and control of the tank sludge washing equipment and other systems as they are brought on line. This plan applies to the System Cognizant Manager and MICON Cognizant Engineer (who is also referred to herein as the system administrator) responsible for the software/hardware and administration of the MICON system. This document also applies to any other organizations within Tank Farms which are currently active on the system including system cognizant engineers, nuclear operators, technicians, and control room supervisors

  14. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    SHULTZ, M.V.

    1999-02-12

    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.

  16. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Himes, D.A.

    1998-08-11

    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

  18. 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

  19. 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)

  20. 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.

  1. Accumulation and retention of 241Am in marine plankton

    International Nuclear Information System (INIS)

    Two samples of sea water spiked with 241Am were prepared, one containing a rich suspension of phytoplankton cells and the other not. Adult Artemia brine shrimp were placed in each sample and the accumulation, uptake and concentration factors were obtained. Results from the Artemia uptake show that 241Am is far more effectively accumulated from the water pathway than from the combined food and water pathway. The experiments indicate that 241Am is relatively non-assimilatable when digested and thus most, if not all, of the isotope is rapidly voided in fecal pellets

  2. 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.

  3. Analysis report for 241-BY-104 auger samples

    International Nuclear Information System (INIS)

    This document details the analytical sample results for two auger samples of the tip 15 cm (6 in.) of tank 241-BY-104 salt cake. The thermal response of tank 241-BY-104 auger samples is generally mild. The level of cyanide and iron, and therefore of ferrocyanide is very low. Evidence of inhomogeneity is present for tank 241-By-104 salt cake. Mass and charge balances were less than ideal. The concentrations found for the major constituents, except chromium, are in line with the expectations

  4. 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.

  5. Radiological risk from Am-241 in ionisation smoke chambers

    International Nuclear Information System (INIS)

    The author discusses the risk to man from the use of ionisation smoke chamber detectors with an Am-241 radiation source. The estimated dose is compared with that due to natural radioactivity. (G.T.H.)

  6. Tank 241-U-111 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-U-111

  7. Tank 241-BX-103 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-BX-103

  8. Tank 241-BX-109 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-BX-109

  9. Tank 241-BX-106 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-BX-106

  10. Acceptance Test Report for 241-U compressed air system

    International Nuclear Information System (INIS)

    This Acceptance Test Report (ATR) documents the results of acceptance testing of a newly upgraded compressed air system at 241-U Farm. The system was installed and the test successfully performed under work package 2W-92-01027

  11. Characterisation of a protection level 241Am calibration source

    International Nuclear Information System (INIS)

    A 241Am radioactive source and transport mechanism was installed at the National Physical Laboratory in December 1991 to be used for protection level calibration work. This report details the various measurements involved in the commissioning process. (Author)

  12. 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.

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

    International Nuclear Information System (INIS)

    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

  14. 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

  15. 241-SY modular exhauster pad analysis

    International Nuclear Information System (INIS)

    The purpose of this document is to show the analytical results which were reached in analyzing the new 241-SY modular exhauster concrete pad and retaining wall. The analysis covers wind loading (80 mph), an equivalent static load due to a seismic event, and from those two results, a determination of the pad thickness and the location and size of reinforcement bar was made. The analysis of the exhauster assembly and sampling cabinet evaluated overturning of the assemblies as a whole. An analysis was then performed for the bolting requirements for these two assemblies. The reason why this was broken up into components was to determine if the individual components could take the load exerted by the workset case loading condition, whether it be wind or seismic. The retaining wall that will be located near the new concrete pad was also analyzed. The retaining wall was evaluated to determine the area of reinforcement required, the location of reinforcement, as well as the mass and configuration of the wall to prevent overturning or sliding. The wall was considered Non-Safety Class 4. Additional piping was required to tie-in the new exhauster to the existing primary ventilation ductwork. The design for the tie-in includes two butterfly valves, a tee fitting, elbows, flanges, straight pipe sections, and two new pipe supports to accommodate the additional weight. The valves will enable the new and existing exhausters to be isolated independently. The ductwork, couplings, and supports were analyzed for structural adequacy given Safety Class 2 loads

  16. 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.

  17. Tank 241-AW-101 tank characterization plan

    International Nuclear Information System (INIS)

    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

  18. 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.

  19. 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.

  20. Tank 241-B-103 tank characterization plan

    International Nuclear Information System (INIS)

    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. The data quality objective (DQO) process was chosen as a tool to be used to identify 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-44-00 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 (e.g., Hanford Facility user groups, regulators) 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-B-103 (B-103) sampling activities. Tank B-103 was placed on the Organic Watch List in January 1991 due to review of TRAC data that predicts a TOC content of 3.3 dry weight percent. The tank was classified as an assumed leaker of approximately 30,280 liters (8,000 gallons) in 1978 and declared inactive. Tank B-103 is passively ventilated with interim stabilization and intrusion prevention measures completed in 1985

  1. 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.

  2. Assessment of Tank 241-S-112 Liquid Waste Mixing in Tank 241-SY-101

    International Nuclear Information System (INIS)

    The objectives of this study were to evaluate mixing of liquid waste from Tank 241-S-112 with waste in Tank 241-SY-101 and to determine the properties of the resulting waste for the cross-site transfer to avoid potential double-shell tank corrosion and pipeline plugging. We applied the time-varying, three-dimensional computer code TEMPEST to Tank SY-101 as it received the S-112 liquid waste. The model predicts that temperature variations in Tank SY-101 generate a natural convection flow that is very slow, varying from about 7 x 10-5 to 1 x 10-3 ft/sec (0.3 to about 4 ft/hr) in most areas. Thus, natural convection would eventually mix the liquid waste in SY-101 but would be very slow to achieve nearly complete mixing. These simulations indicate that the mixing of S-112 and SY-101 wastes in Tank SY-101 is a very slow process, and the density difference between the two wastes would further limit mixing. It is expected to take days or weeks to achieve relatively complete mixing in Tank SY-101

  3. Assessment of Tank 241-S-112 Liquid Waste Mixing in Tank 241-SY-101

    Energy Technology Data Exchange (ETDEWEB)

    Onishi, Yasuo; Trent, Donald S.; Wells, Beric E.; Mahoney, Lenna A.

    2003-10-01

    The objectives of this study were to evaluate mixing of liquid waste from Tank 241-S-112 with waste in Tank 241-SY-101 and to determine the properties of the resulting waste for the cross-site transfer to avoid potential double-shell tank corrosion and pipeline plugging. We applied the time-varying, three-dimensional computer code TEMPEST to Tank SY-101 as it received the S-112 liquid waste. The model predicts that temperature variations in Tank SY-101 generate a natural convection flow that is very slow, varying from about 7 x 10{sup -5} to 1 x 10{sup -3} ft/sec (0.3 to about 4 ft/hr) in most areas. Thus, natural convection would eventually mix the liquid waste in SY-101 but would be very slow to achieve nearly complete mixing. These simulations indicate that the mixing of S-112 and SY-101 wastes in Tank SY-101 is a very slow process, and the density difference between the two wastes would further limit mixing. It is expected to take days or weeks to achieve relatively complete mixing in Tank SY-101.

  4. 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

  5. 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

  6. Riser configuration, Tank 241-A-105, light duty utility arm

    International Nuclear Information System (INIS)

    The light-duty utility arm (LDUA) is a seven-joint stainless steel robotic arm with a payload capacity of 75 lb. The robotic arm is deployed vertically with a maximum vertical reach of 63 ft. and a maximum horizontal reach of 13.5 ft. The functional requirements of the LDUA system are mapping and characterization of waste in Hanford single-shell tanks (SST) before and during waste retrieval. The LDUA system consists of a mobile deployment system (MDS), a vertical positioning mast (VPM), a tank riser interface confinement (TRIC), the LDUA, and a controller subsystem or support trailer. Currently, the system is in design and is subject to change; however, the LDUA or robotic arm will be deployed through a 12-in. riser above the tank dome. Field trips were performed to gather specifics for future deployment of the LDUA in Tank 241-A-105. The purpose of this report is to support two previous reports for the investigation of SSTs for deployment of the LDUA system. The first report identified the availability of risers while the second report identified the availability of Tanks 241-A-105, 241-A-S-109, 241-A-T-101, and 241-A-T-109 for deployment of the LDUA system. The second report also identified those 4- and 12-in. risers that could be used for deployment of the LDUA and camera system. This report addresses accessibility to the 241-A Tank Farm and the usability of the Tank 241-A-105 risers. The following information for assisting in the design and deployment of the LDUA will be discussed in this report: radiation survey; flange identification; high resolution video; computer simulated model; and field survey

  7. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-04-01

    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. 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.

  9. 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.

  10. 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

  11. 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

  12. 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

  13. Comparison of two leg phantoms containing (241)Am in bone.

    Science.gov (United States)

    Kramer, Gary H; Hauck, Barry; Capello, Kevin; Rühm, Werner; El-Faramawy, Nabil; Broggio, David; Franck, Didier; Lopez, Maria Antonia; Navarro, Teresa; Navarro, Juan Francisco; Perez, Begoña; Tolmachev, Sergei

    2011-09-01

    Three facilities (CIEMAT, HMGU and HML) have used their in vivo counters to compare two leg phantoms. One was commercially produced with (241)Am activity artificially added to the bone inserts. The other, the United States Transuranium and Uranium Registries' (USTUR) leg phantom, was manufactured from (241)Am-contaminated bones resulting from an intake. The comparison of the two types of leg phantoms showed that the two phantoms are not similar in their activity distributions. An error in a bone activity estimate could be quite large if the commercial leg phantom is used to estimate what is contained in the USTUR leg phantom and, consequently, a real person. As the latter phantom was created as a result of a real contamination, it is deemed to be the more representative of what would actually happen if a person were internally contaminated with (241)Am. PMID:21799341

  14. Method comparison for 241Am emergency urine bioassay.

    Science.gov (United States)

    Li, Chunsheng; Sadi, Baki; Benkhedda, Karima; St-Amant, Nadereh; Moodie, Gerry; Ko, Raymond; Dinardo, Anthony; Kramer, Gary

    2010-10-01

    241Am is one of the high-risk radionuclides that might be used in a terrorist attack. 241Am in urine bioassay can identify the contaminated individuals who need immediate medical intervention and decontamination. This paper compares three methods for the measurement of 241Am in urine, namely liquid scintillation counting (LSC), inductively coupled plasma mass spectrometry (ICP-MS) and gamma spectrometry (GS), at two levels, 20 and 2 Bq l(-1). All three methods satisfied the ANSI N13.30 radio-bioassay criteria for accuracy and repeatability. ICP-MS offered the best sensitivity and fastest sample turnaround; however, the ICP-MS system used in this work may not be available in many bioassay laboratories. LSC and GS are more commonly available instruments. GS requires minimal or no sample preparation, which makes it a good candidate method. Moreover, the sample throughput can be significantly improved if the GS and LSC methods are automated. PMID:20573683

  15. Uptake of americium-241 by algae and bacteria

    International Nuclear Information System (INIS)

    The uptake of americium by three algae, scenedesmus obliquus, selenastrum capricomutum and chlorella pyrenosdosa and a bacterium aeromonas hydrophila was studied. Live and fixed cells of each algal species and live bacterial cells were used. it is shown that algae and bacteria concentrate americium 241 to a high degree which makes them important links in the biomagnification phenomenon which may ultimately lead to a human hazard and be potentially important in recycling Am 241 in the water column and mobilization from sediments. Chemical fixation of algal cells caused increased uptake which indicated that uptake is by passive diffusion and probably due to chemical alteration of surface binding sites. (U.K.)

  16. 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

  17. 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

  18. Analytical test results for archived core composite samples from tanks 241-TY-101 and 241-TY-103

    Energy Technology Data Exchange (ETDEWEB)

    Beck, M.A.

    1993-07-16

    This report describes the analytical tests performed on archived core composite samples form a 1.085 sampling of the 241-TY-101 (101-TY) and 241-TY-103 (103-TY) single shell waste tanks. Both tanks are suspected of containing quantities of ferrocyanide compounds, as a result of process activities in the late 1950`s. Although limited quantities of the composite samples remained, attempts were made to obtain as much analytical information as possible, especially regarding the chemical and thermal properties of the material.

  19. 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.

  20. 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.

  1. 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

  2. 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...

  3. 8 CFR 241.15 - Countries to which aliens may be removed.

    Science.gov (United States)

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Countries to which aliens may be removed. 241.15 Section 241.15 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS APPREHENSION AND DETENTION OF ALIENS ORDERED REMOVED Post-hearing Detention and Removal § 241.15 Countries...

  4. Tank 241-BY-103 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. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-103

  5. 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

  6. 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

  7. The Cases of Internal Contamination with 241Am

    International Nuclear Information System (INIS)

    Full text: Up to present time, 14 people with intake of 241Am were measured by direct methods and also their excreta were analysed. Different approaches for the estimation of whole body content of 241Am were used. For the direct measurement, method of counting of 241Am in the skull is the most sensitive one. Introduction of this method for the routine in vivo measurements of the workers means that more cases with 241Am internal contamination were identified than before, when only simple whole body counting has been used. The most sensitive method is excretion analysis, which is, of course, quite time consuming. The interpretation of it is much more dependent on the assumed time of intake. Evaluation of the intake from the measurement in the skeleton is less dependent on the time of intake. It is not sensitive enough for monitoring of occupational exposure. This method is especially suitable for follow up of cases with old intakes. When higher inhalation intakes occur (both continuous and single accidental), combination of both approaches direct measurements in vivo and excretion analysis helps to estimate time of intake and enable to estimate committed effective dose in a realistic way. (author)

  8. 49 CFR 241.9 - Prohibition against extraterritorial dispatching; exceptions.

    Science.gov (United States)

    2010-10-01

    ... from Canada or Mexico pursuant to the regulations contained in 49 CFR part 241, revised as of October 1... emergency situation, a railroad may require or permit one of its dispatchers located outside the United... or by electronic mail. (3) A list of the States that make up the FRA regions and the street and...

  9. Tank plan for tank 241-C-104 retrieval testing

    Energy Technology Data Exchange (ETDEWEB)

    HERTING, D.L.

    1999-05-21

    Tank 241-C-104 has been identified as one of the first tanks to be retrieved for high-level waste pretreatment and immobilization. Retrieval of the tank waste will require dilution. Laboratory tests are needed to determine the amount of dilution required for safe retrieval and transfer of feed. The proposed laboratory tests are described in this document.

  10. Test plan for tank 241-C-104 retrieval testing

    International Nuclear Information System (INIS)

    Tank 241-C-104 has been identified as one of the first tanks to be retrieved for high-level waste pretreatment and immobilization. Retrieval of the tank waste will require dilution. Laboratory tests are needed to determine the amount of dilution required for safe retrieval and transfer of feed. The proposed laboratory tests are described in this document

  11. 24 CFR 241.1068 - Renegotiation of an equity loan.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Renegotiation of an equity loan... AUTHORITIES SUPPLEMENTARY FINANCING FOR INSURED PROJECT MORTGAGES Insurance for Equity Loans and Acquisition Loans-Eligibility Requirements § 241.1068 Renegotiation of an equity loan. The Commissioner...

  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. 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.

  14. 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

  15. 39 CFR 241.2 - Stations and branches.

    Science.gov (United States)

    2010-07-01

    ... Service UNITED STATES POSTAL SERVICE ORGANIZATION AND ADMINISTRATION ESTABLISHMENT CLASSIFICATION, AND DISCONTINUANCE § 241.2 Stations and branches. (a) Description. (1) Stations are established within the corporate limits or boundary, and branches are established outside the corporate limits or boundary of the...

  16. 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

  17. 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...

  18. Sentinel node biopsy for melanoma: a study of 241 patients

    DEFF Research Database (Denmark)

    Chakera, Annette Hougaard; Drzewiecki, Krzysztof Tadeusz; Jakobsen, Annika Loft;

    2004-01-01

    The aim of this study was to evaluate the sentinel node biopsy (SNB) technique for melanoma using both radiocolloid and blue dye in 241 clinically N0 patients with melanomas >1.0 mm, or thinner lesions exhibiting regression/ulceration. We showed that an increase in injected radioactivity increased...

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

    International Nuclear Information System (INIS)

    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.

  20. Project W-320, 241-C-106 sluicing, master calculation list

    International Nuclear Information System (INIS)

    This supporting document has been prepared to make the Master Calculation List readily retrievable. The list gives the status of the calculation (as-built, not used, applied, etc.), the calculation title, its originator, comments, and report number under which it was issued. Tank 241-C-106 has been included on the High Heat Load Watch List

  1. 36 CFR 241.2 - Cooperation in wildlife management.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Cooperation in wildlife... FISH AND WILDLIFE General Provisions § 241.2 Cooperation in wildlife management. The Chief of the... other uses and services of the national forests, and, in cooperation with the Fish and Game...

  2. Dicty_cDB: CHE241 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available CH (Link to library) CHE241 (Link to dictyBase) - - - Contig-U16260-1 - (Link to Original site) ... AY305530 |pid:none) Macrobiotus islandicus voucher Mis ... 172 2e-42 AY305532_1( AY305532 |pid:none) Richt ...

  3. 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.

  4. 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.

  5. 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.

  6. Tank 241AP104 Grab Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    TEMPLETON, A.M.

    2000-11-09

    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-AP-104. The purpose of this sampling event is to obtain information about the characteristics of the contents of 241-AP-104 required to provide sample material to the Waste Treatment Contractor. Grab samples will be obtained from riser 001 to provide sufficient material for the chemical analyses and tests required to satisfy these data quality objectives and ICD-23. The 222-S Laboratory will receive samples; composite the samples; perform chemical analyses on composite samples; and provide samples to the Waste Treatment Contractor and the Process Chemistry Laboratory. The Process Chemistry Laboratory at the 222-S Laboratory Complex will perform process tests to evaluate the behavior of the 241-AP-104 waste undergoing the retrieval and treatment scenarios defined in the applicable DQOs. The Waste Treatment Contractor will perform process verification and waste form qualification tests. Requirements for analyses of samples originating in the L & H DQO process tests will be documented in the corresponding test plan (Person 2000) and are not within the scope of this SAP. This report provides the general methodology and procedures to be used in the preparation, retrieval, transport, analysis, and reporting of results from grab samples retrieved from tank 241-AP-104.

  7. Methods of assessment of whole body 241Am content

    International Nuclear Information System (INIS)

    This paper discuss an influence of different skull phantoms on efficiency of the measurement. Description of some methods of an assessment of the 241Am content in the human skeleton from measurements performed over long bones of the human body is also offered. (authors)

  8. 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

  9. 36 CFR 241.20 - Scope and applicability.

    Science.gov (United States)

    2010-07-01

    ... of National Forest System lands nationwide in 36 CFR part 251—Land Uses. (b) The rules of this... AND WILDLIFE Conservation of Fish, Wildlife, and Their Habitat, Chugach National Forest, Alaska § 241... River portion of the Chugach National Forest, Alaska, is the conservation of fish and wildlife and...

  10. 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

  11. Tank 241-C-103 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, 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-103

  12. 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...

  13. 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

  14. 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

  15. 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

  16. Recovery of Americium-241 from lightning rod by the method of chemical treatment

    International Nuclear Information System (INIS)

    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 (241Am), fewer and Radium 226 (226Ra) 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 241Am radioactive lightning rods using the conventional chemical treatment method using agents and acids to break down the slides. The 241Am recovered was as excitation source and alpha particle generator for analysing samples by X Ray Fluorescence, for fixing the stainless steel 241Am technique was used electrodeposition. (author)

  17. 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.

  18. 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.

  19. Distribution of 241Am in offspring from BALB/c mice injected with 241Am at 14 days of gestation: relation to calcium and iron metabolism and comparison with distribution of 241Am after injection of adults

    International Nuclear Information System (INIS)

    Pregnant mice were given intravenous injections of 241 Am citrate at 14 days of gestation. The fetal skeleton had a higher or similar uptake of 241Am per gram of fresh tissue than the liver. The liver in adults concentrated 5 to 20 times more 241 Am per gram of fresh tissue than the bones. Measurement of changes in calcium and iron content and concentration with time, showed that in developing mice intensive calcification of bones determined uptake of 241Am. The 241Am uptake was related to calcium concentration of the fetal bones, which was greater at 14 days of gestation in the anterior bones, mandibles and calvaria, than in ribs and femurs. Transfer of 241Am to pups via milk resulted in further accumulation of 241Am in skeleton and liver. The incorporation in the skeleton persisted after weaning and contributed to the lifetime body burden. The 241Am concentration decreased rapidly with time after injection in relation to growth of the organs. Radiation dose rates and cumulative radiation doses were calculated for liver and bones of contaminated offspring. (author)

  20. Incorporation of 241Am: effectiveness of late DTPA chelation therapy

    International Nuclear Information System (INIS)

    In four persons who had incorporated 241Am probably by inhalation, a DTPA chelation therapy was initiated several months after incorporation. Excretion measurements and in vivo measurements were performed in order to quantify the enhancement of 241Am excretion and the activity distribution in the body. DTPA was administered 4-11 times as an infusion of 1 g DTPA. Daily excretion rates were raised essentially, up to factors of 65-140 (urine) and 30-50 (faeces) after the first administration. Dose calculations performed on the basis of a modified ICRP 30, Part 4 model yielded dose reductions (e.g. for subject A) of 90%, 28%, 28% and 26% for liver, bone surfaces, red bone marrow and lungs, respectively, corresponding to a reduction of the effective dose equivalent of approximately 40%. (author)

  1. 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

  2. 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.

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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.

  8. 241-AY Double Shell Tanks (DST) Integrity Assessment Report

    International Nuclear Information System (INIS)

    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

  9. Test Plan for Tank 241-AZ-101 Solubility Screening Tests

    International Nuclear Information System (INIS)

    Tank 241-AZ-101 (101-AZ) has been identified as one of the early tanks to be retrieved for waste pretreatment and immobilization. Retrieval of the tank waste from other tanks may require dilution. This test is to determine the effects of dilution on the mass of solids and their composition, which can be compared with tanks where dilution is required. This test plan gives test instructions, example data sheets, a waste compatibility review, and a waste stream fact sheet

  10. 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.

  11. Rotary mode core sampling approved checklist: 241-TX-113

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, K.D.

    1998-08-03

    The safety assessment for rotary mode core sampling was developed using certain bounding assumptions, however, those assumptions were not verified for each of the existing or potential flammable gas tanks. Therefore, a Flammable Gas/Rotary Mode Core Sampling Approved Checklist has been completed for tank 241-TX-113 prior to sampling operations. This transmittal documents the dispositions of the checklist items from the safety assessment.

  12. Dicty_cDB: VHD241 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available VH (Link to library) VHD241 (Link to dictyBase) - - - Contig-U16477-1 - (Link to Original site) ... ES282011 |ES282011.1 PP034C10.XT7 non-sporulating culture ... of P. brassicae Phytophthora brassicae cDNA, mRNA ... ES278287 |ES278287.1 PP032A10.XT7 non-sporulating culture ... of P. brassicae Phytophthora brassicae cDNA, mRNA ...

  13. 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.

  14. 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

  15. 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

  16. 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

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

    International Nuclear Information System (INIS)

    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

  18. 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.

  19. 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.)

  20. 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)

  1. Lunar Surface Stirling Power Systems Using Am-241

    Science.gov (United States)

    Schmitz, Paul C.; Penswick, L. Barry; Shaltens, Richard K.

    2009-01-01

    For many years NASA has used the decay of Pu-238 (in the form of the General Purpose Heat Source (GPHS)) as a heat source for Radioisotope Thermoelectric Generators (RTG), which have provided electrical power for many NASA missions. While RTG's have an impressive reliability record for the missions in which they have been used, their relatively low thermal to electric conversion efficiency (-5% efficiency) and the scarcity of Plutoinium-238 (Pu-238) has led NASA to consider other power conversion technologies. NASA is considering returning both robotic and human missions to the lunar surface and, because of the long lunar nights (14 earth days) isotope power systems are an attractive candidate to generate electrical power. NASA is currently developing the Advanced Stirling Radioisotope Generator (ASRG) as a candidate higher efficiency power system that produces greater than 160 watts with 2 GPHS modules at the beginning of life (BOL) (-30% efficiency). The ASRG uses the same Pu-238 GPHS modules, which are used in RTG, but by coupling them to a Stirling convertor provides a 4-fold reduction in the number of GPHS modules. This study considers the use of Americium 241 (Am-241) as a substitute for the Pu-238 in Stirling convertor based Radioisotope Power Systems (RPS) for power levels from 1 O's of watts to 5 kWe. The Am-241 is used as a replacement for the Pu-238 in GPHS modules. Depending on power level, different Stirling heat input and removal systems are modeled. It was found that substituting Am-241 GPHS modules into the ASRG reduces power output by about 1/5 while maintaining approximately the same system mass. In order to obtain the nominal 160 watts electrical output of the Pu-238 ASRG requires 10 Am-241 GPHS modules. Higher power systems require changing from conductive coupling heat input and removal from the Stirling convertor to either pumped loops or heat pipes. Liquid metal pumped loops are considered as the primary heat transportation on the hot end and

  2. Acceptance test report for the Tank 241-C-106 in-tank imaging system

    International Nuclear Information System (INIS)

    This document presents the results of Acceptance Testing of the 241-C-106 in-tank video camera imaging system. The purpose of this imaging system is to monitor the Project W-320 sluicing of Tank 241-C-106. The objective of acceptance testing of the 241-C-106 video camera system was to verify that all equipment and components function in accordance with procurement specification requirements and original equipment manufacturer's (OEM) specifications. This document reports the results of the testing

  3. 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.

  4. 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.

  5. {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.)

  6. 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

  7. 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.

  8. Recovery of 241Am/Be neutron sources, Wooster, Ohio

    International Nuclear Information System (INIS)

    In August 1997, the Nuclear Regulatory Commission (NRC) submitted to the US Department of Energy (DOE) a partial list of licensed radioactive sealed sources to be recovered under a pilot project initiating Radioactive Source Recovery Program (RSRP) operations. The first of the pilot project recoveries was scheduled for September 1997 at Eastern Well Surveys in Wooster, Ohio, a company with five unwanted sealed sources on the NRC list. The sources were neutron emitters, each containing 241Am/Be with activities ranging from 2.49 to 3.0 Ci. A prior radiological survey had established that one of these sources, a Gulf Nuclear Model 71-1 containing 3 Ci of 241Am, was contaminated with 241Am and might be leaking. The other four sources were obsolete and could no longer be used by Eastern Well Surveys for their intended application in well-logging applications due to NRC decertification of these sources. All of the sources exceeded the limits established for Class C waste under 10 CFR 61.55 and, as a result, are the ultimate responsibility of the DOE under the provisions of PL 99-240. This report describes the cooperative effort between the DOE and NRC to recover the sources and transport them to Los Alamos National Laboratory (LANL) for deactivation under the RSRP. This operation alleviated any potential risk to the public health and safety from the site which might result from the leaking neutron sources or the potential mismanagement of unwanted sources. The on-site recovery occurred on September 23, 1997, and was performed by personnel from LANL and its contractor and was observed by staff from the Region III office of the NRC. All aspects of the recovery were successfully accomplished, and the sources were received at LANL on September 29, 1997. Experience gained during this operation will be used to formulate operational poilicies and procedures which will contribute to the eventual routine recovery operations of a full-scale RSRP

  9. A case of occupational internal contamination with 241Am

    International Nuclear Information System (INIS)

    An internal contamination with 241Am was detected in a worker during a routine monitoring of workers from a company producing Am sources for smoke detectors and Am-Be neutron sources. During the 4-year period after the exposure, the number of urine and faecal samples from the worker were analysed; in vivo measurements were also performed. Specific values for absorption parameters of the human respiratory tract model and particle transport values were applied to improve the model fit to the measurement data. A good agreement of the bioassay data with the so-modified model predictions was obtained. (authors)

  10. Progress toward mitigation of flammable gas Tank 241-SY-101

    International Nuclear Information System (INIS)

    The mixing pump installed in Hanford Site tank 241-SY-101 has been shown to be effective in releasing flammable gases in a controlled manner. This controlled release of gas prevents the accumulation and episodic release above flammable limits. More work needs to be done to optimize the pumping operation, and to evaluate the long-term effects of mixing so as to assure that no undesirable changes have occurred to the waste. Other alternative mitigation concepts are still being evaluated as a backup to mixing

  11. 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.

  12. Dicty_cDB: SLF241 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available d:none) Xenopus laevis middle molecular weight... 33 3.8 BC074454_1( BC074454 |pid:none) Xenopus laevis midd...*nnnnkrkkkk Frame B: ---****qq********lfkyvrtitnfsifsstihsikni*nv**ntiksintirfr*i ns...) Podospora anserina genomic DNA ch... 33 2.9 AM270295_28( AM270295 |pid:none) Aspergillus niger contig An13...LF241 (Link to dictyBase) Atlas ID - NBRP ID G22463 dictyBase ID DDB0190606 Link to Contig Contig-U04076-1 Original site URL ht...TSLSISKQQKLKESDSDKKEKNDESSSTGVPIVKQE VTEEKQQELKQQELKQQELKQQELKQQQQEKEEKE Homology vs CSM-cDNA Score E Sequences producing signi

  13. Sentinel node biopsy for melanoma: a study of 241 patients

    DEFF Research Database (Denmark)

    Chakera, Annette Hougaard; Drzewiecki, Krzysztof Tadeusz; Jakobsen, Annika Loft; Juhl, Birgitte Ravn

    2004-01-01

    The aim of this study was to evaluate the sentinel node biopsy (SNB) technique for melanoma using both radiocolloid and blue dye in 241 clinically N0 patients with melanomas >1.0 mm, or thinner lesions exhibiting regression/ulceration. We showed that an increase in injected radioactivity increased...... nine haematoxylin and eosin (HE)-negatives, all of which were found by immunohistochemistry. The false negative rate forthe SNB procedure was 4% (2/55). The complication rate was 6% after SNB and 29% after complete node dissection. In conclusion, SN status is a strong prognostic factor in melanoma...

  14. 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

  15. 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)

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

    International Nuclear Information System (INIS)

    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. 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)

  18. Contingency plan for deployment of the void fraction instrument in Tank 241-AY-102

    International Nuclear Information System (INIS)

    High-heat producing sludge from tank 241-C-106 will be sluiced and transferred to tank 241-AY-102 beginning in October 1998. Safety analyses have postulated that after retrieval, the waste in 241-AY-102 may generate and retain unsafe levels of flammable gases (Noorani 1998, Pasamebmetoglu etal. 1997). Unsafe levels of retained gas are not expected, but cannot be ruled out because of the large uncertainty in the gas generation and retention rates. The Tank Waste Remediation System Basis for Interim Operation (Noorani 1998) identifies the need for a contingency plan to add void fraction monitoring to tank 241-AY-102 within 2 weeks of the identification of flammable gas buildup that would warrant monitoring. The Tank 241-C-106 Waste Retrieval Sluicing System Process Control Plan (Carothers et al. 1998) committed to providing a contingency plan for deployment of the void fraction instrument (VFI) in tank 241-AY-102. The VFI determines the local void fraction of the waste by compressing a waste sample captured in a gas-tight test chamber. The sample chamber is mounted on the end of a 76-cm (2.5-ft) arm that can be rotated from vertical to horizontal when the instrument is deployed. Once in the waste, the arm can be positioned horizontally and rotated to sample in different areas below the riser. The VFI is deployed using a crane. The VFI has been deployed previously in 241-AW, 241-AN, and 241-SY tank farms, most recently in tank 241-SY-101 in June and July 1998. An additional test in tank 241-SY-101 is planned in September 1998. Operating instructions for the VFI are included in the Void Fraction Instrument Operation and Maintenance Manual (Pearce 1994)

  19. Tank characterization report for double-shell tank 241-AN-102

    Energy Technology Data Exchange (ETDEWEB)

    Jo, J., Westinghouse Hanford

    1996-08-29

    This characterization report summarizes the available information on the historical uses, current status, and sampling and analysis results of waste stored in double-shell underground storage tank 241- AN-102. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09 (Ecology et al. 1996). Tank 241-AN-102 is one of seven double-shell tanks located in the AN Tank Farm in the Hanford Site 200 East Area. The tank was hydrotested in 1981, and when the water was removed, a 6-inch heel was left. Tank 241-AN-102 began receiving waste from tank 241-SY-102 beginning in 1982. The tank was nearly emptied in the third quarter of 1983, leaving only 125 kL (33 kgal) of waste. Between the fourth quarter of 1983 and the first quarter of 1984, tank 241-AN-102 received waste from tanks 241-AY-102, 241-SY-102, 241-AW-105, and 241- AN-101. The tank was nearly emptied in the second quarter of 1984, leaving a heel of 129 kL (34 kgal). During the second and third quarters of 1984, the tank was filled with concentrated complexant waste from tank 241-AW-101. Since that time, only minor amounts of Plutonium-Uranium Extraction (PUREX) Plant miscellaneous waste and water have been received; there have been no waste transfer to or from the tank since 1992. Therefore, the waste currently in the tank is considered to be concentrated complexant waste. Tank 241-AN-102 is sound and is not included on any of the Watch Lists.

  20. Tank characterization report for double-shell tank 241-AN-102

    International Nuclear Information System (INIS)

    This characterization report summarizes the available information on the historical uses, current status, and sampling and analysis results of waste stored in double-shell underground storage tank 241- AN-102. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09 (Ecology et al. 1996). Tank 241-AN-102 is one of seven double-shell tanks located in the AN Tank Farm in the Hanford Site 200 East Area. The tank was hydrotested in 1981, and when the water was removed, a 6-inch heel was left. Tank 241-AN-102 began receiving waste from tank 241-SY-102 beginning in 1982. The tank was nearly emptied in the third quarter of 1983, leaving only 125 kL (33 kgal) of waste. Between the fourth quarter of 1983 and the first quarter of 1984, tank 241-AN-102 received waste from tanks 241-AY-102, 241-SY-102, 241-AW-105, and 241- AN-101. The tank was nearly emptied in the second quarter of 1984, leaving a heel of 129 kL (34 kgal). During the second and third quarters of 1984, the tank was filled with concentrated complexant waste from tank 241-AW-101. Since that time, only minor amounts of Plutonium-Uranium Extraction (PUREX) Plant miscellaneous waste and water have been received; there have been no waste transfer to or from the tank since 1992. Therefore, the waste currently in the tank is considered to be concentrated complexant waste. Tank 241-AN-102 is sound and is not included on any of the Watch Lists

  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. Development of rapid analytical methods for Am-241

    International Nuclear Information System (INIS)

    In the framework of the IAEA Co-ordinated Research Programme on Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples, the original programme of the Department of Nuclear Chemistry was modified at the first RCM in Warsaw, Poland, so that the part dealing with Sr-89,90 was to be omitted. In the first phase of the work (reported in Warsaw) the limits of detection for 241Am by gamma spectrometry of its 35.9% abundant 59.5 keV gamma ray were determined for two detectors, i.e. a low energy photon detector (LEPD) of the maximum size currently commercially available (disc 50 mm diameter, 20 mm deep), and an HP Ge well-type detector with a 5 ml hole. It was intended that the major use of the well-type detector would be to measure 241Am by gamma spectroscopy in small concentrates separated by relatively simple and rapid radiochemical procedures from large bulk samples, thus taking advantage of the high efficiency of the detector combined with a large initial sample size

  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. 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

  5. 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.

  6. 49 CFR 241.11 - Prohibition against conducting a railroad operation dispatched by an extraterritorial dispatcher...

    Science.gov (United States)

    2010-10-01

    ... pursuant to the regulations contained in 49 CFR part 241, revised as of October 1, 2002, may continue to... opportunity to file a waiver request pursuant to § 241.7. (c) Emergencies. (1) In an emergency situation, a... mail. (3) A list of the States that make up the FRA regions and the street and e-mail addresses and...

  7. 8 CFR 241.24 - Notice to transportation line of alien's exclusion.

    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 exclusion. 241.24 Section 241.24 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS APPREHENSION AND DETENTION OF ALIENS ORDERED REMOVED Deportation of Excluded Aliens (for...

  8. 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 §...

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

    International Nuclear Information System (INIS)

    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

  10. Operational test report for hourly recording the level of tank 241-AN-107

    Energy Technology Data Exchange (ETDEWEB)

    Dowell, J.L.

    1996-09-30

    The purpose of this report is to document the existing Enraf Advanced Technology Gauges, Communications Interface Unit, and LOGVR18 software installed at 241-AN tank farm record the level of 241-AN-107 on an hourly basis for up to 10 days.

  11. Acceptance Test Report for the 241-AN-107 Enraf Advanced Technology Gauges

    International Nuclear Information System (INIS)

    This Acceptance Test Report covers the results of the execution of the Acceptance Test Procedure for the 241-AN-107 Enraf Advanced Technology Gauges. The test verified the proper operation of the gauges to measure waste density and level in the 241-AN-107 tank

  12. 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

  13. Assessment of vadose zone radionuclide contamination around Single Shell Tank 241-C-103

    International Nuclear Information System (INIS)

    Five drywells surrounding single shell tank 241-C-103 were logged with the high-purity germanium logging system to investigate possible leakage of radioactive contamination from the tank. The investigation included integration of the drywell survey results with several other data sources. There is no conclusive evidence showing indications that the 241-C-103 tank has leaked

  14. 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.

  15. 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.

  16. 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

  17. 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.

  18. 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 §...

  19. 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...

  20. 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...

  1. Acceptance Test Report for the 241-AN-107 Enraf Advanced Technology Gauges

    Energy Technology Data Exchange (ETDEWEB)

    Dowell, J.L.; Enderlin, V.R.

    1995-06-01

    This Acceptance Test Report covers the results of the execution of the Acceptance Test Procedure for the 241-AN-107 Enraf Advanced Technology Gauges. The test verified the proper operation of the gauges to measure waste density and level in the 241-AN-107 tank.

  2. 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...

  3. 241-SY-101 data acquisition and control system (DACS) operator interface upgrade operational test report

    International Nuclear Information System (INIS)

    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

  4. 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

  5. Structural analysis and evaluation of the 241SY101 tank annulus heat-up

    Energy Technology Data Exchange (ETDEWEB)

    Ziada, H.H.

    1994-10-19

    This document provides the structural analysis (static and thermal loads) of the 241SY101 tank to determine the maximum allowable temperature and rate of heating that could be applied to tank 241SY101 through annulus air heating without detrimental effects to the structural integrity of the concrete and steel liner of the tank.

  6. Structural analysis and evaluation of the 241SY101 tank annulus heat-up

    International Nuclear Information System (INIS)

    This document provides the structural analysis (static and thermal loads) of the 241SY101 tank to determine the maximum allowable temperature and rate of heating that could be applied to tank 241SY101 through annulus air heating without detrimental effects to the structural integrity of the concrete and steel liner of the tank

  7. 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...

  8. 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...

  9. 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

  10. 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.

  11. 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

  12. 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.

  13. 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.

  14. 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.

    2004-10-28

    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.

  15. 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.

  16. 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

  17. Tank 241-AP-107 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Defense Nuclear Facilities Safety Board has directed the DOE to concentrate ear-term sampling and analysis activities on identification and resolution of issues (Conway 1993). 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-44-00 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; Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.'' This document satisfies that requirement for the tank 241-AP-107 (AP-107)

  18. Solubilities of gases in simulated Tank 241-SY-101 wastes

    International Nuclear Information System (INIS)

    Oxygen, nitrogen, hydrogen, methane, and nitrous oxide solubilities were evaluated as a function of temperature in SYl-SIM-93B, a homogeneous simulated waste mixture containing sodium hydroxide, sodium nitrite, sodium nitrate, sodium aluminate, and sodium carbonate, the principal inorganic constituents of the wastes in Tank 241-SY-101. Ammonia solubility data for this simulated waste was obtained as a function of temperature in an earlier study. The choice of a homogeneous waste mixture in this study has the advantage of eliminating complications associated with a changing electrolyte concentration as a function of temperature that would be encountered with a slurry simulant. Dissolution is one of the means by which gases may be retained in Hanford Site wastes. While models are available to estimate gas solubilities in electrolyte solutions, few data are in existence that pertain to highly concentrated, multicomponent electrolytes such as those stored in Hanford Site waste tanks

  19. Simulation and rheological analysis of Hanford Tank 241-SY-101

    International Nuclear Information System (INIS)

    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

  20. 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)

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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.

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

    International Nuclear Information System (INIS)

    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

  7. 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

  8. Mechanisms of gas retention and release: Experimental results for Hanford waste tanks 241-AW-101 and 241-AN-103

    International Nuclear Information System (INIS)

    The 177 storage tanks at Hanford contain a vast array of radioactive waste forms resulting, primarily, from nuclear materials processing. Through radiolytic, thermal, and other decomposition reactions of waste components, gaseous species including hydrogen, ammonia, and the oxidizer nitrous oxide are generated within the waste tanks. Many of these tanks are known to retain and periodically release quantities of these flammable gas mixtures. The primary focus of the Flammable Gas Project is the safe storage of Hanford tank wastes. To this end, we strive to develop an understanding of the mechanisms of flammable gas retention and release in Hanford tanks through laboratory investigations on actual tank wastes. These results support the closure of the Flammable Gas Unreviewed Safety Question (USQ) on the safe storage of waste tanks known to retain flammable gases and support resolution of the broader Flammable Gas Safety Issue. The overall purpose of this ongoing study is to develop a comprehensive and thorough understanding of the mechanisms of flammable gas retention and release. The first objective of the current study was to classify bubble retention and release mechanisms in two previously untested waste materials from Tanks 241-AN-103 (AN-103) and 241-AW-101 (AW-101). Results were obtained for retention mechanisms, release characteristics, and the maximum gas retention. In addition, unique behavior was also documented and compared with previously studied waste samples. The second objective was to lengthen the duration of the experiments to evaluate the role of slowing bubble growth on the retention and release behavior. Results were obtained for experiments lasting from a few hours to a few days

  9. Tank 241-S-102, Core 232 analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the analytical laboratory report for tank 241-S-102 push mode core segments collected between March 5, 1998 and April 2, 1998. The segments were subsampled and analyzed in accordance with the Tank 241-S-102 Retained Gas Sampler System Sampling and Analysis Plan (TSAP) (McCain, 1998), Letter of Instruction for Compatibility Analysis of Samples from Tank 241-S-102 (LOI) (Thompson, 1998) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Mulkey and Miller, 1998). The analytical results are included in the data summary table (Table 1)

  10. 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.

  11. 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

  12. 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

  13. 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.

  14. 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.

  15. 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

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

    International Nuclear Information System (INIS)

    Ninety five surface scrape samples were collected at the Ravenglass saltmarsh and analysed for radionuclides by alpha spectrometry (238Pu and 239,240Pu), gamma spectrometry (241Am and 137Cs) and liquid scintillation counting (241Pu). Both 241Am and 137Cs 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.

  17. Analysis of 241Pu radioactivity by isotope dilution-extraction liquid scintillation spectrometer

    International Nuclear Information System (INIS)

    The radionuclide 241Pu decays predominantly by β emission with a half-life 14.29 a. The branching ratio of its α-emission is negligibly small. However, it is difficult to measure the radioactivity of 241Pu in a Pu containing complicated sample because of its low β energy. A method for determination of 241Pu in high level liquid waste (HLLW) was developed. It consists of the following steps. The first step is to separate and purify plutonium from HLLW. The chemical yield of plutonium is higher than 95%. Secondly, a determination method by using modern liquid scintillation spectrometry combined with isotope dilution, solvent extraction, and ion exchange chromatography was established to analyze the 241Pu content in HLLW. (authors)

  18. Final report for tank 241-U-109, rotary and push mode cores 123, 124 and 128

    International Nuclear Information System (INIS)

    This report contains tables of the analytical results from sampling tank 241-U-109 using two types of samplers. Activity levels of radionuclides are tabulated. This tank has been on the Hydrogen Watch List

  19. 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.

  20. 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

  1. Determination of the 241Pu(n,f) reaction cross sections by surrogate ratio method

    International Nuclear Information System (INIS)

    In a recent work, direct measurement of neutron induced fission cross section of 241Pu(T1/2 = 14.1 yrs), has been carried out using neutron time of flight. Differences between the reported experimental measurement and evaluation by standard libraries exceeds by 30%, thus it is suggested to carry out further confirmatory measurements on 241Pu(n,f) cross sections. In this paper, we report the use of 238U(6Li,d)242Pu and 232Th(6Li,d)236U transfer reactions as surrogate of 241Pu(n,f) and 235U(n,f) compound nuclear reactions respectively. By employing the surrogate ratio method (SRM) and taking 235U(n,f) as reference, the 241Pu(n,f) cross sections have been determined in the equivalent neutron energy range of 11.0 MeV-16.0 MeV

  2. 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.

  3. Tank characterization report for single-shell tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Winters, W.I., Westinghouse Hanford

    1996-06-26

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-C-103. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

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

    Energy Technology Data Exchange (ETDEWEB)

    Conner, J.M., Westinghouse Hanford

    1996-09-11

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in tank 241-SY-103. This report supports the requirements of Tri-Party Agreement Milestone M-44 09.

  5. Tank characterization report for single-shell tank 241-B-203

    Energy Technology Data Exchange (ETDEWEB)

    Jo, J., Westinghouse Hanford

    1996-07-03

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in tank 241-B-203. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

  6. Tank 241-B-203 push mode core sampling and analysis plan. Revision 1

    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 two push-mode core samples from tank 241-B-203 (B-203)

  7. Tank characterization report for single-shell tank 241-T-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-T-106. This report supports the requirements of Tri-Party Agreement Milestone M-44-09

  8. 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

  9. Tank characterization report for double-shell tank 241-SY-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-SY-103. This report supports the requirements of Tri-Party Agreement Milestone M-44 09

  10. 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.

  11. 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.

  12. 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

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

    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-B-107. This report supports the requirements of the Tri-Party Agreement Milestone M-44-ISB

  14. Acceptance test report for the 241-SY-101 Flexible Receiver Gamma Detector System

    International Nuclear Information System (INIS)

    This Acceptance Test Report is for the 241-SY-101 Flexible Receiver Gamma Detector System. This test verified that the data logger and data converter for the gamma detector system functions as intended

  15. Tank characterization report for single-shell tank 241-T-108

    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-108. This report supports the requirements of Tri-Party Agreement Milestone M-44-09

  16. Tank 241-A-101 cores 154 and 156 analytical results for the final report

    International Nuclear Information System (INIS)

    This report contains tables of the analytical results from sampling Tank 241-A-101 for the following: fluorides, chlorides, nitrites, bromides, nitrates, phosphates, sulfates, and oxalates. This tank is listed on the Hydrogen Watch List

  17. 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.

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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.

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

    International Nuclear Information System (INIS)

    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

  5. Final results of double-shell tank 241-AY-102 ultrasonic inspection

    International Nuclear Information System (INIS)

    This document presents the results and documentation of the nondestructive ultrasonic examination of tank 241-AY-102. 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-AY-102 primary tank wall and welds. The inspection found some indication of insignificant general and local wall thinning with no cracks detected

  6. Closed out Tank 241-SY-101 DACS system change request number-sign 1--100

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  8. Tank 241-AP-106 tank characterization plan: Revision 1

    International Nuclear Information System (INIS)

    Tank 241-AP-106 (AP-106) is a candidate feed tank which is expected to be processed at the 242-A Evaporator. Three issues related to the overall concern of the evaporator must be evaluated: compatibility of the candidate waste with respect to feed tank, slurry tank, and evaporator requirements; safety parameters of the candidate waste tank to avoid a facility condition which is outside the safety boundaries; and compliance of the waste as dictated by regulations from various government and environmental agencies. The characterization efforts of this Tank Characterization Plan are focused on the resolution of the issues above. To evaluate the potential for waste incompatibility with the feed tank, slurry tank, and evaporator, as well as relevant safety issues, analyses will be performed on the grab samples obtained from tank AP-106. These analyses are discussed in Section 4.0. Once the characterization of tank AP-106 has been performed, the waste compatibility and safety assessment shall be conducted. This effort is discussed elsewhere

  9. 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

  10. 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

  11. 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.

  12. Incorporation monitoring during decommissioning - Am-241 problem in Gundremmingen

    International Nuclear Information System (INIS)

    The decommissioning of the nuclear power station Gundremmingen unit A (KRB A) began in 1983 and should be finished in 2003. 153 people were included in the regular incorporation monitoring programme during the decommissioning between 1993 and 1998. The most important nuclide was Am-241 which has a contribution of 60% to the committed effective dose. The assessment of intake and dose were carried out in accordance to the German guidelines. The mean value for the effective dose was 1.5 mSv (geometric mean 0.67 mSv), calculated over all dose assessments. Intakes more than the ALI could not be detected from 1996 to 1998. Decontamination and decomposition of radioactively contaminated parts of the plant and handling of radioctive waste were found to be the activities with the highest risk of incorporation. Intensive regular cleaning and decontamination of the working places were established to avoid or to reduce incorporations. However, the most important requirement is to increase the workers sensitivity to the problems of incorporation of radioactive material by careful instructions related to their individual work. The strict realization of these measures have clearly reduced the risk of intake as can be seen from the results of the incorporation monitoring programme. (orig.)

  13. 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.

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

    International Nuclear Information System (INIS)

    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

  15. 241Am distribution in foetal haemopoietic organs of Balb/c mice

    International Nuclear Information System (INIS)

    Developing haemopoietic organs and the fetal skeleton are considered target organs after internal contamination of the mother with actinides. Pregnant Balb/c mice were injected with 14 kBq 241Am citrate at day 14 of gestation, at the time haematopoiesis rises in the foetal liver. The 241Am retention was measured between one day after injection until 3 months after birth. The activities of 241Am in carcass and liver were measured by gamma-counting in a NaI (Tl) well-type crystal, skeletal parts and intestinal tract were measured by alpha-counting in a ZnS counter. Liver and skeleton concentrated 241Am but in the skeleton the 241Am concentration varied considerably between various parts: e.g. mandible and calvarium showed a 5 fold higher 241Am concentration compared to the femur. Comparison was made between mice which stayed with their mother till 3 weeks after birth and mice which received a foster-mother, this allows to calculate the importance of the maternal contamination via milk to the dose of the young mice. The retention data were used to calculate initial dose rates and absorbed radiation doses in function of time in the organs at risk. 15 refs.; 1 figure; 2 tabs

  16. 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

  17. Flammable gas tank waste level reconciliation tank 241-SX-105

    International Nuclear Information System (INIS)

    Fluor Daniel Northwest was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 241-SX-105 (SX-105, typical). The trapped gas evaluation document states that Tank SX-105 exceeds the 25% of the lower flammable limit criterion, based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the Welty Report is the basis for this letter report. The Welty Report is also a part of the trapped gas evaluation document criteria. The Welty Report contains various tank information, including: physical information, status, levels, and dry wells. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unaccounted for surface level rise. From 1973 through 1980, the Welty Report tracked Tank SX-105 transfers and reported a net cumulative change of 20.75 in. This surface level increase is from an unknown source or is unaccounted for. Duke Engineering and Services Hanford and Lockheed Martin Hanford Corporation are interested in determining the validity of unexplained surface level changes reported in the Welty Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unaccounted for surface level changes as shown in the Welty Report from 1973 through 1980. Tank SX-105 initially received waste from REDOX starting the second quarter of 1955. After June 1975, the tank primarily received processed waste (slurry) from the 242-S Evaporator/Crystallizer and transferred supernate waste to Tanks S-102 and SX-102. The Welty Report shows a cumulative change of 20.75 in. from June 1973 through December 1980

  18. 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

  19. 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.)

  20. Americium 241 in vegetation of natural biocenoses and agrocenoses on Belarus territories contaminated with Chernobyl fall-out

    International Nuclear Information System (INIS)

    As a result of beta-decay of plutonium 241 the content of americium 241 increases progressively in soils, contaminated with Chernobyl trans uranium elements. Americium 241 displayed higher (0,5 - 1,5-fold) biological mobility than isotopes of plutonium 239, 240. Activity of americium 241 in surface phyto mass of wild and cultural plants varies from 0,04 to 5,9 Bq/kg of dry weight. Americium 241 contribution to the total trans uranium elements contamination of plants made up 60 - 80% in 1996 - 1998. Investigation of trials from the areas adjacent to the 30-km zone showed that mobility of americium 241 and plutonium was 5 - 15 times as high as in the zone

  1. 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)

  2. 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

  3. 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

  4. $^{241}$Am: a difficult actinide for (n,$\\gamma$) cross section measurement

    CERN Document Server

    Rossbach, M

    2014-01-01

    Many attempts have been made in the past to determine accurate cross section data for neutron capture in $^{241}$Am, however, the reported data for thermal neutron energies scatter by more than 25% around 680 b. The situation is complicated as the product of the capture reaction is twofold: $^{241}$Am (n,$\\gamma$)$^{242g}Am,^{242m}$Am. The production ratio for ground- and metastable state is uncertain but also $^{241}$Am exhibits a very low first resonance at about 0.3 eV and this might influence the 1/v behaviour at thermal energy, 0.025 eV. In our experiments, we are using cold neutrons at the PGAA facilities of the Budapest and Garching Research Reactors, hence, we assume to be independent of the perturbations from possible non-1/v behaviour.

  5. Accumulation of 241Am by suspended matter, diatoms and aquatic weeds of the Yenisei River

    International Nuclear Information System (INIS)

    In this work we experimentally estimated the capacities of the key components of the Yenisei River (Russia): particulate suspended matter (seston), diatom microalgae, and submerged macrophytes for accumulating 241Am from water. In our experiments large particles of seston (>8 μm), comparable in size with diatoms, took up most of americium from water. The accumulation of americium by isolated diatom algae (Asterionella formosa and Diatoma vulgare) was lower than by total seston. The concentration factors (CFs) of 241Am for seston of the Yenisei River in our experiments were (2.8-6.9).105; for diatoms - (1.5-4.2).104. The CFs for aquatic plant Elodea canadensis were within the same order of magnitude as those for diatoms. Activity concentration and CFs of 241Am were nearly the same in experiments under dark and light conditions. This is indicative of an energy independent mechanism of americium uptake from the water by diatoms and submerged macrophytes.

  6. Adsorption of 241Am and 226Ra from natural water by wood charcoal

    International Nuclear Information System (INIS)

    The adsorption of 241Am and 226Ra from natural water by a granulated wood charcoal was investigated as a function of the solution pH, in the range 4-10, and of the water flow, in the range 3.5-42 cm3/min. The percentage adsorption of 241Am (fairly constant at >80% for all pHs) was greater than that of 226Ra (which increased with increasing pH from ∼40% up to >80%). The results are explained by considering the different species of each radionuclide present at the pH values of the solution at the end of the adsorbent column, and the pH of the point of zero charge of the adsorbent. At pH 6, the elimination of 241Am from natural water was independent of the water flow, while the elimination of 226Ra declined linearly as the flow rate was increased

  7. 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

  8. Tank characterization report for double-shell tank 241-AP-105

    International Nuclear Information System (INIS)

    Double-Shell Tank 241-AP-105 is a radioactive waste tank most recently sampled in March of 1993. Sampling and characterization of the waste in Tank 241-AP-105 contributes toward the fulfillment of Milestone M-44-05 of the Hanford Federal Facility Agreement and Consent Order (Ecology, EPA, and DOE, 1993). Characterization is also needed tot evaluate the waste's fitness for safe processing through an evaporator as part of an overall waste volume reduction program. Tank 241-AP-105, located in the 200 East Area AP Tank Farm, was constructed and went into service in 1986 as a dilute waste receiver tank; Tank 241AP-1 05 was considered as a candidate tank for the Grout Treatment Facility. With the cancellation of the Grout Program, the final disposal of the waste in will be as high- and low-level glass fractions. The tank has an operational capacity of 1,140,000 gallons, and currently contains 821,000 gallons of double-shell slurry feed. The waste is heterogeneous, although distinct layers do not exist. Waste has been removed periodically for processing and concentration through the 242-A Evaporator. The tank is not classified as a Watch List tank and is considered to be sound. There are no Unreviewed Safety Questions associated with Tank 241-AP-105 at this time. The waste in Tank 241-AP-105 exists as an aqueous solution of metallic salts and radionuclides, with limited amounts of organic complexants. The most prevalent soluble analytes include aluminum, potassium, sodium, hydroxide, carbonate, nitrate, and nitrite. The calculated pH is greater than the Resource Conservation and Recovery Act established limit of 12.5 for corrosivity. In addition, cadmium, chromium, and lead concentrations were found at levels greater than their regulatory thresholds. The major radionuclide constituent is 137Cs, while the few organic complexants present include glycolate and oxalate. Approximately 60% of the waste by weight is water

  9. 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

  10. 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.

  11. Characterization of Direct Push Vadose Zone Sediments from the 241-U Single-Shell Tank Farm

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-12-20

    The overall goals of the Tank Farm Vadose Zone Project, led by CH2M HILL Hanford Group, Inc., are 1) to define risks from past and future single-shell tank farm activities, 2) to identify and evaluate the efficacy of interim measures, and 3) to aid, via collection of geochemical information and data, the future decisions that must be made by the U.S. Department of Energy (DOE) regarding the near-term operations, future waste retrieval, and final closure activities for the single-shell tank Waste Management Areas (WMAs). For a more complete discussion of the goals of the Tank Farm Vadose Zone Project, see the overall work plan, Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for the Single-Shell Tank Waste Management Areas (DOE 1999). Specific details on the rationale for activities performed at WMA U are found in Crumpler (2003). To meet these goals, CH2M HILL Hanford Group, Inc., asked scientists from Pacific Northwest National Laboratory (PNNL) to perform detailed analyses of vadose zone sediment collected within the U Single-Shell Tank Farm. Specifically, this report contains all the geochemical and selected physical characterization data collected on vadose zone sediment recovered from ten direct push characterization holes emplaced to investigate vadose zone contamination associated with potential leaks within the 241-U Single-Shell Tank Farm. Specific tanks targeted during this characterization campaign included tanks 241-U-104/241-U-105, 241-U-110, and 241-U-112. Additionally, this report compiles data from direct push samples collected north of tank 241-U-201, as well as sediment collected from the background borehole (C3393). After evaluating all the characterization and analytical data, there is no question that the vadose zone in the vicinity of tanks 241-U-104 and 241-U-105 has been contaminated by tank-related waste. This observation is not new, as gamma logging of drywells in the area has identified uranium contamination at the

  12. Plutonium-241 in seawater of the Northwest European shelf seas 1989-1993

    International Nuclear Information System (INIS)

    This poster contributes to the knowledge about the levels and distribution of 241Pu in seawater in the North Sea and adjacent European shelf seas during the period 1989-1993. The controlled release of low-level radioactive waste from European nuclear fuel reprocessing plants in the UK (Sellafield, Dounreay) and France (La Hague) has led to a widespread contamination of the northeast North Atlantic and its adjoining shelf seas, Sellafield being the main contributor. Within the numerous nuclides released into the marine environment, results of 241Pu have been published rather sparsely

  13. 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}.

  14. Tank 241-BY-103 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-BY-103 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-103 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  15. Tank 241-C-112 vapor sampling and analysis tank characterization report. Revision 1

    International Nuclear Information System (INIS)

    Tank 241-C-112 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-C-112 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  16. 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

  17. 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)

  18. 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

  19. 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

  20. Tank 241-BY-112 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-BY-112 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-112 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  1. 241-SY-101 multi-functional instrument tree acceptance for beneficial use (ABU)

    International Nuclear Information System (INIS)

    This document formally demonstrates that the ABU process for the 241-SY-101 risers 17B and 17C Multi-functional Instrument Trees (MIT's) has been properly completed in accordance with the approved ABU checklists. For each item required on the ABU Checklist, a bibliography of the documentation prepared and released to satisfy the requirements is provided. Release of this documentation signifies that the tank farm Operations, Engineering, and Maintenance organizations have accepted responsibility for the MIT'S in 241-SY-101 Risers 17B and 17C

  2. 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

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

    International Nuclear Information System (INIS)

    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

  4. Tank 241-U-111 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-U-111 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-U-111 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  5. Tank 241-C-108 vapor sampling and analysis tank characterization report. Revision 1

    International Nuclear Information System (INIS)

    Tank 241-C-108 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-C-108 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  6. Tank 241-S-102 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-S-102 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-S-102 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution. close quotes

  7. Tank 241-C-104 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-C-104 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-C-104 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  8. Tank 241-BY-104 vapor sampling and analysis tank characterization report. Revision 1

    International Nuclear Information System (INIS)

    Tank 241-BY-104 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-104 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  9. Tank 241-TX-105 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-TX-105 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-TX-105 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  10. Tank 241-BY-105 vapor sampling and analysis tank characterization report. Revision 1

    International Nuclear Information System (INIS)

    Tank 241-BY-105 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-105 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  11. Tank 241-BY-111 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-BY-111 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-111 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  12. Tank 241-U-107 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-U-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-U-107 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

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

    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 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

  14. 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)

  15. Tank 241-C-108 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-C-108 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 Program Plan for the Resolution of Tank Vapor Issues (Osborne and Huckaby 1994). Tank 241-C-108 was vapor sampled in accordance with Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution (Osborne et al., 1994)

  16. 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.

  17. 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.

  18. 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

  19. 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.

  20. 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

  1. 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

  2. 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

  3. Uptake of americium-241 by plants from contaminated Chernobyl exclusive zone test site soils

    International Nuclear Information System (INIS)

    Americium-241 was found to accumulate in soils and biological objects of the environment. Its concentration has increased many times after the Chernobyl disaster and can be expected to increase about 40 times in the future. This research concentrated on the contaminated exclusive Chernobyl zone polluted by trace radionuclides, their behavior and accumulation by various plant species. Special attention is devoted to the bioavailability of 241Am to the plants Galium rivale, G. tinctorium, G. aparine, G. intermedium, Berteroa incana, Artemisia absinthium, A. vulgaris, Centaurea borysthenica, C. arenaria, Cirsium arvense, Succissa pratensis, Solidago virgaurea, Linaria vulgaris, Lepidium ruderale, Stenactis annua, Veronica maxima, Verbascum lychnitis, Euphorbia cyparissias, Genista tinctoria, Erigeron canadensis, Oenothera biennis, Betula pendula and Quercus robur, which were collected from the Chernobyl, Kopachi, and Yanov districts. The plant samples of Oenothera biennis, Betula pendula and Quercus robur were collected from the Yanov district, where the soil contamination by 241Am and 137Cs was at the level of 660 and 27 MBq/m2, respectively. Gamma spectroscopy and radiochemical methods were used to estimate the activity concentration of 137Cs, 90Sr, 238Pu, 239+240Pu, 241Am. The radionuclides were measured in the dry green mass of the plant samples and in the dry soils. The contamination of the Oenothera biennis, Betula pendula and Quercus robur samples by 137Cs was (5.8±1,5)x106, (7.4±1.1)x105, and (2.6±0.2)x106 Bq/kg dry mass, respectively, and contamination by 241Am was 47±5, 45±3 and 3.2±0.2 Bq/kg, respectively. The soil-to-plant transfer ratio for 137Cs ranged lay within the interval of 0.2 to 0.03 Bq/kg : Bq/m2, the the transfer ratio for 241Am did not exceed 7x10-5 Bq/kg : Bq/m2. The coefficient of the relative contents of the 241Am/239+240Pu radionuclides in the various plant samples varied from 3.2 to 8.3, while for soil from the Yanov district this

  4. 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

  5. Theoretical L X-ray emission probabilities in the decay of 241Am

    International Nuclear Information System (INIS)

    L X-rays emitted in the decay of 241Am are widely used for the calibration of X-ray detectors. Many measurements of the X-ray intensities in this decay have been made, however detailed balancing of the decay scheme has not yet been successful. This work attempts balancing of the decay scheme. The balance does not work with published values of fluorescence yields and Coster-Kronig transition probabilities but produces a better balance than previous studies and also shows the possibility of problems due to chemical effects with 241Am as a standard. (orig.)

  6. Tank 241-TX-118 vapor sampling and analysis tank characterization report

    International Nuclear Information System (INIS)

    Tank 241-TX-118 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-TX-118 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

  7. 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.

  8. 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

  9. Bonner sphere measurements of 241Am-B and 241Am-F neutron energy spectra unfolded using high-resolution a priori data

    International Nuclear Information System (INIS)

    High-resolution neutron energy spectra, covering the entire energy range of interest, for two standard radionuclide neutron sources (241Am-B and 241Am-F) have been derived from Bonner sphere measurements by using high-resolution a priori data in the unfolding process. In each case, two a priori spectra were used, one from a two-stage calculation and also one from a combination of the calculated spectrum with a high-resolution measured spectrum. The unfolded spectra are compared with those published elsewhere and show significant differences from the ISO- and IAEA-recommended spectra for 241Am-B and 241Am-F, respectively. Values for the fluence-average energy and fluence-to-dose-equivalent conversion coefficients are presented for the new spectra, and the implications of the new spectra for the emission rates of the sources when measured by the manganese bath technique are also determined. A combination of calculations and measurements has been performed to determine the spectral fluence from two reference neutron sources over the entire energy range of interest. For the Am-B source, this approach has supported the spectra of Marsh et al. and Zimbal and reduced confidence in the ISO 8529 spectrum. However, in terms of derived quantities, there is a good agreement between all the available spectra. In contrast, the new Am-F spectrum presented here is significantly different from those already published. The fluence to dose conversion coefficients derived from the new spectrum are 9 % lower than the currently accepted values, and the emission rates of Am-F sources measured by the manganese bath technique may need to be increased by up to 0.5 %. (authors)

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

    International Nuclear Information System (INIS)

    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

  11. 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.

  12. 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)

  13. 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)

  14. 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)

  15. 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)

  16. 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...

  17. 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.

  18. 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)

  19. Tank characterization report for single-shell tank 241-b-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-B-110. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05

  20. Exposure of workers from intakes of ''241Am in the Czech Republic

    International Nuclear Information System (INIS)

    Americium 241 has been used for many applications in the Czech republic since the end of the sixties. The original material was AmO2 powder, imported from the ten Soviet Union. Up to now, about 30 cases with ''241Am internal contamination had been identified. The intakes and commented effective doses have been calculated according to ICRP 78 biokinetic model for ''241Am of class M and AMAD 5μm, however, the agreement between intakes calculated from skeleton activities and activities in urine and faeces has not been very good. In the present paper, activities in skulls, obtained from in vivo measurements, were calculated suing efficiencies depending on the size of skull. The activity of ''241Am in skeleton and daily excreted activity of 3 voltammeters were fitted with ICRP 67 biokinetic models for classes M and S and AMAD values 1, 5, 10 and 20 μm. The best agreement in intakes calculated from individual data sets (skeleton, urine, faces) was obtained for the class M and AMAD 10 μm. (Author) 16 refs

  1. Exposure of workers from intakes of ''241Am in the Czech Republic

    Energy Technology Data Exchange (ETDEWEB)

    Malatova, I.; Beckova, V.; Vrba, T.; Pospisilova, H.

    2004-07-01

    Americium 241 has been used for many applications in the Czech republic since the end of the sixties. The original material was AmO{sub 2} powder, imported from the ten Soviet Union. Up to now, about 30 cases with ''241Am internal contamination had been identified. The intakes and commented effective doses have been calculated according to ICRP 78 biokinetic model for ''241Am of class M and AMAD 5{mu}m, however, the agreement between intakes calculated from skeleton activities and activities in urine and faeces has not been very good. In the present paper, activities in skulls, obtained from in vivo measurements, were calculated suing efficiencies depending on the size of skull. The activity of ''241Am in skeleton and daily excreted activity of 3 voltammeters were fitted with ICRP 67 biokinetic models for classes M and S and AMAD values 1, 5, 10 and 20 {mu}m. The best agreement in intakes calculated from individual data sets (skeleton, urine, faces) was obtained for the class M and AMAD 10 {mu}m. (Author) 16 refs.

  2. 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...

  3. 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)

  4. 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...

  5. 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.

  6. 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.

  7. Tank 241-AZ-101 steam bumping and settling Process Test report

    International Nuclear Information System (INIS)

    This report summarizes the process test in which the airlift circulators in Tank 241-AZ-101 were shutdown. The test was successful, in that no extreme temperature excursions occurred. Only general data was obtianed through the use of a gamma energy probe

  8. TANK 241-AN-102 MULTI-PROBE CORROSION MONITORING SYSTEM PROJECT LESSONS LEARNED

    International Nuclear Information System (INIS)

    During 2007 and 2008, a new Multi-Probe Corrosion Monitoring System (MPCMS) was designed and fabricated for use in double-shell tank 241-AN-102. The system was successfully installed in the tank on May 1, 2008. The 241-AN-102 MPCMS consists of one 'fixed' in-tank probe containing primary and secondary reference electrodes, tank material electrodes, Electrical Resistance (ER) sensors, and stressed and unstressed corrosion coupons. In addition to the fixed probe, the 241-AN-102 MPCMS also contains four standalone coupon racks, or 'removable' probes. Each rack contains stressed and unstressed coupons made of American Society of Testing and Materials A537 CL1 steel, heat-treated to closely match the chemical and mechanical characteristics of the 241-AN-102 tank wall. These coupon racks can be removed periodically to facilitate examination of the attached coupons for corrosion damage. Along the way to successful system deployment and operation, the system design, fabrication, and testing activities presented a number of challenges. This document discusses these challenges and lessons learned, which when applied to future efforts, should improve overall project efficiency

  9. Tank characterization report for double-shell tank 241-SY-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-SY-103. This report supports the requirements of the Tri-Party Agreement Milestone M-44-09

  10. Prelimainary tank characterization report for single-shell tank 241-TY-103 : Best-Basis inventory

    International Nuclear Information System (INIS)

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241'-TY-103 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  11. Preliminary tank characterization report for single-shell tank 241-A-103: best-basis inventory

    International Nuclear Information System (INIS)

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-A-103 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  12. Tank characterization report for double-shell tank 241-AW-102

    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-AW-102. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05

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

    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-BY-105. Sampling and analyses were completed to meet Safety Screening, Ferrocyanide and Historical Data Quality Objectives. This report supports the requirements of Tri-Party Agreement Milestone M-44-09

  14. Tank characterization report for single-shell tank 241-BY-105

    Energy Technology Data Exchange (ETDEWEB)

    Field, J.G., Westinghouse Hanford

    1996-08-30

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-105. Sampling and analyses were completed to meet Safety Screening, Ferrocyanide and Historical Data Quality Objectives. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

  15. Preliminary tank characterization report for single-shell tank 241-TX-102: best-basis inventory

    International Nuclear Information System (INIS)

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-TX-102 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  16. Mixer pump long term operations plan for Tank 241-SY-101 mitigation

    International Nuclear Information System (INIS)

    This document provides the general Operations Plan for performance of the mixer pump long term operations for Tank 241-SY-101 mitigation of gas retention and periodic release in Tank 101-SY. This operations plan will utilize a 112 kW (150 hp) mixing pump to agitate/suspend the particulates in the tank

  17. 45-Day safety screen results for tank 241-U-202, push mode, cores 75 and 78

    International Nuclear Information System (INIS)

    This document is a report of the analytical results for samples collected from the radioactive wastes in Tank 241-U-202 at the Hanford Reservation. Core samples were collected from the solid wastes in the tank and underwent safety screening analyses including differential scanning calorimetry, thermogravimetric analysis, and total alpha analysis. Results indicate that no safety screening notification limits were exceeded

  18. 45-Day safety screen results for tank 241-C-105, push mode, cores 72 and 76

    International Nuclear Information System (INIS)

    This document is a report of the analytical results for samples collected between March 14 and March 22, 1995 from the radioactive wastes in Tank 241-C-105 at the Hanford Reservation. Core samples were collected from the solid wastes in the tank and underwent safety screening analyses including differential scanning calorimetry, thermogravimetric analysis, and total alpha analysis

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

  20. 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)

  1. Project W-320, 241-C-106 sluicing piping calculations, Volume 7

    International Nuclear Information System (INIS)

    The object of this report is to calculate the hydraulic forces imposed at the sluicer nozzle. This is required by Project W-320 waste retrieval for tank 241-C-106. The method of analysis used is Bernoulli's momentum equation for stead flow

  2. Preliminary tank characterization report for single-shell tank 241-T-103: best-basis inventory

    International Nuclear Information System (INIS)

    An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-T-103 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task

  3. 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.

  4. Multimode approach to Am-241 and Np-237 fission induced by 660-MeV protons

    Czech Academy of Sciences Publication Activity Database

    Karapetyan, G. S.; Balabekyan, A. R.; Demekhina, N. A.; Adam, Jindřich

    2009-01-01

    Roč. 72, č. 6 (2009), s. 911-916. ISSN 1063-7788 R&D Projects: GA MŠk(CZ) LA08002 Institutional research plan: CEZ:AV0Z10480505 Keywords : FISSION * Am-241 * Np-237 Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.539, year: 2009

  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. Project W-320, 241-C-106 sluicing piping calculations, Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, J.W.

    1998-07-29

    The object of this report is to calculate the hydraulic forces imposed at the sluicer nozzle. This is required by Project W-320 waste retrieval for tank 241-C-106. The method of analysis used is Bernoulli`s momentum equation for stead flow.

  10. High resolution measurements of the Am241(n,2n) reaction cross section

    Science.gov (United States)

    Sage, C.; Semkova, V.; Bouland, O.; Dessagne, P.; Fernandez, A.; Gunsing, F.; Nästren, C.; Noguère, G.; Ottmar, H.; Plompen, A. J. M.; Romain, P.; Rudolf, G.; Somers, J.; Wastin, F.

    2010-06-01

    Measurements of the Am241(n,2n) reaction cross section have been performed at the Joint Research Centre (JRC) Geel in the frame of a collaboration between the European Commission (EC) JRC and French laboratories from CNRS and the Commissariat à L’Energie Atomique (CEA) Cadarache. Raw material coming from the Atalante facility of CEA Marcoule has been transformed by JRC Karlsruhe into suitable Am241O2 samples embedded in Al2O3 matrices specifically designed for these measurements. The irradiations were carried out at the 7-MV Van de Graaff accelerator. The Am241(n,2n) reaction cross section was determined relative to the Al27(n,α)Na24 standard cross section. The measurements were performed in four sessions, using quasi-mono-energetic neutrons with energies ranging from 8 to 21 MeV produced via the H2(d,n)He3 and the H3(d,n)He4 reactions. The induced activity was measured by standard γ-ray spectrometry using a high-purity germanium detector. Below 15 MeV, the present results are in agreement with data obtained earlier. Above 15 MeV, these measurements allowed the experimental investigation of the Am241(n,2n) reaction cross section for the first time. The present data are in good agreement with predictions obtained with the talys code that uses an optical and fission model developed at CEA.

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

    International Nuclear Information System (INIS)

    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

  12. 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.

  13. Relative radiation and hygienic significance of Am-241 and other radionuclides of Chernobyl release

    International Nuclear Information System (INIS)

    The dynamics of significance of certain nuclides of Chernobyl release has been studied on the basis of the radiation safety standards in force. In spite of accumulation of Am-241, the summary radiation impact of nuclides mixture is not increasing. The estimates of integral damage due to long-life nuclides have been presented

  14. 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.

  15. 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

  16. 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

  17. Engineering Task Plan for a vapor treatment system on Tank 241-C-103

    International Nuclear Information System (INIS)

    This Engineering Task Plan describes tasks and responsibilities for the design, fabrication, test, and installation of a vapor treatment system (mixing system) on Tank 241-C-103. The mixing system is to be installed downstream of the breather filter and will use a mixing blower to reduce the chemical concentrations to below allowable levels

  18. 39 CFR 241.4 - Expansion, relocation, and construction of post offices.

    Science.gov (United States)

    2010-07-01

    ... only in accordance with 39 U.S.C. 404(b) and 39 CFR 243.1. In the event a facility action is subject to... ESTABLISHMENT CLASSIFICATION, AND DISCONTINUANCE § 241.4 Expansion, relocation, and construction of post offices.... Emergency situations include, but are not limited to, earthquakes, floods, fire, lease terminations,...

  19. Tank characterization report for single-shell tank 241-T-107

    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-107. This tank is listed on the Ferrocyanide Watch List. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05

  20. 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

  1. 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.

  2. 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

  3. 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

  4. 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

  5. Tank characterization report for single-shell tank 241-T-107

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, L.M.

    1997-05-01

    This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-107. This tank is listed on the Ferrocyanide Watch List. This report supports the requirements of the Tri-Party Agreement Milestone M-44-05.

  6. 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)

  7. 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

  8. 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.)

  9. Tank characterization report for double-shell tank 241-AP-105

    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-AP-105. This report supports the requirements of the Tri-Party Agreement Milestone M 44-05

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

    International Nuclear Information System (INIS)

    In August 1992, Single-Shell Tank 241-T-104 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 (Ecology, 1991). 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. The purpose of this report is to describe and characterize the waste in Single-Shall Tank 241-T-104 (hereafter, Tank 241-T-104) based on information given from various sources. This report summarizes the available information regarding the waste in Tank 241-T-104, 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

  11. 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

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

    International Nuclear Information System (INIS)

    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

  13. Ventilation system consequence calculations to support salt well pumping single-shell tank 241-A-101

    International Nuclear Information System (INIS)

    This document presents the radiological dose and toxicological exposure calculations for an accident scenario involved with the ventilation system used to support salt well pumping single-shell tank 241-A-101. This tank has been listed on the Hydrogen Watch List

  14. 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).

  15. 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

  16. 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

  17. 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

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

    International Nuclear Information System (INIS)

    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

  19. 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.)

  20. 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

  1. Tank characterization report for double-shell tank 241-AP-101. Revision 1

    International Nuclear Information System (INIS)

    One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes m 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 appendixes serve as the TCR for double-shell tank 241-AP-101. The objectives of this report are to use characterization data in response to technical issues associated with tank 241-AP-101 waste; and 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 safety status and additional sampling needs. The appendixes contain supporting data and information. This report supported the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-05. The characterization information in this report originated from sample analyses and known historical sources. Appendix A provides historical information for tank 241-AP-101 including surveillance, information, records pertaining to waste transfers and tank operations, and expected tank contents derived from a model based upon process knowledge. Appendix B summarizes recent sampling events and historical sampling information. Tank 241-AP-101 was grab sampled in November 1995, when the tank contained 2,790 kL (737 kgal) of waste. An addition1034al 1,438 kL (380 kgal) of waste was received from tank 241-AW-106 in transfers on March 1996 and January 1997. This waste was the product of the 242-A Evaporator Campaign 95-1. Characterization information for the additional 1,438 kL (380 kgal) was obtained using grab sampling data from tank 241-AW-106 and a slurry sample from the evaporator. Appendix C reports on the statistical analysis and numerical manipulation of data used in

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

    International Nuclear Information System (INIS)

    This document provides the characterization information and interprets the data for Single-Shell Tank 241-C-109. Single-Shell Tank 241-C-109 is an underground storage tank containing high-level radioactive waste. It is located in the C Tank Farm in the Hanford Site's 200 East Area. The tank was sampled in September of 1992 to address the Ferrocyanide Unreviewed Safety Question. Analyses of tank waste were also performed to support Hanford Federal Facility Agreement and Consent Order Milestone M-44-08. Tank 241-C-109 went into service in 1946 and received first-cycle decontamination waste from bismuth phosphate process operations at B Plant in 1948. Other waste types added that are expected to contribute to the current contents include ferrocyanide scavenging waste and Strontium Semiworks waste. It is the last tank in a cascade with Tanks 241-C-107 and 241-C-108. The tank has a capacity of 2,010 kL (530 kgal) and currently contains 250 kL (66 kgal) of waste, existing primarily of sludge. Approximately 9.15 kL (4 kgal) of supernate remain. The sludge is heterogeneous, with significantly different chemical compositions depending on waste depth. The major waste constituents include aluminum, calcium, iron, nickel, nitrate, nitrite, phosphate, sodium, sulfate and uranium. The major radionuclides present are Cesium 137 and Strontium 90. The results of this characterization indicate that the waste in this tank is adequately described in the Dangerous Waste Permit Application of the Single-Shell Tank System

  3. 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)

  4. Tank characterization report for single-shell Tank 241-B-110

    International Nuclear Information System (INIS)

    Single-shell Tank 241-B-110 is an underground storage tank containing radioactive waste. The tank was sampled at various times between August and November of 1989 and later in April of 1990. The analytical data gathered from these sampling efforts were used to generate this Tank Characterization Report. Tank 241-B-110, located in the 200 East Area B Tank Farm, was constructed in 1943 and 1944, and went into service in 1945 by receiving second cycle decontamination waste from the B and T Plants. During the service life of the tank, other wastes were added including B Plant flush waste, B Plant fission product waste, B Plant ion exchange waste, PUREX Plant coating waste, and waste from Tank 241-B-105. The tank currently contains 246,000 gallons of non-complexed waste, existing primarily as sludge. Approximately 22,000 gallons of drainable interstitial liquid and 1,000 gallons of supernate remain. The solid phase of the waste is heterogeneous, for the top layer and subsequent layers have significantly different chemical compositions and are visually distinct. A complete analysis of the top layer has not been done, and auger sampling of the top layer is recommended to fully characterize the waste in Tank 241-B-110. The tank is not classified as a Watch List tank; however, it is a Confirmed Leaker, having lost nearly 10,000 gallons of waste. The waste in Tank 241-B-110 is primarily precipitated salts, some of which are composed of radioactive isotopes. The most prevalent analytes include water, bismuth, iron, nitrate, nitrite, phosphate, silicon, sodium, and sulfate. The major radionuclide constituents are 137Cs and 90Sr

  5. Removal of inhaled 241Am oxide particles of various sizes from beagle dogs using lung lavage and chelation treatment

    International Nuclear Information System (INIS)

    The combined treatments of lung lavage and chelation therapy were evaluated for the removal of inhaled 241AmO2 aerosols in Beagle dogs. Groups 1 to 3 were exposed to monodisperse particles of 241AmO2 of 0.75, 1.5 and 3.0 μm aerodynamic diameter (AD) respectively; a fourth group was exposed to polydisperse particles of 241AmO2 with an activity median aerodynamic diameter (AMAD) of 1.8 μm. Treatment consisted of 5 lung lavages of the right and left lungs. Treated dogs were also given 18 intravenous injections of DTPA. The dogs were sacrificed 64 days after inhalation exposure. The amount of 241Am removed from lung in the lavage fluid for Groups 1 to 4 represented 41, 46, 42 and 33 % of the initial lung burden, respectively. The amount of 241Am excreted in the urine from the treated dogs in excess of that excreted by the untreated dogs for Groups 1 to 4 was 20, 19, 8 and 26 %, respectively. More 241Am was excreted in the urine from dogs that inhaled smaller particle sized aerosols. As a result of the removal of 241Am activity, the 64-day cumulative absorbed radiation doses to lung, liver and skeleton were reduced by 50, 90 and 85 %, respectively. (author)

  6. Effects of naturally occurring aquatic organic fractions on 241Am uptake by Scenedesmus obliquus (Chlorophyceae) and Aeromonas hydrophila (Pseudomonadaceae)

    International Nuclear Information System (INIS)

    Naturally occurring organics were extracted from water collected from Skinface Pond near Aiken, S.C. Organics were separated into four nominal diameter size fractions (I, greater than 0.0183; II, 0.0183 to 0.0032; III, 0.0032 to 0.0009; IV, less than 0.0009 μm) by membrane ultrafiltration and introduced into Scenedesmus obliquus and Aeromonas hydrophila cultures to determine their effects on 241Am availability for uptake. Effects on 241Am uptake were determined in actively growing S. obliquus cultures after 96 h of growth and in dense cultures of nongrowing cells after 4 h. Uptake by A. hydrophila was determined after 4 and 24 h in actively growing cultures. All organic fractions stimulated S. obliquus growth, with the most pronounced effects due to larger organic fractions, whereas no apparent growth stimulation of A. hydrophila was observed for any organic fraction. For both long-term and short-term studies, cellular 241Am concentration (picocuries/cell) increased with increasing 241Am concentration for S. obliquus and A. hydrophila. Fraction IV increased 241Am uptake by both S. obliquus and A. hydrophila during 4-h incubations. During 96-h incubations fraction I was flocculated and cosedimented, with S. obliquus and A. hydrophila cells causing an apparent increase in 241Am uptake. Fractions II and III reduced apparent 241Am uptake by S. obliquus as a result of biological dilution caused by increased algal growth due to the organics. Fraction IV caused a reduction in 241Am uptake by S. obliquus not attributable to biological dilution. Organics increased 241Am uptake by A. hydrophila during 4- and 24-h incubations. A. hydrophila also caused flocculation of fraction I during 96-h incubations

  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. Vapor and gas sampling of single-shell tank 241-B-102 using the in situ vapor sampling system

    International Nuclear Information System (INIS)

    The Vapor Issue Resolution Program tasked the Vapor Team (the team) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-B-102. This document presents sampling data resulting from the April 18, 1996 sampling of SST 241-B-102. Analytical results will be presented in a separate report issued by Pacific Northwest National Laboratory (PNNL), which supplied and analyzed the sampling media. The team, consisting of Sampling and Mobile Laboratories (SML) and Special Analytical Studies (SAS) personnel, used the vapor sampling system (VSS) to collect representative samples of the air, gases, and vapors from the headspace of SST 241-B-102 with sorbent traps and SUMMA canisters

  9. Vapor and gas sampling of single-shell tank 241-C-107 using the in situ vapor sampling system

    International Nuclear Information System (INIS)

    The Vapor Issue Resolution Program tasked the Vapor Team (the team) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-C-107. This document presents sampling data resulting from the February 7, 1997 sampling of SST 241-C-107. Analytical results will be presented in separate reports issued by the Pacific Northwest National Laboratory which supplied and analyzed the sample media. This is the last in a series of temporal sampling events on SST 241-C-107. The strategy of temporal sampling is to measure the compositional changes of the waste tank headspace as related to seasonal effects and gradual changes of waste chemistry

  10. Vapor and gas sampling of single-shell tank 241-S-102 using the in situ vapor sampling system

    International Nuclear Information System (INIS)

    The Vapor Issue Resolution Program tasked the Vapor Team (the team) to collect representative headspace samples from Hanford Site single-shell tank (SST) 241-S-102. This document presents sampling data resulting from the February 11, 1997 sampling of SST 241-S-102. Analytical results will be presented in separate reports issued by the Pacific Northwest National Laboratory which supplied and analyzed the sample media. This is the last in a series of temporal sapling events on SST 241-S-102. The strategy of temporal sampling is to measure the compositional changes of the waste tank headspace as related to seasonal effects and gradual changes of waste chemistry

  11. 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)

  12. 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. The purpose of this sampling event is to obtain information about the characteristics of the contents of 241-AZ-102 required to satisfy the Data Quality Objectives For TWRS Privatization Phase I : Confirm Tank TIS An Appropriate Feed Source For High-Level Waste Feed Batch X(HLW DQO) (Nguyen 1999a), Data Quality Objectives For TWRS Privatization Phase 1: Confirm Tank TIS An Appropriate Feed Source For Low-Activity Waste Feed Batch X (LAW DQO) (Nguyen 1999b), Low Activity Waste and High Level Waste Feed Data Quality Objectives (L and H DQO) (Patello et al. 1999) and Characterization Data Needs for Development, Design, and Operation of Retrieval Equipment Developed through the Data Quality Objective Process (Equipment DQO) (Bloom 1996). The Tank Characterization Technical Sampling Basis document (Brown et al. 1998) indicates that these issues, except the Equipment DQO apply to tank 241-AZ-102 for this sampling event. The Equipment DQO is applied for shear strength measurements of the solids segments only. Poppiti (1999) requires additional americium-241 analyses of the sludge segments. Brown et al. (1998) also identify safety screening, regulatory issues and provision of samples to the Privatization Contractor(s) as applicable issues for this tank. However, these issues will not be addressed via this sampling event. Reynolds et al. (1999) concluded that information from previous sampling events was sufficient to satisfy the safety screening requirements for tank 241-AZ-102. Push mode core samples will be obtained from risers 15C and 24A to provide sufficient material for the chemical analyses and tests required to satisfy these data quality objectives. The 222-S Laboratory will extrude core samples, composite the liquids and solids, perform chemical analyses

  13. An assessment of the dilution required to mitigate Hanford tank 241-SY-101

    International Nuclear Information System (INIS)

    A group of experts from PNL and WHC convened November 2 and 3, 1994, to screen the current state of knowledge about dilution and reach a consensus on the minimum dilution ratio that will achieve passive mitigation of Tank 241-SY-101 wastes and the dilution ratio that would satisfy the given cross-site transfer criteria with reasonable assurance. The panel evaluated the effects of dilution on the parameters important in gas generation, retention, and release and reached the following conclusions, which are deduced from the existing body of data, experience, and analyses: (1) Dissolution of solids is the single most important aspect of mitigation by dilution. We are confident that diluting until nitrates, nitrites, and aluminum salts are dissolved will mitigate Hanford flammable gas tanks; (2) Sufficient solids dissolution can be achieved in Tank 241-SY-101 at a dilution ratio of 1:1, which will result in a average specific gravity of approximately 1.35. It is likely that a 0.5:1 dilution will also mitigate 241-SY-101, but the current uncertainty is too high to recommend this dilution ratio; (3) The recommended dilution requires a diluent with at least 2 molar free hydroxide, because aluminum probably precipitates at lower hydroxide concentrations. The transfer criteria for Tank 241-SY-101 waste were also evaluated. These criteria have been specified as solids content ≤30% (volume), viscosity ≤30% cP and density <1.5 g/mL. (1) Solids content is the limiting criterion if it is defined as volume fraction of settled solids. A 1:1 dilution will satisfy this criterion at nominal premixing conditions in Tank 241-SY-101; however, analysis of Window E core samples suggests that up to 1.5:1 might be required. If the solids content is interpreted simply as solids volume fraction no further dilution is necessary, because Tank 241-SY-101 waste (excluding the crust) is already below 30%; (2) Bulk density is the next limiting criterion and is met at 0.4:1 dilution

  14. IARC Press Release N°241 / Comunicato stampa N°241 della IARC "GIORNATA INTERNAZIONALE CONTRO I TUMORI INFANTILI: RIMANE MOLTO DA FARE PER COMBATTERE I TUMORI INFANTILI" pubblicato il 15 Febbraio 2016

    OpenAIRE

    Fellone, Lucio

    2016-01-01

    Versione autorizzata in italiano del Comunicato Stampa della IARC N°241 pubblicato il 15 febbraio 2016: "GIORNATA INTERNAZIONALE CONTRO I TUMORI INFANTILI: RIMANE MOLTO DA FARE PER COMBATTERE I TUMORI INFANTILI". Documento originale all'indirizzo: http://www.iarc.fr/en/media-centre/pr/2016/pdfs/pr241_E.pdf. Authorized Italian version of the IARC Press Release N°238 published on 15 February 2016: International Childhood Cancer Day: Much remains to be done to...

  15. Calculation note: project W-320 primary ventilation air flow requirements for mitigation of steady state flammable gas concentrations in the headspaces of tanks 241-C-106 and 241-AY-102

    International Nuclear Information System (INIS)

    This calculation note analyzes headspace concentrations of hydrogen dependent upon assumed ventilation flow rates provided for tanks 241-C-106 and 241-AY-102. The analyses are based on measured or estimated steady state hydrogen release rates. Tank 241-C-106 is analyzed prior to sluicing; tank 241-AY-102 is analyzed both prior to and after completion of sluicing. Specific analyses, using both best estimated and bounding hydrogen generation rates, include the minimum primary ventilation flow rates required in the tanks to ensure that the steady state hydrogen concentration in the respective tank headspace does not exceed 25% and 100% of the LFL. The headspace hydrogen concentration as a function of time as well as the time required to reach 25% and 100% of LFL upon complete loss of active ventilation, starting from the steady state hydrogen concentration based on a 200 CFM minimum flow rate in tank 241-C-106 and a 100 CFM minimum flow rate in tank241-AY-102. The headspace hydrogen concentration as a function of thee following partial loss of active ventilation (i.e., step changes to l60, l20, 80, and 40 CFM ventilation flow rates) in tank 241-C-106, staffing from a 200 CFM flow rate and the corresponding steady state hydrogen concentration based on the 200 CFM flow rate. The headspace hydrogen concentration as a function of the following partial loss of active ventilation i.e., step changes to 80, 60, 40, and 20 CFM ventilation flow rates) in tank 241-AY-102, starting from a 100 CFM flow rate and the corresponding steady state hydrogen concentration based on the 100 CFM flow rate

  16. 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.

  17. 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)

  18. Geographic and vertical distribution of global fallout americium 241, plutonium isotopes and cesium 137 in lake sediments

    International Nuclear Information System (INIS)

    In this study, we present results concerning the activity concentrations of 241Am, 239-240Pu, 238Pu and 137Cs in lake sediments. Bulk cores for radionuclide inventories and high resolution cores for depth distribution are analysed

  19. The Potential for Buoyant Displacement Gas Release Events in Tank 241-SY-102 after Waste Transfer from Tank 241-SY-101

    Energy Technology Data Exchange (ETDEWEB)

    Wells, Beric E.; Meyer, Perry A.; Chen, Guang

    2000-04-10

    Tank 241-SY-101 is a double-shell radioactive waste storage tank containing waste that, before recent transfer and water back-dilution operations, was capable of retaining gas and producing flammable buoyant displacement gas release events (BD GREs). A BD GRE occurs when a portion of the nonconvective layer waste retains enough gas to become buoyant, rises to the waste surface, breaks up, and releases some of the stored gas. Installing the mixer pump in 1993 successfully mitigated gas retention in the settled solids layer in SY-101 and has prevented BD GREs. Gas retention in the floating drust layer and the corresponding accelerated waste level growth made it necessary to begin waste removal and back-dilution with water in December 1999. During these operations, some of the SY-101 mixed slurry layer is removed and transferred into Tank 241-SY-102. There was some concern that adding the SY-101 waste into SY-102 could create a waste configuration in SY-102 capable of BD GREs. This report updates and extends earlier assessments of the potential for BD GRE conditions in SY-102 after waste is transferred from SY-101. We determined that, under the given assumptions, no possibility of BD GREs exists in SY-102 from the SY-101 waste being added during from December 1999 through March 2000.

  20. Tank 241-AN-104, cores 163 and 164 analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the analytical laboratory report for tank 241-AN-104 push mode core segments collected between August 8, 1996 and September 12, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-AAr-1 04 Push Mode Core Sampling and Analysis Plan (TSAP) (Winkelman, 1996), the Safety Screening Data Quality Objective (DQO) (Dukelow, et at., 1995) and the Flammable Gas Data Quality Objective (DQO) (Benar, 1995). The analytical results are included in a data summary table. None of the samples submitted for Differential Scanning Calorimetry (DSC), Total Alpha Activity (AT), Total Organic Carbon (TOC) and Plutonium analyses (239,240 Pu) 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 not considered in this report

  1. 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

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

    International Nuclear Information System (INIS)

    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

  3. Tank 241-T-105, cores 205 and 207 analytical results for the final report

    International Nuclear Information System (INIS)

    This document is the final laboratory report for tank 241-T-105 push mode core segments collected between June 24, 1997 and June 30, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (TSAP) (Field,1997), the Tank Safety Screening Data Quality Objective (Safety DQO) (Dukelow, et al., 1995) and Tank 241-T-105 Sample Analysis (memo) (Field, 1997a). The analytical results are included in Table 1. None of the subsamples submitted for the differential scanning calorimetry (DSC) analysis or total alpha activity (AT) exceeded the notification limits as stated in the TSAP (Field, 1997). 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, 1997) and not considered in this report

  4. 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

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

    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 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

  6. Standardization of 241Am by digital coincidence counting, liquid scintillation counting and defined solid angle counting

    CERN Document Server

    Balpardo, C; Rodrigues, D; Arenillas, P

    2010-01-01

    The nuclide 241Am decays by alpha emission to 237Np. Most of the decays (84.6 %) populate the excited level of 237Np with energy of 59.54 keV. Digital Coincidence Counting was applied to standardize a solution of 241Am by alpha-gamma coincidence counting with efficiency extrapolation. Electronic discrimination was implemented with a pressurized proportional counter and the results were compared with two other independent techniques: Liquid Scintillation Counting using the logical sum of double coincidences in a TDCR array and Defined Solid Angle Counting taking into account activity inhomogeneity in the active deposit. The results show consistency between the three methods within a limit of a 0.3%. An ampoule of this solution will be sent to the International Reference System (SIR) during 2009. Uncertainties were analysed and compared in detail for the three applied methods.

  7. 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.

  8. 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.

  9. Am-241 remobilization in a calcareous soil under simplified rhizospheric conditions studied by column experiments

    International Nuclear Information System (INIS)

    The effects of simplified rhizospheric conditions on the leaching of 241Am from a calcareous soil, freshly contaminated, were investigated in batch and column experiments. Glucose and/or citrate were used as artificial exudate solutions at concentrations ranging from 10-4 to 10-2 mol dm-3. Am desorption, expressed in terms of distribution coefficients, varied from Kd > 104 dm3 kg-1 corresponding to a majority of experimental conditions, to Kd ≤ 102 dm3 kg-1 when citrate combined or not with glucose was used at ≥10-2 mol dm-3. Soil columns revealed successive steady states coupled with transitory episodes, the latter represented up to 90% of the total Am release. 241Am fractions with different behaviours were thus highlighted in columns whereas batch only accounted for highest Am mobile fractions. The implications of the different processes are discussed in terms of modelling approach and risk assessment

  10. 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

  11. 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.

  12. 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

  13. 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

  14. Mechanism of vertical migration of Am 241 in peaty-gley soil

    International Nuclear Information System (INIS)

    Nowadays soil in the Chernobyl zone has become a source from which radionuclides can come to other objects of biosphere. The vertical migration determines distribution of the radionuclides in the soil. For research of vertical migration of Am 241 in soil the distribution of the radionuclide in granulometric fractions of the soil particles was measured, humus was extracted from the soil with the help of a sodium pyrophosphate solution by the accelerated method of Kononova and Beltchikova. For an estimation of a share of a mobile form of radionuclide the soil was dissolved in ammonium acetate solution. The conclusion is made, that nowadays significant part of Am 241 is strongly fixed on a mineral matrix of the soil and migrates together with the soil particles

  15. 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.

  16. Determination of worst case projected source term in tank 241-SY-102; TOPICAL

    International Nuclear Information System (INIS)

    This document describes the methodology used to determine the worst case projected source term that could be in double-shell tank 241-SY-102 for the upcoming cross-site waste transfer. The worst case projected source term is given in Table 4-1 is the weighted average of the tank waste sources with the addition of sufficient waste from a defined worst source tank to fill the tank to 416 inches. The projected source term in this document is not intended to represent what will be in tank 241-SY-102. Rather, it is a conservative bounding composition considering that the volume of waste that will be added from each current source is unknown

  17. 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.

  18. The Integration of the 241-Z Building Decontamination and Decommissioning Under Cercla with RCRA Closure at the Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    The 241-Z treatment and storage tanks, a hazardous waste Treatment, Storage and Disposal (TSD) unit permitted pursuant to the Resource Conservation and Recovery Act of 1976 (RCRA) and Washington State Hazardous Waste Management Act, RCW 70.105, , have been deactivated and are being actively decommissioned under the provisions of the Hanford Federal Facility Agreement and Consent Order (HFFACO), RCRA and Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) 42 U.S.C. 9601 et seq. The 241-Z TSD unit managed non-listed radioactive contaminated waste water, containing trace RCRA characteristic constituents. The 241-Z TSD unit consists of below grade tanks (D-4, D-5, D-7, D-8, and an overflow tank) located in a concrete containment vault, sample glovebox GB-2-241-ZA, and associated ancillary piping and equipment. The tank system is located beneath the 241-Z building. The 241-Z building is not a portion of the TSD unit. The sample glovebox is housed in the above-grade building. Waste managed at the TSD unit was received via underground piping from Plutonium Finishing Plant (PFP) sources. Tank D-6, located in the D-6 vault cell, is a past-practice tank that was taken out of service in 1972 and has never operated as a portion of the RCRA TSD unit. CERCLA actions will address Tank D-6, its containment vault cell, and soil beneath the cell that was potentially contaminated during past-practice operations and any other potential past-practice contamination identified during 241-Z closure, while outside the scope of the Hanford Facility Dangerous Waste Closure Plan, 241-Z Treatment and Storage Tanks. Under the RCRA closure plan, the 241-Z TSD unit is anticipated to undergo clean closure to the performance standards of the State of Washington with respect to dangerous waste contamination from RCRA operations. The TSD unit will be clean closed if physical closure activities identified in the plan achieve clean closure standards for all 241-Z

  19. 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.

  20. 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.