Temperature feedback of TRIGA MARK-II fuel

Science.gov (United States)

Usang, M. D.; Minhat, M. S.; Rabir, M. H.; M. Rawi M., Z.

2016-01-01

We study the amount of temperature feedback on reactivity for the three types of TRIGA fuel i.. ST8, ST12 and LEU fuel, are used in the TRIGA MARK II reactor in Malaysia Nuclear Agency. We employ WIMSD-5B for the calculation of kin f for a single TRIGA fuel surrounded by water. Typical calculations of TRIGA fuel reactivity are usually limited to ST8 fuel, but in this paper our investigation extends to ST12 and LEU fuel. We look at the kin f of our model at various fuel temperatures and calculate the amount reactivity removed. In one instance, the water temperature is kept at room temperature of 300K to simulate sudden reactivity increase from startup. In another instance, we simulate the sudden temperature increase during normal operation where the water temperature is approximately 320K while observing the kin f at various fuel temperatures. For accidents, two cases are simulated. The first case is for water temperature at 370K and the other is without any water. We observe that the higher Uranium content fuel such as the ST12 and LEU have much smaller contribution to the reactivity in comparison to the often studied ST8 fuel. In fact the negative reactivity coefficient for LEU fuel at high temperature in water is only slightly larger to the negative reactivity coefficient for ST8 fuel in void. The performance of ST8 fuel in terms of negative reactivity coefficient is cut almost by half when it is in void. These results are essential in the safety evaluation of the reactor and should be carefully considered when choices of fuel for core reconfiguration are made.

Production and use of {sup 18}F by TRIGA nuclear reactor: a first report

Energy Technology Data Exchange (ETDEWEB)

Burgio, N.; Ciavola, C.; Festinesi, A.; Capannesi, G. [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Innovazione

1999-02-01

The irradiation and radiochemical facilities at public research centre can contribute to the start up of the regional PET centre. In particular, the TRIGA reactor of Casaccia Research Centre could produce a sufficient amount of {sup 18}F to start up a PET centre and successively integrated the cyclotron production. This report establishes, in the light of the preliminary experimental works, a guideline to the reactor`s production and extraction of {sup 18}F in a convenient form for the synthesis of the most representative PET radiopharmaceutical: {sup 18}F-FDG. [Italiano] Le facilities di irraggiamento e i laboratori Radiochimici dei Centri Statali di Ricerca possono contribuire allo sviluppo di centri regionali PET (Tomografia ed Emissione Positronica). In particolare, il reattore TRIGA del Centro Ricerca Casaccia potrebbe produrre un quantitativo di {sup 18}F sufficiente alle attivita` formative propedeutiche al centro PET che, successivamente sarebbe in grado di avviare una propria produzione da ciclotrone. Questo rapporto stabilisce le linee guida sperimentali per la produzione del {sup 18}F da reattore nucleare e la sua successiva estrazione in una forma conveniente per la sintesi del piu` rappresentativo dei radiofarmaci PET: il {sup 18}F-FDG.

ORIGEN2 calculations supporting TRIGA irradiated fuel data package

Energy Technology Data Exchange (ETDEWEB)

Schmittroth, F.A.

1996-09-20

ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiography Facility. The calculations support storage and disposal and results include mass, activity,and decay heat. Comparisons with underwater dose-rate measurements were used to confirm and adjust the calculations.

76 FR 72391 - Defense Logistics Agency Revised Regulation 1000.22, Environmental Considerations in Defense...

Science.gov (United States)

2011-11-23

... DEPARTMENT OF DEFENSE Office of the Secretary [Docket ID DOD-2011-OS-0055] Defense Logistics Agency Revised Regulation 1000.22, Environmental Considerations in Defense Logistics Agency Actions AGENCY: Defense Logistics Agency, Department of Defense. ACTION: Revised Defense Logistics Agency...

Research work with TRIGA Mark II at the Nuclear Chemistry Section of the 'J. Stefan' Institute in Ljubljana

International Nuclear Information System (INIS)

Byrne, A.R.; Dermelj, M.; Kosta, L.; Ravkin, V.; Stegnar, P.

1978-01-01

The general features of our research programme using TRIGA MK II, as outlined at the last TRIGA Reactor Users Conference in Vienna, September 28-30,1976, remain the same; namely, neutron activation analysis for trace and some minor elements. The four main areas presently investigated are a) environmental studies, b) life sciences research, c) standardization and d) methodology for specific problems arising in the first three topics

History, Development and Future of TRIGA Research Reactors

International Nuclear Information System (INIS)

2016-01-01

Due to its particular fuel design and resulting enhanced inherent safety features, TRIGA reactors (Training, Research, Isotopes, General Atomics) constitute a ‘class of their own’ among the large variety of research reactors built world-wide. This publication summarizes in a single document the information on the past and present of TRIGA research reactors and presents an outlook in view of potential issues to be solved by TRIGA operating organizations in the near future. It covers the historical development and basic TRIGA characteristics, followed by utilization, fuel conversion and ageing management of TRIGA research reactors. It continues with issues and challenges, introduction to the global TRIGA research reactor network and concludes with future perspectives. The publication is complemented with a CD-ROM to illustrate the historical developments of TRIGA research reactors through individual facility examples and experiences

76 FR 28757 - Defense Logistics Agency Revised Regulation 1000.22, Environmental Considerations in Defense...

Science.gov (United States)

2011-05-18

... DEPARTMENT OF DEFENSE Office of the Secretary [DOCKET ID DOD-2011-OS-0055] Defense Logistics Agency Revised Regulation 1000.22, Environmental Considerations in Defense Logistics Agency Actions AGENCY: Defense Logistics Agency, Department of Defense. ACTION: Notice of Availability (NOA) of Revised...

76 FR 53119 - Defense Logistics Agency Revised Regulation 1000.22, Environmental Considerations in Defense...

Science.gov (United States)

2011-08-25

... DEPARTMENT OF DEFENSE Office of the Secretary [Docket ID: DOD-2011-OS-0055] Defense Logistics Agency Revised Regulation 1000.22, Environmental Considerations in Defense Logistics Agency Actions AGENCY: Defense Logistics Agency, Department of Defense. ACTION: Comment Addressed on Notice of...

NMDA receptor channels: labeling of MK-801 with iodine-125 and fluorine-18

International Nuclear Information System (INIS)

Wieland, D.M.; Kilbourn, M.R.; Yang, D.J.; Laborde, E.; Gildersleeve, D.L.; Van Dort, M.E.; Pirat, J.-L.; Ciliax, B.J.; Young, A.B.

1988-01-01

Methods for labeling the glutamate channel blocking agent MK-801 with iodine-125 ( 125 I) and fluorine-18 ( 18 F) are described. Radioiodine was incorporated in the 1- or 3-positions of the aromatic ring of (±)MK-801 by solid-state halogen exchange techniques. Attachment of the [ 18 F]fluoromethyl group to the bridgehead methyl position was achieved by reaction of [ 18 F]fluoride with the triflamide alcohol or the novel cyclic sulfamate recently reported by Merck chemists. Radiochemical yields of (±)13-[ 18 F]-fluoromethyl-MK-801 were >72%, EOB; radiochemical purity > 99%. In competitive binding studies using rat brain homogenates, (±)3-bromo-MK-801 showed greater affinity than (±)MK-801 for the glutamate-linked channel. The experimental log P (2.1 ± 0.1) of MK-801 is optimal for transit of the blood-brain barrier. These preliminary findings support further testing of [ 123 I]iodo-MK-801 and [ 18 F]fluoromethyl-MK-801 as possible agents for in vivo mapping of the glutamate receptor complex. (author)

Capsicum annuum transcription factor WRKYa positively regulates defense response upon TMV infection and is a substrate of CaMK1 and CaMK2.

Science.gov (United States)

Huh, Sung Un; Lee, Gil-Je; Jung, Ji Hoon; Kim, Yunsik; Kim, Young Jin; Paek, Kyung-Hee

2015-01-23

Plants are constantly exposed to pathogens and environmental stresses. To minimize damage caused by these potentially harmful factors, plants respond by massive transcriptional reprogramming of various stress-related genes via major transcription factor families. One of the transcription factor families, WRKY, plays an important role in diverse stress response of plants and is often useful to generate genetically engineered crop plants. In this study, we carried out functional characterization of CaWRKYa encoding group I WRKY member, which is induced during hypersensitive response (HR) in hot pepper (Capsicum annuum) upon Tobacco mosaic virus (TMV) infection. CaWRKYa was involved in L-mediated resistance via transcriptional reprogramming of pathogenesis-related (PR) gene expression and affected HR upon TMV-P0 infection. CaWRKYa acts as a positive regulator of this defense system and could bind to the W-box of diverse PR genes promoters. Furthermore, we found Capsicum annuum mitogen-activated protein kinase 1 (CaMK1) and 2 (CaMK2) interacted with CaWRKYa and phosphorylated the SP clusters but not the MAPK docking (D)-domain of CaWRKYa. Thus, these results demonstrated that CaWRKYa was regulated by CaMK1 and CaMK2 at the posttranslational level in hot pepper.

76 FR 22681 - Defense Logistics Agency (DLA) Address Directory

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2011-04-22

... DEPARTMENT OF DEFENSE Office of the Secretary Defense Logistics Agency (DLA) Address Directory AGENCY: Department of Defense. ACTION: Notice. SUMMARY: The Defense Logistics Agency (DLA) is updating... Directory: Defense Logistics Agency Headquarters, Andrew T. McNamara Building, 8725 John J. Kingman Road...

75 FR 76423 - Defense Intelligence Agency National Defense Intelligence College Board of Visitors Closed Meeting

Science.gov (United States)

2010-12-08

... DEPARTMENT OF DEFENSE Office of the Secretary Defense Intelligence Agency National Defense Intelligence College Board of Visitors Closed Meeting AGENCY: National Defense Intelligence College, Defense Intelligence Agency, Department of Defense. ACTION: Notice of Closed Meeting. SUMMARY: Pursuant to the...

76 FR 28960 - Defense Intelligence Agency National Defense Intelligence College Board of Visitors Closed Meeting

Science.gov (United States)

2011-05-19

... DEPARTMENT OF DEFENSE Office of the Secretary Defense Intelligence Agency National Defense Intelligence College Board of Visitors Closed Meeting AGENCY: National Defense Intelligence College, Defense Intelligence Agency, Department of Defense. ACTION: Notice of Closed Meeting. SUMMARY: Pursuant to the...

History, Development and Future of TRIGA Research Reactors. Companion CD-ROM

International Nuclear Information System (INIS)

2016-01-01

Due to its particular fuel design and resulting enhanced inherent safety features, TRIGA reactors (Training, Research, Isotopes, General Atomics) constitute a ‘class of their own’ among the large variety of research reactors built world-wide. This publication summarizes in a single document the information on the past and present of TRIGA research reactors and presents an outlook in view of potential issues to be solved by TRIGA operating organizations in the near future. It covers the historical development and basic TRIGA characteristics, followed by utilization, fuel conversion and ageing management of TRIGA research reactors. It continues with issues and challenges, introduction to the global TRIGA research reactor network and concludes with future perspectives. This CD-ROM illustrates the historical developments of TRIGA research reactors through individual facility examples and experiences

Neutronic calculations in core conversion of the IAN-R1 research reactor from MTR HEU to TRIGA LEU fuel

International Nuclear Information System (INIS)

Sarta Fuentes, Jose A.; Castiblanco, L.A.

2003-01-01

With cooperation of the International Atomic Energy Agency (IAEA), neutronic calculations were carried out for conversion of the Ian-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. In order to establish a staff for neutronic calculation at the Instituto de Cancan's Nucleares y Energia s Alternatives (INEA) a program was established. This program included training, acquisition of hardware, software and calculation for the core with MTR-HEU fuel , enriched nominally to 93% and calculation for several arrangements with the TRIGA-LEU fuel, enriched to 19.7%. The results were verified and compared with several groups of calculation at the Instituto Nacional de Investigaciones Nucleares (ININ) in Mexico, and General Atomics (GA) in United States. As a result of this program, several technical reports have been wrote. (author)

Defense Logistics Agency Revenue Eliminations

National Research Council Canada - National Science Library

1996-01-01

The issue of revenue eliminations was identified during our work on the Defense Logistics Agency portion of the Audit of Revenue Accounts in the FY 1996 Financial Statements of the Defense Business Operations Fund...

Modeling the PUSPATI TRIGA Reactor using MCNP code

International Nuclear Information System (INIS)

Mohamad Hairie Rabir; Mark Dennis Usang; Naim Syauqi Hamzah; Julia Abdul Karim; Mohd Amin Sharifuldin Salleh

2012-01-01

The 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency achieved initial criticality on June 28, 1982. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes. This paper describes the reactor parameters calculation for the PUSPATI TRIGA REACTOR (RTP); focusing on the application of the developed reactor 3D model for criticality calculation, analysis of power and neutron flux distribution and depletion study of TRIGA fuel. The 3D continuous energy Monte Carlo code MCNP was used to develop a versatile and accurate full model of the TRIGA reactor. The model represents in detailed all important components of the core and shielding with literally no physical approximation. (author)

75 FR 9588 - Defense Intelligence Agency Advisory Board; Closed Meeting

Science.gov (United States)

2010-03-03

... DEPARTMENT OF DEFENSE Office of the Secretary Defense Intelligence Agency Advisory Board; Closed Meeting AGENCY: Defense Intelligence Agency, DoD. ACTION: Notice of closed meeting. SUMMARY: Pursuant to... Law 94-409, notice is hereby given that the Defense Intelligence Agency Advisory Board, will meet on...

The Core Conversion of the TRIGA Reactor Vienna

International Nuclear Information System (INIS)

Villa, M.; Bergmann, R.; Musilek, A.; Sterba, J.H.; Böck, H.; Messick, C.

2016-01-01

The TRIGA Reactor Vienna has operated for many years with a mixed core using Al-clad and stainless-steel (SST) clad low enriched uranium (LEU) fuel and a few SST high enriched uranium (HEU) fuel elements. In view of the US spent fuel return program, the average age of these fuel elements and the Austrian position not to store any spent nuclear fuel on its territory, negotiation started in April 2011 with the US Department of Energy (DOE) and the International Atomic Energy Agency (IAEA). The sensitive subject was to return the old TRIGA fuel and to find a solution for a possible continuation of reactor operation for the next decades. As the TRIGA Vienna is the closest nuclear facility to the IAEA headquarters, high interest existed at the IAEA to have an operating research reactor nearby, as historically close cooperation exists between the IAEA and the Atominstitut. Negotiation started before summer 2011 between the involved Austrian ministries, the IAEA and the US DOE leading to the following solution: Austria will return 91 spent fuel elements to the Idaho National Laboratory (INL) while INL offers 77 very low burnt SST clad LEU elements for further reactor operation of the TRIGA reactor Vienna. The titles of these 77 new fuel elements will be transferred to Euratom in accordance with Article 86 of the Euratom-US Treaty. The fuel exchange with the old core returned to the INL, and the new core transferred to Vienna was carried out in one shipment in late 2012 through the ports of Koper/Slovenia and Trieste/Italy. This paper describes the administrative, logistic and technical preparations of the fuel exchange being unique world-wide and first of its kind between Austria and the USA performed successfully in early November 2012. (author)

77 FR 62469 - Defense Logistics Agency Freedom of Information Act Program

Science.gov (United States)

2012-10-15

... DEPARTMENT OF DEFENSE Office of the Secretary 32 CFR Part 300 Defense Logistics Agency 32 CFR Part 1285 RIN 0790-AI87 [Docket ID: DOD-2012-OS-0019] Defense Logistics Agency Freedom of Information Act Program AGENCY: Defense Logistics Agency, DoD. ACTION: Proposed rule. SUMMARY: The Defense Logistics...

Kinetic analysis of the cannabinoid-1 receptor PET tracer [18F]MK-9470 in human brain

International Nuclear Information System (INIS)

Sanabria-Bohorquez, Sandra Marina; Hamill, Terence G.; Burns, H.D.; Goffin, Karolien; Laere, Koen van; Lepeleire, Inge de; Bormans, Guy

2010-01-01

Quantitative imaging of the type 1 cannabinoid receptor (CB1R) opens perspectives for many neurological and psychiatric disorders. We characterized the kinetics and reproducibility of the CB1R tracer [ 18 F]MK-9470 in human brain. [ 18 F]MK-9470 data were analysed using reversible models and the distribution volume V T and V ND k 3 (V ND k 3 = K 1 k 2 ) were estimated. Tracer binding was also evaluated using irreversible kinetics and the irreversible uptake constant K i and fractional uptake rate (FUR) were estimated. The effect of blood flow on these parameters was evaluated. Additionally, the possibility of determining the tracer plasma kinetics using a reduced number of blood samples was also examined. A reversible two-tissue compartment model using a global k 4 value was necessary to describe brain kinetics. Both V T and V ND k 3 were estimated satisfactorily and their test-retest variability was between 10% and 30%. Irreversible methods adequately described brain kinetics and FUR values were equivalent to K i . The linear relationship between K i and V ND k 3 demonstrated that K i or FUR and thus the simple measure of tracer brain uptake provide CB1R availability information. The test-retest variability of K i and FUR was 18 F]MK-9470 specific binding can be accurately determined using FUR values requiring a short scan 90 to 120 min after tracer administration. Our results suggest that [ 18 F]MK-9470 plasma kinetics can be assessed using a few venous samples. (orig.)

Preclinical evaluation and quantification of [18F]MK-9470 as a radioligand for PET imaging of the type 1 cannabinoid receptor in rat brain

International Nuclear Information System (INIS)

Casteels, Cindy; Koole, Michel; Laere, Koen van; Celen, Sofie; Bormans, Guy

2012-01-01

[ 18 F]MK-9470 is an inverse agonist for the type 1 cannabinoid (CB1) receptor allowing its use in PET imaging. We characterized the kinetics of [ 18 F]MK-9470 and evaluated its ability to quantify CB1 receptor availability in the rat brain. Dynamic small-animal PET scans with [ 18 F]MK-9470 were performed in Wistar rats on a FOCUS-220 system for up to 10 h. Both plasma and perfused brain homogenates were analysed using HPLC to quantify radiometabolites. Displacement and blocking experiments were done using cold MK-9470 and another inverse agonist, SR141716A. The distribution volume (V T ) of [ 18 F]MK-9470 was used as a quantitative measure and compared to the use of brain uptake, expressed as SUV, a simplified method of quantification. The percentage of intact [ 18 F]MK-9470 in arterial plasma samples was 80 ± 23 % at 10 min, 38 ± 30 % at 40 min and 13 ± 14 % at 210 min. A polar radiometabolite fraction was detected in plasma and brain tissue. The brain radiometabolite concentration was uniform across the whole brain. Displacement and pretreatment studies showed that 56 % of the tracer binding was specific and reversible. V T values obtained with a one-tissue compartment model plus constrained radiometabolite input had good identifiability (≤10 %). Ignoring the radiometabolite contribution using a one-tissue compartment model alone, i.e. without constrained radiometabolite input, overestimated the [ 18 F]MK-9470 V T , but was correlated. A correlation between [ 18 F]MK-9470 V T and SUV in the brain was also found (R 2 = 0.26-0.33; p ≤ 0.03). While the presence of a brain-penetrating radiometabolite fraction complicates the quantification of [ 18 F]MK-9470 in the rat brain, its tracer kinetics can be modelled using a one-tissue compartment model with and without constrained radiometabolite input. (orig.)

Defense POW/MIA Accounting Agency > News & Stories > Recent News & Stories

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Skip to main content (Press Enter). Toggle navigation Defense POW/MIA Accounting Agency Search Search DPAA: Search Search DPAA: Search Defense POW/MIA Accounting Agency Fulfilling Our Nation's Promise Defense POW/MIA Accounting Agency Home Families Family Events Posters Contact Information Our Missing Past

Preclinical evaluation and quantification of [{sup 18}F]MK-9470 as a radioligand for PET imaging of the type 1 cannabinoid receptor in rat brain

Energy Technology Data Exchange (ETDEWEB)

Casteels, Cindy [K.U. Leuven, University Hospital Leuven, Division of Nuclear Medicine, Leuven (Belgium); K.U. Leuven, MoSAIC, Molecular Small Animal Imaging Center, Leuven (Belgium); University Hospital Gasthuisberg, Division of Nuclear Medicine, Leuven (Belgium); Koole, Michel; Laere, Koen van [K.U. Leuven, University Hospital Leuven, Division of Nuclear Medicine, Leuven (Belgium); K.U. Leuven, MoSAIC, Molecular Small Animal Imaging Center, Leuven (Belgium); Celen, Sofie; Bormans, Guy [K.U. Leuven, MoSAIC, Molecular Small Animal Imaging Center, Leuven (Belgium); K.U. Leuven, Laboratory for Radiopharmacy, Leuven (Belgium)

2012-09-15

[{sup 18}F]MK-9470 is an inverse agonist for the type 1 cannabinoid (CB1) receptor allowing its use in PET imaging. We characterized the kinetics of [{sup 18}F]MK-9470 and evaluated its ability to quantify CB1 receptor availability in the rat brain. Dynamic small-animal PET scans with [{sup 18}F]MK-9470 were performed in Wistar rats on a FOCUS-220 system for up to 10 h. Both plasma and perfused brain homogenates were analysed using HPLC to quantify radiometabolites. Displacement and blocking experiments were done using cold MK-9470 and another inverse agonist, SR141716A. The distribution volume (V{sub T}) of [{sup 18}F]MK-9470 was used as a quantitative measure and compared to the use of brain uptake, expressed as SUV, a simplified method of quantification. The percentage of intact [{sup 18}F]MK-9470 in arterial plasma samples was 80 {+-} 23 % at 10 min, 38 {+-} 30 % at 40 min and 13 {+-} 14 % at 210 min. A polar radiometabolite fraction was detected in plasma and brain tissue. The brain radiometabolite concentration was uniform across the whole brain. Displacement and pretreatment studies showed that 56 % of the tracer binding was specific and reversible. V{sub T} values obtained with a one-tissue compartment model plus constrained radiometabolite input had good identifiability ({<=}10 %). Ignoring the radiometabolite contribution using a one-tissue compartment model alone, i.e. without constrained radiometabolite input, overestimated the [{sup 18}F]MK-9470 V{sub T}, but was correlated. A correlation between [{sup 18}F]MK-9470 V{sub T} and SUV in the brain was also found (R {sup 2} = 0.26-0.33; p {<=} 0.03). While the presence of a brain-penetrating radiometabolite fraction complicates the quantification of [{sup 18}F]MK-9470 in the rat brain, its tracer kinetics can be modelled using a one-tissue compartment model with and without constrained radiometabolite input. (orig.)

Defense Agency Travel Payments at Defense Finance and Accounting Service Indianapolis Center

National Research Council Canada - National Science Library

1997-01-01

The audit objective was to assess the effectiveness of Defense Finance and Accounting Service Indianapolis Center management controls over payments to Defense agency personnel for temporary duty and local travel...

Increasing TRIGA fuel lifetime with 12 wt.% U TRIGA fuel

Energy Technology Data Exchange (ETDEWEB)

Naughton, W F; Cenko, M J; Levine, S H; Witzig, W F [Pennsylvania State University (United States)

1974-07-01

In-core fuel management studies have been performed for the Penn State Breazeale Reactor (PSBR) wherein 12 wt % U fuel elements are used to replace the standard 8.5 wt % U TRIGA fuel. The core configuration used to develop a calculational model was a 90-element hexagonal array, which is representative of the PSBR core, and consists of five hexagonal rings surrounding a central thimble containing water. The technique employed for refueling the core fully loaded with 8.5 wt % U fuel involves replacing 8.5 wt % U fuel with 12 wt % U fuel using an in-out reloading scheme. A batch reload consists of 6 new 12 wt % U fuel elements. Placing the 12 wt % U fuel in the B ring produces fuel temperatures ({approx}450 {sup o}C) that are well below the 800{sup o}C maximum limitation when the PSBR is operating at its maximum allowed power of 1 Megawatt. The advantages of using new 12 wt % U fuel to replace the burned up 8.5 wt % U fuel in the B ring over refueling strictly with 8.5 wt % U-Zr TRIGA fuel are clearly delineated in Table 1 where cost calculations used the General Atomic pre-1972 prices for TRIGA fuel, i.e., $1500 and $1650 for an 8.5 and 12 wt % U fuel element, respectively. Experimental results obtained to date utilizing the 12 wt % U fuel elements agree with the computed results. (author)

International Atomic Energy Agency Publications. Catalogue 1986-1999

International Nuclear Information System (INIS)

2000-07-01

This catalogue lists all sales publications of the International Atomic Energy Agency issued from 1986 up to the end of 1999 and still available. Some earlier titles which form part of an established series or are still considered of importance have been included. Most Agency publications are issued in English, though some are also available in Chinese, French, Russian or Spanish. This is noted as C for Chinese, E for English, F for French, R for Russian and S for Spanish by the relevant ISBN number

Preclinical evaluation and quantification of [(18)F]MK-9470 as a radioligand for PET imaging of the type 1 cannabinoid receptor in rat brain

OpenAIRE

Casteels, Cindy; Koole, Michel; Celen, Sofie; Bormans, Guy; Van Laere, Koen

2012-01-01

PURPOSE: [(18)F]MK-9470 is an inverse agonist for the type 1 cannabinoid (CB1) receptor allowing its use in PET imaging. We characterized the kinetics of [(18)F]MK-9470 and evaluated its ability to quantify CB1 receptor availability in the rat brain. METHODS: Dynamic small-animal PET scans with [(18)F]MK-9470 were performed in Wistar rats on a FOCUS-220 system for up to 10 h. Both plasma and perfused brain homogenates were analysed using HPLC to quantify radiometabolites. Displacement and blo...

Industrial and commercial applications for a Triga reactor

International Nuclear Information System (INIS)

Green, D.

1986-01-01

The Physics and Radioisotope Services Group of ICI operates a Triga Reactor in support of a commercial, Industrial Radioisotope Technology Service. The technical and commercial development of this business is discussed in the context of operating a Triga Reactor in an Industrial Environment. (author)

Assessment results of the Indonesian TRIGA SNF to be shipped to INEEL

International Nuclear Information System (INIS)

Jefimoff, J.; Robb, A.K.; Wendt, K.M.; Syarip, I.; Alfa, T.

1997-01-01

This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination performed by technical personnel from the Idaho National Engineering and Environmental Laboratory (INEEL) at the Bandung and Yogyakarta research reactor facilities in Indonesia. The examination was required before the SNF would be accepted for transportation to and storage at the INEEL. This paper delineates the Initial Preparations prior to the Indonesian foreign research reactor (FRR) fuel examination. The technical basis for the examination, the TRIGA SNF Acceptance Criteria, and the physical condition required for transportation, receipt and storage of the TRIGA SNF at the INEEL is explained. In addition to the initial preparations, preparation descriptions of the Work Plan For TRIGA Fuel Examination, the Underwater Examination Equipment used, and personnel Examination Team Training are included. Finally, the Fuel Examination and Results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. Lessons learned from all the activities completed to date is provided in an addendum. The initial preparations included: (1) coordination between the INEEL, FRR or Badan Tenaga Atom Nasional (BATAN), DOE-HQ, and the US State Department and Embassy; (2) incorporating Savannah River Site (SRS) FRR experience and lessons learned; (3) collecting both FRR facility and spent fuel data, and issuing a radionuclide report (Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels) needed for transportation and fuel acceptance at the INEEL; and (4) preexamination work at the research reactor for the fuel examination

Set-up of a high-resolution 300 mK atomic force microscope in an ultra-high vacuum compatible "3He/10 T cryostat

International Nuclear Information System (INIS)

Allwörden, H. von; Ruschmeier, K.; Köhler, A.; Eelbo, T.; Schwarz, A.; Wiesendanger, R.

2016-01-01

The design of an atomic force microscope with an all-fiber interferometric detection scheme capable of atomic resolution at about 500 mK is presented. The microscope body is connected to a small pumped "3He reservoir with a base temperature of about 300 mK. The bakeable insert with the cooling stage can be moved from its measurement position inside the bore of a superconducting 10 T magnet into an ultra-high vacuum chamber, where the tip and sample can be exchanged in situ. Moreover, single atoms or molecules can be evaporated onto a cold substrate located inside the microscope. Two side chambers are equipped with standard surface preparation and surface analysis tools. The performance of the microscope at low temperatures is demonstrated by resolving single Co atoms on Mn/W(110) and by showing atomic resolution on NaCl(001).

Optimum burnup of BAEC TRIGA research reactor

International Nuclear Information System (INIS)

Lyric, Zoairia Idris; Mahmood, Mohammad Sayem; Motalab, Mohammad Abdul; Khan, Jahirul Haque

2013-01-01

Highlights: ► Optimum loading scheme for BAEC TRIGA core is out-to-in loading with 10 fuels/cycle starting with 5 for the first reload. ► The discharge burnup ranges from 17% to 24% of U235 per fuel element for full power (3 MW) operation. ► Optimum extension of operating core life is 100 MWD per reload cycle. - Abstract: The TRIGA Mark II research reactor of BAEC (Bangladesh Atomic Energy Commission) has been operating since 1986 without any reshuffling or reloading yet. Optimum fuel burnup strategy has been investigated for the present BAEC TRIGA core, where three out-to-in loading schemes have been inspected in terms of core life extension, burnup economy and safety. In considering different schemes of fuel loading, optimization has been searched by only varying the number of fuels discharged and loaded. A cost function has been defined and evaluated based on the calculated core life and fuel load and discharge. The optimum loading scheme has been identified for the TRIGA core, the outside-to-inside fuel loading with ten fuels for each cycle starting with five fuels for the first reload. The discharge burnup has been found ranging from 17% to 24% of U235 per fuel element and optimum extension of core operating life is 100 MWD for each loading cycle. This study will contribute to the in-core fuel management of TRIGA reactor

Applications of the Dow TRIGA research reactor

International Nuclear Information System (INIS)

Kocher, C.W.; Quinn, T.J.; Krueger, D.A.

1982-01-01

The Dow TRIGA Mark I reactor is a one-hundred kilowatt nuclear reactor installed by General Atomics using the Torrey Pines reactor console, seventy-five used stainless-steel clad fuel elements and one new aluminium clad fuel element. The reactor is equipped with a forty-position rotating Lazy Susan in the reflector, a pneumatic transfer system with its terminal in the F-ring of the core, and a central thimble which can be used for irradiation of samples in the center of the core or which can be emptied of the shielding water to produce a beam of neutrons and gamma rays in the area atop the pool. Samples can also be irradiated in or near the core. There is no provision for pulsing this TRIGA reactor. The neutron activation analysis program uses the Dow TRIGA reactor as a source of thermal neutrons and a Kaman A711 generator as a source of 14-MeV neutrons. The associated counting equipment includes one Gel(Li) detector and two Nal(Tl) detectors, each using a 100-position sample changer and all interfaced to a Tracor-Northern TN-11 data acquisition and computing system, one Ge(Li) detector and its TN-11 system for the pneumatic transfer system and the beam tube experiments, and two NaKTl)detectors with a TN-4000 system used with the Kaman neutron generator. The activation analysis program gets samples from all parts of the manufacturing and research efforts at Dow: raw materials, intermediates, products, effluents, research samples, samples from customers who use Dow products, and environmental samples. This presentation is devoted to the progress made in the past year on the pneumatic transfer system and the renewed work on prompt gamma-ray spectroscopy including the extensive process of method validation

Status of the TRIGA shipments to the INEEL from Europe

International Nuclear Information System (INIS)

Mustin, T.; Stump, R.C.; Tyacke, M.J.

1997-01-01

This paper reports the activities underway by the US Department of Energy (DOE) for returning Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) from foreign research reactors (FRR) in four European countries to the Idaho National Engineering and Environmental Laboratory (INEEL). Those countries are Germany, Italy, Romania, and Slovenia. This is part of the ''Nuclear Weapons Nonproliferation Policy'' of returning research reactor SNF containing uranium enriched in the US. This paper describes the results of a pre-assessment trip in September, 1997, to these countries, including: history of the reactors and research being performed; inventory of TRIGA SNF; fuel types (stainless steel, aluminum, or Incoloy) and enrichments; and each country's plans for returning their TRIGA SNF to the INEEL

Personnel, Area And Environmental Surveillance Practices At The PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Ligam, A.S.; Zarina Masood; Mohammad Suhaimi Kassim; Ismail Sulaiman; Mohd Fazli Zakaria; Ahmad Nabil Abdul Rahim

2013-01-01

Personnel, area and environmental surveillance at research reactors are important to ensure that the worker, public and environment do not receive radiation doses exceeding the prescribed national limits. A surveillance programme has been in place ever since the PUSPATI TRIGA Reactor (RTP) first started its operation in 1982. The results of the surveillance have to be reported to the national regulatory body as well as the International Atomic Energy Agency. This paper will discuss the findings and improvements of the surveillance programme over the past few years. It can be concluded that workers, public and the environment does not receive doses in excess of the prescribed limits due to the operation of the RTP.(author)

Set-up of a high-resolution 300 mK atomic force microscope in an ultra-high vacuum compatible {sup 3}He/10 T cryostat

Energy Technology Data Exchange (ETDEWEB)

Allwörden, H. von; Ruschmeier, K.; Köhler, A.; Eelbo, T.; Schwarz, A., E-mail: aschwarz@physnet.uni-hamburg.de; Wiesendanger, R. [Department of Physics, University of Hamburg, Jungiusstrasse 11, 20355 Hamburg (Germany)

2016-07-15

The design of an atomic force microscope with an all-fiber interferometric detection scheme capable of atomic resolution at about 500 mK is presented. The microscope body is connected to a small pumped {sup 3}He reservoir with a base temperature of about 300 mK. The bakeable insert with the cooling stage can be moved from its measurement position inside the bore of a superconducting 10 T magnet into an ultra-high vacuum chamber, where the tip and sample can be exchanged in situ. Moreover, single atoms or molecules can be evaporated onto a cold substrate located inside the microscope. Two side chambers are equipped with standard surface preparation and surface analysis tools. The performance of the microscope at low temperatures is demonstrated by resolving single Co atoms on Mn/W(110) and by showing atomic resolution on NaCl(001).

Twelfth European TRIGA users conference. Papers and abstracts

International Nuclear Information System (INIS)

2008-01-01

The Twelfth European TRIGA Users Conference was held in Pitesti, Romania, on September 28 - October 1, 1992, under the sponsorship of the Institute for Nuclear Research. The papers which follow in this document are presented in the same order as listed in the Conference Program. All papers which were received for publication (44) have been included. Those papers which were presented but not received for publication are presented in abstract form (3). The European TRIGA9 Owners' Group was fortunate to be hosted by the owners and users of the world's largest TRIGA reactor - the 14-MW Romanian research and test reactor. For too many years it has been impossible to enjoy open interactions with the Romanian researchers. By hosting the 1992 European TRIGA Users' Conference in Romania, the Romanians accomplished a breakthrough in the exchange of TRIGA reactor technology. It was very interesting for the Conference attendees from the West to learn about the large scope of excellent work conducted in Romania, especially at the Institute of Nuclear Research in Pitesti. Similarly, it was fortunate that a large attendance of Romanian researchers from many institutes, universities, and government agencies could attend the Conference and interact with their counterparts from outside Romania. The proceedings of the conference were structured onto the following 6 subject matters: - Opening Session and Introduction; - Session I, Operating and Maintenance Experience (10 papers); - Session II, Reactor Physics And Fuel Utilization (11 papers); - Session III, Instrumentation and Control (5 papers); - Session IV, Irradiation Facilities, Experimental Accessories (8 papers); - Session V, Applications, New Development of TRIGA Concept (6 papers). The document is completed with the abstracts of 3 contributions. A number of 19 experts from Austria, Germany, Italy, United States, Turkey, Morocco, England, Slovenia and Albania, that use TRIGA reactors, and Romania attended the conference. The

Financial Reporting Procedures for Defense Distribution Depots - Defense Logistics Agency Business Area of the Defense Business Operations Fund

National Research Council Canada - National Science Library

Young, Shelton

1994-01-01

In our audit of the FY 1993 Financial Statements for the Distribution Depots--Defense Logistics Agency Business Mea of the Defense Business Operations Fund, we evaluated procedures and controls used...

Decommissioning of the Northrop TRIGA reactor

International Nuclear Information System (INIS)

Cozens, George B.; Woo, Harry; Benveniste, Jack; Candall, Walter E.; Adams-Chalmers, Jeanne

1986-01-01

An overview of the administrative and operational aspects of decommissioning and dismantling the Northrop Mark F TRIGA Reactor, including: planning and preparation, personnel requirements, government interfacing, costs, contractor negotiations, fuel shipments, demolition, disposal of low level waste, final survey and disposition of the concrete biological shielding. (author)

Defense Contract Audit Agency Compensation Audits

National Research Council Canada - National Science Library

1999-01-01

.... The Defense Contract Audit Agency (DCAA) assists the administrative contracting officer in accomplishing that responsibility by determining whether the contractor's compensation system is sound, reliable, consistently applied, and results...

Kinetic analysis of the cannabinoid-1 receptor PET tracer [{sup 18}F]MK-9470 in human brain

Energy Technology Data Exchange (ETDEWEB)

Sanabria-Bohorquez, Sandra Marina; Hamill, Terence G.; Burns, H.D. [Merck Research Laboratories, Imaging, West Point, PA (United States); Goffin, Karolien; Laere, Koen van [University Hospital and K.U. Leuven, Division of Nuclear Medicine, Leuven (Belgium); Lepeleire, Inge de [Merck Research Laboratories, Brussels (Belgium); Bormans, Guy [K.U. Leuven, Laboratory of Radiopharmacy, Leuven (Belgium)

2010-05-15

Quantitative imaging of the type 1 cannabinoid receptor (CB1R) opens perspectives for many neurological and psychiatric disorders. We characterized the kinetics and reproducibility of the CB1R tracer [{sup 18}F]MK-9470 in human brain. [{sup 18}F]MK-9470 data were analysed using reversible models and the distribution volume V{sub T} and V{sub ND} k{sub 3} (V{sub ND} k{sub 3} = K{sub 1} k{sub 2}) were estimated. Tracer binding was also evaluated using irreversible kinetics and the irreversible uptake constant K{sub i} and fractional uptake rate (FUR) were estimated. The effect of blood flow on these parameters was evaluated. Additionally, the possibility of determining the tracer plasma kinetics using a reduced number of blood samples was also examined. A reversible two-tissue compartment model using a global k{sub 4} value was necessary to describe brain kinetics. Both V{sub T} and V{sub ND} k{sub 3} were estimated satisfactorily and their test-retest variability was between 10% and 30%. Irreversible methods adequately described brain kinetics and FUR values were equivalent to K{sub i}. The linear relationship between K{sub i} and V{sub ND} k{sub 3} demonstrated that K{sub i} or FUR and thus the simple measure of tracer brain uptake provide CB1R availability information. The test-retest variability of K{sub i} and FUR was <10% and estimates were independent of blood flow. Brain uptake can be used as a receptor availability index, albeit at the expense of potential bias due to between-subject differences in tracer plasma kinetics. [{sup 18}F]MK-9470 specific binding can be accurately determined using FUR values requiring a short scan 90 to 120 min after tracer administration. Our results suggest that [{sup 18}F]MK-9470 plasma kinetics can be assessed using a few venous samples. (orig.)

75 FR 43944 - Membership of the Defense Logistics Agency (DLA) Senior Executive Service (SES) Performance...

Science.gov (United States)

2010-07-27

... CONTACT: Ms. Lisa Novajosky, SES Program Manager, DLA Human Resources (J-14), Defense Logistics Agency... DEPARTMENT OF DEFENSE Defense Logistics Agency Membership of the Defense Logistics Agency (DLA... management of the SES cadre. DATES: Effective Date: September 16, 2010. ADDRESSES: Defense Logistics Agency...

Study of compoisiton of saturated vapor of MF-CuF2 systems, where M=K, Rb, Cs

International Nuclear Information System (INIS)

Morozov, I.V.; Korenev, Yu.M.

1993-01-01

Investigation into composition of saturated vapor of MF-CuF 2 systems where M=K, Rb, Cs is conducted using high-temperature mass-spectrometry. Existence of MCuF 3 molecules in gas phase is determined. MCuF 3(r) dissociation enthalpies are calculated using the first law-of thermodynamics and are compared with theoretically determined values. Value Δ D G 0 944 (CsCuF 3(r) =105.6±6.3 kj/mol is determined

Management Data Used to Manage the Defense Logistics Agency Supply Management Division of the Defense Business Operations Fund

National Research Council Canada - National Science Library

1994-01-01

The Defense Logistics Agency Supply Management Division (the Division) of the Defense Business Operations Fund provides supplies and logistics services to DoD Components and other (Government agencies...

Intergovernmental organisation activities: European Atomic Energy Community, International Atomic Energy Agency, OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

Anon.

2012-01-01

European Atomic Energy Community: Proposed legislative instruments, Adopted legislative instruments, Non-legislative instruments, Other activities (meetings). International Atomic Energy Agency: IAEA Action Plan on Nuclear Safety. OECD Nuclear Energy Agency: The Russian Federation to join the OECD Nuclear Energy Agency; Participation by the regulatory authorities of India and the United Arab Emirates in the Multinational Design Evaluation Programme (MDEP); NEA International Workshop on Crisis Communication, 9-10 May 2012; International School of Nuclear Law: 2013; Next NEA International Nuclear Law Essentials Course

77 FR 32952 - Defense Intelligence Agency National Intelligence University Board of Visitors Closed Meeting

Science.gov (United States)

2012-06-04

... DEPARTMENT OF DEFENSE Office of the Secretary Defense Intelligence Agency National Intelligence University Board of Visitors Closed Meeting AGENCY: Department of Defense, Defense Intelligence Agency, National Intelligence University. ACTION: Notice of closed meeting. SUMMARY: Pursuant to the provisions of...

TRIGA reactor main systems

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2007-01-01

This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

International Atomic Energy Agency Publications. Catalogue 1980-1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

This catalogue lists all sales publications of the International Atomic Energy Agency issued from 1980 up to the end of 1995 an still available. Some earlier titles which form part of an established series or are still considered of importance have been included. Most Agency publications are issued in English, though some are also available in Chinese, French, Russian or Spanish. This is noted as C for Chinese, E for English, F for French, R for Russian and S For Spanish by the relevant ISBN number. Proceedings of conferences, symposia, seminars and panels, of experts contain papers in their original language (English, French, Russian or Spanish) with abstracts in English and in the original language.

International Atomic Energy Agency Publications. Catalogue 1980-1995

International Nuclear Information System (INIS)

1996-08-01

This catalogue lists all sales publications of the International Atomic Energy Agency issued from 1980 up to the end of 1995 an still available. Some earlier titles which form part of an established series or are still considered of importance have been included. Most Agency publications are issued in English, though some are also available in Chinese, French, Russian or Spanish. This is noted as C for Chinese, E for English, F for French, R for Russian and S For Spanish by the relevant ISBN number. Proceedings of conferences, symposia, seminars and panels, of experts contain papers in their original language (English, French, Russian or Spanish) with abstracts in English and in the original language

Startup tests for TRIGA-ACPR at the Japan Atomic Energy Research Institute

International Nuclear Information System (INIS)

West, G.; Whittemore, W.

1976-01-01

The JAERI ACPR TRIGA startup tests involved procedures somewhat different from those considered standard for TRIGA. While the approach to critical followed standard procedures, the tests involving (1) the core loading to the permitted excess reactivity, and (2) the calibration of the 11 control rods (six Reg, two Safety, three Transient rods) were somewhat unusual. The power calibration involved three techniques: reactor noise analysis, flux foil activation, and calorimetry. The pulsing tests involved the insertion of increasing amounts of excess reactivity until the predicted performance was reached with a total insertion of $4.70. For,this the peak measured fuel temperature was 850 o C, and the integrated prompt energy release was about 100 megawatt-second, both in good agreement with predictions. (author)

TRIGA reactor characteristics

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2007-01-01

This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

Earth sciences. 1990-2001. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2001-05-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Earth Sciences and issued during the period 1 January 1990 - 31 May 2001. Most publications are issued in English, though some are also available in other languages. This is noted as A for Arabic, C for Chinese, E for English, F for French, R for Russian and S for Spanish before the relevant ISBN number

Driving Innovation to Support the Warfighter: Additive Manufacturing Initiatives Within the Defense Logistics Agency

Science.gov (United States)

2016-12-01

AM) in the commercial sector, but it is also intense for the Defense Logistics Agency (DLA), which hopes to capitalize on the promise of innovation...off. Criteria for assessing provider viability are more clearly defined and the technology’s broad market applicability and relevance are clearly...supply chain allows it to leverage its procurement and distribution ca- pabilities to capitalize on the potential new efficiencies of AM. Background

78 FR 32241 - Defense Intelligence Agency National Intelligence University Board of Visitors; Notice of Closed...

Science.gov (United States)

2013-05-29

... DEPARTMENT OF DEFENSE Office of the Secretary Defense Intelligence Agency National Intelligence University Board of Visitors; Notice of Closed Meeting AGENCY: National Intelligence University, Defense Intelligence Agency, Department of Defense. ACTION: Notice of closed meeting. SUMMARY: Pursuant to the...

Acquisition: Acquisition of Targets at the Missile Defense Agency

National Research Council Canada - National Science Library

Ugone, Mary L; Meling, John E; James, Harold C; Haynes, Christine L; Heller, Brad M; Pomietto, Kenneth M; Bobbio, Jaime; Chang, Bill; Pugh, Jacqueline

2005-01-01

Who Should Read This Report and Why? Missile Defense Agency program managers who are responsible for the acquisition and management of targets used to test the Ballistic Missile Defense System should be interested in this report...

Purchases of Consumable Items Transferred to the Defense Logistics Agency

National Research Council Canada - National Science Library

Young, Shelton

1995-01-01

Defense Management Report Decision 926, "Consolidation of Inventory Control Points," included a recommendation to transfer all consumable items managed by the Military Departments to the Defense Logistics Agency (DLA...

Department of Defense Agency Financial Report. Fiscal Year 2007

National Research Council Canada - National Science Library

2007-01-01

The Department of Defense (DoD) Fiscal Year (FY) 2007 Agency Financial Report (AFR) provides the President, the Congress, other Federal departments and agencies, and the American public an overview of the Department's financial condition...

Defense Agencies Initiative Increment 2 (DAI Inc 2)

Science.gov (United States)

2016-03-01

module. In an ADM dated September 23, 2013, the MDA established Increment 2 as a MAIS program to include budget formulation; grants financial...2016 Major Automated Information System Annual Report Defense Agencies Initiative Increment 2 (DAI Inc 2) Defense Acquisition Management...President’s Budget RDT&E - Research, Development, Test, and Evaluation SAE - Service Acquisition Executive TBD - To Be Determined TY - Then

10th European TRIGA users conference

International Nuclear Information System (INIS)

Anon.

1988-01-01

Abstracts of 46 papers on various aspects of Triga reactors (mainly Triga Mark 2 reactors) are given, according to the main headings: reactor operation and maintenance experience; new developments and improvements of Triga components and systems, including instrumentation; fuel and fuel management; safety aspects, licensing and radiation protection; experiments with Triga reactors; radiochemistry, radioisotope production and NAA; reactor physics. (qui)

41 CFR 101-26.603 - Electronic items available from the Defense Logistics Agency.

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Electronic items available from the Defense Logistics Agency. 101-26.603 Section 101-26.603 Public Contracts and Property... items available from the Defense Logistics Agency. Executive agencies shall satisfy their requirements...

78 FR 90 - Defense Intelligence Agency National Intelligence University Board of Visitors Closed Meeting

Science.gov (United States)

2013-01-02

... DEPARTMENT OF DEFENSE Office of the Secretary Defense Intelligence Agency National Intelligence University Board of Visitors Closed Meeting AGENCY: National Intelligence University, Defense Intelligence... hereby given that a closed meeting of the National Intelligence University Board of Visitors has been...

76 FR 4322 - Availability of the Fiscal Year 2009 Missile Defense Agency Services Contracts Inventory Pursuant...

Science.gov (United States)

2011-01-25

... DEPARTMENT OF DEFENSE Office of the Secretary Availability of the Fiscal Year 2009 Missile Defense... Act AGENCY: Missile Defense Agency (MDA), DoD. ACTION: Notice of availability. SUMMARY: In accordance... for Fiscal Year 2008 (NDAA 08) Section 807, the Director of the Missile Defense Agency and the Office...

Transition from HEU to LEU fuel in Romania's 14-MW TRIGA reactor

International Nuclear Information System (INIS)

Bretscher, M.M.; Snelgrove, J.L.

1995-01-01

The 14-MW TRIGA steady state reactor (SSR) located in Pitesti, Romania, first went critical in the fall of 1979. Initially, the core configuration for full power operation used 29 fuel clusters each containing a 5 x 5 square array of HEU U (10 wt% - ZrH - Er 2.8 wt%) fuel-moderator rods (1.295 cm o.d.) clad in Incoloy. With a total inventory of 35 HEU fuel clusters, burnup, considerations required a gradual expansion of the core from 29 to 32 and finally to 35 clusters before the reactor was shut down because of insufficient excess reactivity. At this time each of the original 29 fuel clusters had an average 235 U burnup in the range from 50 to 62%. Because of the U.S. policy regarding the export of highly enriched uranium, fresh HEU TRIGA replacement fuel is not available. After a number of safety-related measurements, the SSR is expected to resume full power operation in the near future using a mixed core containing five LEU TRIGA clusters of the same geometry as the original fuel but with fuel-moderator rods containing 45 wt% U (19.7% 235 U enrichment) and 1.1 wt% Er. Rods for 14 additional LEU fuel clusters will be fabricated by General Atomics. In support of the SSR mixed core operation numerous neutronic calculations have been performed. This paper presents some of the results of those calculations. (author)

Accounting for Defense Logistics Agency Supply Management Receivables

National Research Council Canada - National Science Library

Lane, F

1998-01-01

.... For this part of the audit, we determined whether Defense Logistics Agency supply management receivables were accurately accounted for, classified, and reported in the Statement of Financial Position...

Defense Logistics Agency Disposition Services Needs to Improve Demilitarization Program Self-Assessment Evaluations - Redacted

Science.gov (United States)

2016-12-20

from mandatory disclosure under the Freedom of Information Act. Defense Logistics Agency Disposition Services Needs to Improve Demilitarization...Project No. D2016-D000RD-0057.000) │ i Results in Brief Defense Logistics Agency Disposition Services Needs to Improve Demilitarization Program Self...Assessment Evaluations Visit us at www.dodig.mil December 20, 2016 Objective Our audit objective was to determine whether the Defense Logistics Agency

Experimental research in neutron physic and thermal-hydraulic at the CDTN Triga reactor

Energy Technology Data Exchange (ETDEWEB)

Mesquita, Amir Z.; Souza, Rose Mary G.P.; Ferreira, Andrea V.; Pinto, Antonio J.; Costa, Antonio C.L.; Rezende, Hugo C., E-mail: amir@cdtn.b, E-mail: souzarm@cdtn.b, E-mail: avf@cdtn.b, E-mail: ajp@cdtn.b, E-mail: aclc@cdtn.b, E-mail: hcr@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

The IPR-R1 TRIGA (Training, Research, Isotopes production, General Atomics) at Nuclear Technology Development Center (CDTN) is a pool type reactor cooled by natural circulation of light water and an open surface. TRIGA reactors, developed by General Atomics (GA), are the most widely used research reactor in the world and characterized by inherent safety. The IPR-R1 is the only Brazilian nuclear research reactor available and able to perform experiments in which interaction between neutronic and thermal-hydraulic areas occurs. The IPR-R1 has started up on November 11th, 1960. At that time the maximum thermal power was 30 kW. The present forced cooling system was built in the 70th and the power was upgraded to 100 kW. Recently the core configuration and instrumentation was upgraded again to 250 kW at steady state, and is awaiting the license of CNEN to operate definitely at this new power. This paper describes the experimental research project carried out in the IPR-R1 reactor that has as objective evaluate the behaviour of the reactor operational parameters, and mainly to investigate the influence of temperature on the neutronic variables. The research was supported by Research Support Foundation of the State of Minas Gerais (FAPEMIG) and Brazilian Council for Scientific and Technological Development (CNPq). The research project meets the recommendations of the IAEA, for safety, modernization and development of strategic plan for research reactors utilization. This work is in line with the strategic objectives of Brazil, which aims to design and construct the Brazilian Multipurpose research Reactor (RMB). (author)

Experimental research in neutron physic and thermal-hydraulic at the CDTN Triga reactor

International Nuclear Information System (INIS)

Mesquita, Amir Z.; Souza, Rose Mary G.P.; Ferreira, Andrea V.; Pinto, Antonio J.; Costa, Antonio C.L.; Rezende, Hugo C.

2011-01-01

The IPR-R1 TRIGA (Training, Research, Isotopes production, General Atomics) at Nuclear Technology Development Center (CDTN) is a pool type reactor cooled by natural circulation of light water and an open surface. TRIGA reactors, developed by General Atomics (GA), are the most widely used research reactor in the world and characterized by inherent safety. The IPR-R1 is the only Brazilian nuclear research reactor available and able to perform experiments in which interaction between neutronic and thermal-hydraulic areas occurs. The IPR-R1 has started up on November 11th, 1960. At that time the maximum thermal power was 30 kW. The present forced cooling system was built in the 70th and the power was upgraded to 100 kW. Recently the core configuration and instrumentation was upgraded again to 250 kW at steady state, and is awaiting the license of CNEN to operate definitely at this new power. This paper describes the experimental research project carried out in the IPR-R1 reactor that has as objective evaluate the behaviour of the reactor operational parameters, and mainly to investigate the influence of temperature on the neutronic variables. The research was supported by Research Support Foundation of the State of Minas Gerais (FAPEMIG) and Brazilian Council for Scientific and Technological Development (CNPq). The research project meets the recommendations of the IAEA, for safety, modernization and development of strategic plan for research reactors utilization. This work is in line with the strategic objectives of Brazil, which aims to design and construct the Brazilian Multipurpose research Reactor (RMB). (author)

Some concept for the TRIGA core design

International Nuclear Information System (INIS)

Aizawa, Otohiko

1994-01-01

There is the research reactor called TRIGA Mark-2 of 100 kW in Atomic Energy Research Laboratory, Musashi Institute of Technology. Recently, while the various calculations on the core were carried out, the author became aware of that this TRIGA core was designed at that time with excellent consideration. The reason for that is, although fuel is arranged in simple concentric circular state at a glance, it was known that in reality, this is the modification of the hexagonal core of triangular lattice. In the examination of square lattice fuel arrangement, the reactivity was calculated by using the gap between fuel rods as the parameter and by using ENDF/B-4 library and Monte Carlo code Keno-5. It is known that the design of the lattice with maximum reactivity cannot be done by the square lattice. The similar examination was carried out on triangular lattice, and it was found that the gap between fuel rods of 4 mm is the optimal design. The average neutron energy spectra in the fuel rods of the TRIGA Mark-2 core agreed considerably well with the energy spectra at 4.16 cm fuel rod pitch in triangular hexagonal core. In the reactor of about 100 kW, even if the gap between fuel rods is less than 4 mm, heat removal is sufficiently possible. (K.I.)

Modeling a TRIGA Power System with ATHENA

International Nuclear Information System (INIS)

Davis, C.B.

1985-01-01

GA Technologies TRIGA Power System (TPS) is a power-producing version of the Training Research and Isotope General Atomic (TRIGA) reactor. The TPS analyzed here is designed to produce 10 MW of electrical power. The TPS features three major thermal-hydraulic systems, including a water-filled primary coolant system, a water-filled residual heat removal system, and a Freon-filled secondary coolant system. A thermal-hydraulic model of the TPS was developed using the Advanced Thermal Hydraulic Energy Network Analyzer (ATHENA) computer code, and two demonstration calculations were performed. ATHENA is based on the Reactor Excursion and Leak Analysis Program (RELAP5/MOD2) and has similar, but expanded capabilities. The expanded capabilities allow the representation of several different fluids, including water and Freon-11. This paper provides descriptions of the TPS, the ATHENA computer code and ATHENA TPS model, results of the demonstration calculations, conclusions, and references. 2 refs., 7 figs

Supervisory system to monitor the neutron flux of the IPR-R1 TRIGA research reactor at CDTN

International Nuclear Information System (INIS)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Tello, Cledola Cassia Oliveira

2009-01-01

The IPR-R1 TRIGA Mark I nuclear research reactor at the Nuclear Technology Development Center - CDTN (Belo Horizonte) is a pool type reactor. It was designed for research, training and radioisotope production. The International Atomic Energy Agency- IAEA - recommends the use of friendly interfaces for monitoring and controlling the operational parameters of nuclear reactors. This paper reports the activities for implementing a supervisory system, using LabVIEW software, with the purpose to provide the IPR-R1 TRIGA research reactor with a modern, safe and reliable system to monitor the time evolution of the power of its core. The use of the LabVIEW will introduce modern techniques, based on electronic processor and visual interface in video monitor, substituting the mechanical strip chart recorders (ink-pen drive and paper) that monitor the current neutrons flux, which is proportional to the thermal power supplied by reactor core. The main objective of the system will be to follow the evolution of the neutronic flux originated in the Linear and Logarithmic channels. A great advantage of the supervisory software nowadays, in relation to computer programs currently used in the facility, is the existence of new resources such as the data transmission and graphical interfaces by net, grid lines display in the graphs, and resources for real time reactor core video recordings. The considered system could also in the future be optimized, not only for data acquisition, but also for the total control of IPR-R1 TRIGA reactor(author)

TRIGA 14 MW Research Reactor Status and Utilization

International Nuclear Information System (INIS)

Barbos, D.; Ciocanescu, M.; Paunoiu, C.

2016-01-01

Institute for Nuclear Research is the owner of the largest family TRIGA research reactor, TRIGA14 MW research reactor. TRIGA14 MW reactor was designed to be operated with HEU nuclear fuel but now the reactor core was fully converted to LEU nuclear fuel. The full conversion of the core was a necessary step to ensure the continuous operation of the reactor. The core conversion took place gradually, using fuel manufactured in different batches by two qualified suppliers based on the same well qualified technology for TRIGA fuel, including some variability which might lead to a peculiar behaviour under specific conditions of reactor utilization. After the completion of the conversion a modernization program for the reactor systems was initiated in order to achieve two main objectives: safe operation of the reactor and reactor utilization in a competitive environment to satisfy the current and future demands and requirements. The 14 MW TRIGA research reactor operated by the Institute for Nuclear Research in Pitesti, Romania, is a relatively new reactor, commissioned 37 years ago. It is expected to operate for another 15-20 years, sustaining new fuel and testing of materials for future generations of power reactors, supporting radioisotopes production through the development of more efficient new technologies, sustaining research or enhanced safety, extended burn up and verification of new developments concerning nuclear power plants life extension, to sustain neutron application in physics research, thus becoming a centre for instruction and training in the near future. A main objective of the TRIGA14MW research reactor is the testing of nuclear fuel and nuclear material. The TRIGA 14 MW reactor is used for medical and industrial radioisotopes production ( 131 I, 125 I, 192 Ir etc.) and a method for 99 Mo- 99 Tc production from fission is under development. For nuclear materials properties investigation, neutron radiography methods have been developed in the INR. The

The 10 MW multipurpose TRIGA reactor at Ongkharak Nuclear Research Center, Thailand

International Nuclear Information System (INIS)

Thurgood, B.E.; Razvi, J.; Whittemore, J.L.; Bhadrakom, K.

1997-01-01

General Atomics (GA), has been selected to lead a team of firms from the United States, Japan, Australia and Thailand to design, build and commission the Ongkharak Nuclear Research Center near Bangkok, Thailand, for the Office of Atomic Energy for Peace. The facilities to be provided comprise of: A Reactor Island, consisting of a 10 MW TRIGA reactor that takes full advantage of the inherent safety characteristics of uranium-zirconium hydride (UZrH) fuel; An Isotope Production Facility for the production of radioisotopes and radiopharmaceuticals using the TRIGA reactor; A Waste Processing and Storage Facility for the processing and storage of radioactive waste from the facility as well as other locations in Thailand. The centerpiece of the Center will be the TRIGA reactor, fueled with low-enriched UZrH fuel, cooled and moderated by light water, and reflected by beryllium and heavy water. The UZrH fueled reactor will have a rated steady state thermal power output of 10 MW, and will be capable of performing the following: Radioisotope production for medical, industrial and agricultural uses; Neutron transmutation doping of silicon; Beam experiments such as Neutron Scattering, Neutron Radiography (NR), and Prompt Gamma Neutron Activation Analysis (PGNAA); Medical therapy of patients using Boron Neutron Capture Therapy (BNCT); Applied research and technology development in the nuclear field; Training in principles of reactor operation, reactor physics, reactor experiments, etc. (author)

The post-irradiated examination of CANDU type fuel irradiated in the Institute for Nuclear Research TRIGA reactor

International Nuclear Information System (INIS)

Tuturici, I.L.; Parvan, M.; Dobrin, R.; Popov, M.; Radulescu, R.; Toma, V.

1995-01-01

This post-irradiation examination work has been done under the Research Contract No. 7756/RB, concluded between the International Atomic Energy Agency and the Institute for Nuclear Research. The paper contains a general description of the INR post-irradiation facility and methods and the relevant post-irradiation examination results obtained from an irradiated experimental CANDU type fuel element designed, manufactured and tested by INR in a power ramp test in the 100 kW Pressurised Water Irradiation Loop of the TRIGA 14 MW(th) Reactor. The irradiation experiment consisted in testing an assembly of six fuel elements, designed to reach a bumup of ∼ 200 MWh/kgU, with typical CANDU linear power and ramp rate. (author)

Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia.

Science.gov (United States)

Yavar, A R; Khalafi, H; Kasesaz, Y; Sarmani, S; Yahaya, R; Wood, A K; Khoo, K S

2012-10-01

A 3-D model for 1 MW TRIGA Mark II research reactor was simulated. Neutron flux parameters were calculated using MCNP-4C code and were compared with experimental results obtained by k(0)-INAA and absolute method. The average values of φ(th),φ(epi), and φ(fast) by MCNP code were (2.19±0.03)×10(12) cm(-2)s(-1), (1.26±0.02)×10(11) cm(-2)s(-1) and (3.33±0.02)×10(10) cm(-2)s(-1), respectively. These average values were consistent with the experimental results obtained by k(0)-INAA. The findings show a good agreement between MCNP code results and experimental results. Copyright © 2012 Elsevier Ltd. All rights reserved.

International Atomic Energy Agency activities in decommissioning

International Nuclear Information System (INIS)

Reisenweaver, D W.; )

2005-01-01

Full text: The International Atomic Energy Agency (IAEA) has been addressing the safety and technical issues of decommissioning for over 20 years, but their focus has been primarily on planning. Up to know, the activities have been on an ad hoc basis and sometimes, important issues have been missed. A new Action Plan on the Decommissioning of Nuclear Facilities has recently been approved by the Agency's board of Governors which will focus the Agency's efforts and ensure that our Member States' concerns are addressed. The new initiatives associated with this Action Plan will help ensure that decommissioning activities in the future are performed in a safe and coherent manner. The International Atomic Energy Agency (IAEA) has been preparing safety and technical documents concerning decommissioning since the mid-1980's. There have been over 30 documents prepared that provide safety requirements, guidance and supporting technical information. Many of these documents are over 10 years old and need updating. The main focus in the past has been on planning for decommissioning. During the past five years, a set of Safety Standards have been prepared and issued to provide safety requirements and guidance to Member States. However, decommissioning was never a real priority with the Agency, but was something that had to be addressed. To illustrate this point, the first requirements documents on decommissioning were issued as part of a Safety Requirements [1] on pre-disposal management of radioactive waste. It was felt that decommissioning did not deserve its own document because it was just part of the normal waste management process. The focus was mostly on waste management. The Agency has assisted Member States with the planning process for decommissioning. Most of these activities have been focused on nuclear power plants and research reactors. Now, support for the decommissioning of other types of facilities is being requested. The Agency is currently providing technical

Thermal 18F atom addition to olefins

International Nuclear Information System (INIS)

Rogers, P.J.M.

1986-01-01

The addition of thermal 18 F atoms to olefins was investigated using various substrate molecules. The 18 F atoms were produced by the 19 F(n,2n) 18 F nuclear reaction with >10 5 eV of energy which is removed by multiple collisions with SF 6 molecules before reaction occurs with an olefin. By varying the SF 6 /substrate mole ratio it was demonstrated that the fraction of non-thermal reactions is dependent upon the frequency of non-reactive energy reducing collisions with SF 6 . The rate constants for addition and abstraction reactions with propene, cis-1-chloropropene and trans-1-chloropropene were determined. The substitution of a C1 atom for the olefinic H atom in the C 1 position does not affect the rate of 18 F bond formation but it changes the orientation of attack. The 18 F atom prefers the terminal carbon-in propene and propene-d 6 by a factor of 1.35 while the preference is less than 0.5 for the terminal carbon in cis-1-chloropropene and trans-1-chloropropene. The addition of 18 F atoms to olefins creates vibrationally excited fluoroalkyl radicals which can either decompose or stabilize by collision with another molecule. The rate constants for decomposition of excited CH 3 CHCHC1F radicals formed by 18 F addition to cis-1-chloropropene and trans-1-chloropropene are competitive with C 1 -C 2 bond rotation. The 18 F atoms add to the parent molecule with retention of geometry and a memory of the geometry persists as demonstrated by the cis-1-fluoropropene/trans-1-fluoropropene decomposition product ratio

41 CFR 101-26.602 - Fuels and packaged petroleum products obtained from or through the Defense Logistics Agency.

Science.gov (United States)

2010-07-01

... petroleum products obtained from or through the Defense Logistics Agency. 101-26.602 Section 101-26.602... Logistics Agency. (a) Agencies shall be governed by the provisions of this § 101-26.602 in satisfying... petroleum products from or through the Defense Logistics Agency. (b) The Defense Logistics Agency has been...

Safety evaluation for instrumentation and control system upgrading project of Malaysian TRIGA MARK II PUSPATI Research reactor

International Nuclear Information System (INIS)

Ridha Roslan; Nik Mohd Faiz Khairuddin

2013-01-01

Full-text: Malaysian TRIGA MARK II research reactor has been in safe operation since its first criticality in 1982. The reactor is licensed to be operated by Malaysian Nuclear Agency to perform training and research development related activities. Due to its extensive operation since last three decades, the option of modifications for safety and safety-related item and component become a necessary to replace the outdated equipment to a stat-of-art, reliable technologies. This paper will present the current regulatory activities performed by Atomic Energy Licensing Board (AELB) to ensure the upgrading of analogue to digital instrumentation and control system is implemented in safe manner. The review activity includes documentation review, manufacturer quality audit and on-site inspection for commissioning. The review performed by AELB is based on The International Atomic Energy Agency (IAEA) Safety Requirements NS-R-4, entitled Safety of Research Reactors. During this endeavour, AELB seeks technical cooperation from Korea Institute of Nuclear Safety (KINS), the nuclear experts organization of the country of origin of the instrumentation and control technology. The regulatory activity is still on-going and is expected to be completed by issuance of Authorization for Restart on December 2013. (author)

Three-dimensional coupled kinetics/thermal- hydraulic benchmark TRIGA experiments

International Nuclear Information System (INIS)

Feltus, Madeline Anne; Miller, William Scott

2000-01-01

This research project provides separate effects tests in order to benchmark neutron kinetics models coupled with thermal-hydraulic (T/H) models used in best-estimate codes such as the Nuclear Regulatory Commission's (NRC) RELAP and TRAC code series and industrial codes such as RETRAN. Before this research project was initiated, no adequate experimental data existed for reactivity initiated transients that could be used to assess coupled three-dimensional (3D) kinetics and 3D T/H codes which have been, or are being developed around the world. Using various Test Reactor Isotope General Atomic (TRIGA) reactor core configurations at the Penn State Breazeale Reactor (PSBR), it is possible to determine the level of neutronics modeling required to describe kinetics and T/H feedback interactions. This research demonstrates that the small compact PSBR TRIGA core does not necessarily behave as a point kinetics reactor, but that this TRIGA can provide actual test results for 3D kinetics code benchmark efforts. This research focused on developing in-reactor tests that exhibited 3D neutronics effects coupled with 3D T/H feedback. A variety of pulses were used to evaluate the level of kinetics modeling needed for prompt temperature feedback in the fuel. Ramps and square waves were used to evaluate the detail of modeling needed for the delayed T/H feedback of the coolant. A stepped ramp was performed to evaluate and verify the derived thermal constants for the specific PSBR TRIGA core loading pattern. As part of the analytical benchmark research, the STAR 3D kinetics code (, STAR: Space and time analysis of reactors, Version 5, Level 3, Users Guide, Yankee Atomic Electric Company, YEAC 1758, Bolton, MA) was used to model the transient experiments. The STAR models were coupled with the one-dimensional (1D) WIGL and LRA and 3D COBRA (, COBRA IIIC: A digital computer program for steady-state and transient thermal-hydraulic analysis of rod bundle nuclear fuel elements, Battelle

Using TRIGA Mark II research reactor for irradiation with thermal neutrons

Energy Technology Data Exchange (ETDEWEB)

Kolšek, Aljaž, E-mail: aljaz.kolsek@gmail.com; Radulović, Vladimir, E-mail: vladimir.radulovic@ijs.si; Trkov, Andrej, E-mail: andrej.trkov@ijs.si; Snoj, Luka, E-mail: luka.snoj@ijs.si

2015-03-15

Highlights: • Monte Carlo N-Particle Transport Code was used to design and perform calculations. • Characterization of the TRIGA Mark II ex-core irradiation facilities was performed. • The irradiation device was designed in the TRIGA irradiation channel. • The use of the device improves the fraction of thermal neutron flux by 390%. - Abstract: Recently a series of test irradiations was performed at the JSI TRIGA Mark II reactor for the Fission Track-Thermoionization Mass Spectrometry (FT-TIMS) method, which requires a well thermalized neutron spectrum for sample irradiation. For this purpose the Monte Carlo N-Particle Transport Code (MCNP5) was used to computationally support the design of an irradiation device inside the TRIGA model and to support the actual measurements by calculating the neutron fluxes inside the major ex-core irradiation facilities. The irradiation device, filled with heavy water, was designed and optimized inside the Thermal Column and the additional moderation was placed inside the Elevated Piercing Port. The use of the device improves the ratio of thermal neutron flux to the sum of epithermal and fast neutron flux inside the Thermal Column Port by 390% and achieves the desired thermal neutron fluence of 10{sup 15} neutrons/cm{sup 2} in irradiation time of 20 h.

Status of DOE defense waste management policy

International Nuclear Information System (INIS)

Oertel, K.G.; Scott, R.S.

1983-01-01

This paper very briefly traces the statutory basis for DOE management of atomic energy defense activity wastes, touches on the authority of the Federal agencies involved in the regulation of defense nuclear waste management, and addresses the applicable regulations and their status. This background sets the stage for a fairly detailed discussion of management and disposal strategies of the Defense Waste and Byproducts Management Program

Credible accident analyses for TRIGA and TRIGA-fueled reactors

International Nuclear Information System (INIS)

Hawley, S.C.; Kathren, R.L.

1982-04-01

Credible accidents were developed and analyzed for TRIGA and TRIGA-fueled reactors. The only potential for offsite exposure appears to be from a fuel-handling accident that, based on highly conservative assumptions, would result in dose equivalents of less than or equal to 1 mrem to the total body from noble gases and less than or equal to 1.2 rem to the thyroid from radioiodines. Credible accidents from excess reactivity insertions, metal-water reactions, lost, misplaced, or inadvertent experiments, core rearrangements, and changes in fuel morphology and ZrH/sub x/ composition are also evaluated, and suggestions for further study provided

Thermal neutron spectrum distribution in TRIGA fuels

International Nuclear Information System (INIS)

Gui Ah Auu; Harasawa, Susumu; An, Shigehiro

1989-01-01

The dependence of thermal neutron spectrum in TRIGA fuel cell on fuel temperature and TRIGA fuel types were studied using LIBP and THERMOS codes. Some characteristics of the TRIGA fuel including its prompt negative temperature coefficient of reactivity were explained using the results of the study. (author)

Core Calculation of 1 MWatt PUSPATI TRIGA Reactor (RTP) using Monte Carlo MVP Code System

Science.gov (United States)

Karim, Julia Abdul

2008-05-01

The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speed by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained.

Core Calculation of 1 MWatt PUSPATI TRIGA Reactor (RTP) using Monte Carlo MVP Code System

International Nuclear Information System (INIS)

Karim, Julia Abdul

2008-01-01

The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speed by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained

Defense Special Weapons Agency Advisory Panel on the Nuclear Weapon Effects Program

National Research Council Canada - National Science Library

1998-01-01

We performed the audit in response to allegations made to the Defense Hotline concerning conflicts of interest among members of the Defense Special Weapons Agency Advisory Panel on the Nuclear Weapon Effects Program...

European TRIGA owners' conference. Papers and abstracts

International Nuclear Information System (INIS)

1970-01-01

The conference covers the following topics, concerning TRIGA reactors: Experience in the Operation and Maintenance and utilization of TRIGA reactors; reactor upgrading; irradiation facilities; fuel management; air-concentration measurements; nuclear tests; use of TRIGA in nuclear medicine and biology; reactor design, fuel and performance; failures and other research activities

Department of Defense support to spill response operations

International Nuclear Information System (INIS)

Ducey, D.L. Jr.; Walker, A.H.

1993-01-01

The Department of Defense (DOD), operating through the Directorate of Military Support in the Department of the Army, supports state, local and other federal agency response operations in a wide range of natural and man-caused emergencies. Examples within the past six years include the Ashland Oil tank collapse in Floreffe, Pennsylvania, Exxon Valdez cleanup, Loma Prieta earthquake, hurricanes Hugo and Andrew, Mexico City earthquake, Armero (Columbia) volcanic eruption, and Puerto Rico floods and mud slides. From March 24 to September 27, 1989, the period of the Exxon Valdez initial cleanup operations, DOD provided military and civilian personnel, US Navy ships for housing response workers, cargo and medical evacuation aircraft (fixed wing and helicopters), skimmers, modified dredges, landing craft, Dracones, Zodiak boats, radios, computers, and other miscellaneous equipment. This was in addition to assets of the Alaska Army and Air National Guard, which were committed by the governor. Support was provided to the US Coast Guard on scene coordinator and supervised by the Alaska Oil Spill Joint Task Force. The General Accounting Office, in its January 1990 report, Federal Costs Resulting from the Exxon Valdez Oil Spill, estimated that DOD spent $62.8 million through September 30, 1989, the largest expenditure by any federal agency. Use of military resources is a realistic scenario in certain situations. Primary responders at the federal and state level should understand how to request and employ these assets. This paper provides a background on DOD support to disaster relief operations, and discusses the types of support available to agencies responding to natural or man-caused emergencies, request and approval mechanisms, the Department of Defence organization to provide support, and reimbursement of the department

The Chip-Scale Atomic Clock - Prototype Evaluation

Science.gov (United States)

2007-11-01

39th Annual Precise Time and Time Interval (PTTI) Meeting THE CHIP-SCALE ATOMIC CLOCK – PROTOTYPE EVALUATION R. Lutwak *, A. Rashed...been supported by the Defense Advanced Research Projects Agency, Contract # NBCHC020050. REFERENCES [1] R. Lutwak , D. Emmons, W. Riley, and...D.C.), pp. 539-550. [2] R. Lutwak , D. Emmons, T. English, W. Riley, A. Duwel, M. Varghese, D. K. Serkland, and G. M. Peake, 2004, “The Chip-Scale

STRUCTURAL CALCULATIONS FOR THE CODISPOSAL OF TRIGA SPENT NUCLEAR FUEL IN A WASTE PACKAGE

International Nuclear Information System (INIS)

S. Mastilovic

1999-01-01

The purpose of this analysis is to determine the structural response of a TRIGA Department of Energy (DOE) spent nuclear fuel (SNF) codisposal canister placed in a 5-Defense High Level Waste (DHLW) waste package (WP) and subjected to a tipover design basis event (DBE) dynamic load; the results will be reported in terms of displacements and stress magnitudes. This activity is associated with the WP design

A TRIGA reactor in an industrial laboratory

International Nuclear Information System (INIS)

Anders, Oswald U.

1980-01-01

The Dow TRIGA Reactor is a well established facility in its industrial environment. It is used extensively for internal Dow projects. The primary use of the TRIGA is as neutron source for NAA. It faces similar technical and organizational challenges as other TRIGA installations and over the years developed its own solutions

Performance Monitoring for Nuclear Safety Related Instrumentation at PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2015-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on performance monitoring for nuclear safety related instrumentation in TRIGA PUSPATI Reactor (RTP) of based on various parameter of reactor safety instrument channel such as log power, linear power, Fuel temperature, coolant temperature will take into consideration. Methodology of performance on estimation and monitoring is to evaluate and analysis of reactor parameters which is important of reactor safety and control. And also to estimate power measurement, differential of log and linear power and fuel temperature during reactor start-up, operation and shutdown .This study also focus on neutron power fluctuation from fission chamber during reactor start-up and operation. This work will present result of performance monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that performance of nuclear safety related instrumentation will improved the reactor control and safety parameter during reactor start-up, operation and shutdown. (author)

Simulation development for TRIGA reactor

International Nuclear Information System (INIS)

Handoyo, D.

1997-01-01

A simulator of the dynamic of TRIGA reactor has been made. this simulator is meant to study the reactor kinetic behavior and for operator training to more assure the safety and the reliability of the real operation of TRIGA reactor. the simulator consists of PC (Personal Computer) for processing the calculation of reactivity, neutron flux, period, ect and control panel for regulating the input data such as the change of power range, control rod position as well as cooling flow rate. the result will be displayed on screen monitor of personal computer as given in the real control room of TRIGA reactor. the output of simulator will be verified by comparing with measurement result in the real TRIGA MARK II reactor of Musashi institute of technology. for the change of reactivity of 0.3, 0.5 and 0.7 the reactor power and fuel temperature between the simulator and measurements are comparable

Opportunities for TRIGA reactors in neutron radiography

International Nuclear Information System (INIS)

Barton, John P.

1978-01-01

In this country the two most recent installations of TRIGA reactors have both been for neutron radiography, one at HEDL and the other at ANL. Meanwhile, a major portion of the commercial neutron radiography is performed on a TRIGA fueled reactor at Aerotest. Each of these installations has different primary objectives and some comparative observations can be drawn. Another interesting comparison is between the TRIGA reactors for neutron radiography and other small reactors that are being installed for this purpose such as the MIRENE slow pulse reactors in France, a U-233 fueled reactor for neutron radiography in India and the L88 solution reactor in Denmark. At Monsanto Laboratory, in Ohio, a subcritical reactor based on MTR-type fuel has recently been purchased for neutron radiography. Such systems, when driven by a Van de Graaff neutron source, will be compared with the standard TRIGA reactor. Future demands on TRIGA or competitive systems for neutron radiography are likely to include the pulsing capability of the reactor, and also the extraction of cold neutron beams and resonance energy beams. Experiments recently performed on the Oregon State TRIGA Reactor provide information in each of these categories. A point of particular current concern is a comparison made between the resonance energy beam intensity extracted from the edge of the TRIGA core and from a slot which penetrated to the center of the TREAT reactor. These results indicate that by using such slots on a TRIGA, resonance energy intensities could be extracted that are much higher than previously predicted. (author)

Material Accounting and Management Control Weaknesses in the Defense Agencies' FYs 1995 and 1996 Financial Information

National Research Council Canada - National Science Library

Gimble, Thomas

1997-01-01

The primary audit objective was to summarize Defense agency accounting system weaknesses and related management control program weaknesses identified during audits of defense agencies' FYs 1995 and 1996 financial data...

Neutronics modeling of TRIGA reactor at the University of Utah using agent, KENO6 and MCNP5 codes

International Nuclear Information System (INIS)

Yang, X.; Xiao, S.; Choe, D.; Jevremovic, T.

2010-01-01

The TRIGA reactor at the University of Utah is modelled in 2D using the AGENT state-of-the-art methodology based on the Method of Characteristics (MOC) and R-function theory supporting detailed reactor analysis of reactor geometries of any type. The TRIGA reactor is also modelled using KENO6 and MCNP5 for comparison. The spatial flux and reaction rates distribution are visualized by AGENT graphics support. All methodologies are in use in to study the effect of different fuel configurations in developing practical educational exercises for students studying reactor physics. At the University of Utah we train graduate and undergraduate students in obtaining the Nuclear Regulatory Commission license in operating the TRIGA reactor. The computational models as developed are in support of these extensive training classes and in helping students visualize the reactor core characteristics in regard to neutron transport under various operational conditions. Additionally, the TRIGA reactor is under the consideration for power uprate; this fleet of computational tools once benchmarked against real measurements will provide us with validated 3D simulation models for simulating operating conditions of TRIGA. (author)

JOYO MK-II core characteristics database

International Nuclear Information System (INIS)

Ohkawachi, Yasushi; Maeda, Shigetaka; Sekine, Takashi; Aoyama, Takafumi

2003-04-01

The 'JOYO' MK-II core characteristics database was compiled and published in 1998. Comments and requests from many users led to the creation of a revised edition. The revisions include changes to the MAGI calculation code system to use the 70 group JFS-3-J3.2 constant set processed from the JENDL-3.2 library. Total control rod worth, reactor kinetic parameters and the MK-II core performance test results were included per user's requests. The core characteristics obtained from the 32 nd to 35 th operational cycles, which were conducted in the MK-III transition core, were newly added in this revised version. The MK-II core management data and core characteristics data were recorded to CD-ROM for user convenience. The Configuration Data' include the core arrangement and refueling record for each operational cycle. The 'Subassembly Library Data' include the atomic number density, neutron fluence, burn-up, integral power of 362 driver fuel subassemblies and 69 irradiation test subassemblies. The 'Output Data' contain the calculated neutron flux, gamma flux, power density, linear heat rate, coolant and fuel temperature distribution of all the fuel subassemblies at the beginning and end of each operational cycle. The 'Core Characteristics Data' include the measured excess reactivity, control rod worth calibration curve, and reactivity coefficients of temperature, power and burn-up. (author)

Achieving RCRA compliance in DOE defense waste management operations

International Nuclear Information System (INIS)

Frankhauser, W.A.; Shepard, M.D.

1989-01-01

The U.S. Department of Energy (DOE) generates significant volumes of radioactive mixed waste (RMW) through its defense-related activities. Defense RMW is co-regulated by DOE and the U.S. Environmental Protection Agency/State agencies in accordance with requirements of the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). This paper highlights some of the problems encountered in co-regulation and discusses achievements of the defense waste management program in integrating RCRA requirements into RMW operations. Defense waste sites are planning facility modifications and major new construction projects to develop treatment, storage and disposal capacity for existing RMW inventories and projected needs

75 FR 65462 - Renewal of Department of Defense Federal Advisory Committee; Department of Defense Military...

Science.gov (United States)

2010-10-25

... Committee; Department of Defense Military Family Readiness Council AGENCY: Department of Defense (DoD... renewing the charter for the Department of Defense Military Family Readiness Council (hereafter referred to... requirements for the support of military family readiness by the Department of Defense; and (c) evaluate and...

TRIGA 14 MW spent fuel shipment to USA

International Nuclear Information System (INIS)

Toma, C.; Barbos, D.; Preda, M.; Covaci, St.; Ciocanescu, M.

2008-01-01

Romania has begun to convert Pitesti TRIGA 14 MW reactor having HEU fuel in its first loading and has agreed to complete conversion of the reactor to LEU fuel by May 12, 2006. Thus it became possible to benefit of US policy as set forth in the Record of Decision (ROD) issued by the Department of Energy (DOE ) on May 13 , 1996 directed for acceptance, management and disposition of the Authorized Material which has been discharged from the foreign research reactors. Consequently, United States, DOE Idaho Operations Office and Institute for Nuclear Research at Pitesti, Romania have mutually agreed the terms and conditions set forth in a contract applicable to the receipt of the Authorized Material. Irradiated and spent nuclear fuel rods from TRIGA reactor containing uranium enriched in the United States that have met the requirements set forth in the Environmental Impact Statement and the ROD have been designated as 'Authorized Material' and transferred to Idaho National Engineering and Environmental Laboratory (INEEL)- USA during the summer of 1999 in a joint shipment. 267 TRIGA spent fuel rods loaded in a Legal Weight Truck Shipping Cask belonging to the NAC International have been transported through an overland truck route from Pitesti, Romania to Koper, Slovenia and from there it was shipped to USA. The paper has the following contents: 1.Introduction; 2.Fuel rods selection; 3.Fuel rods characterization; 4.Evaluation of TRIGA fuel in wet storage; 5.Fuel rods transfer from TRIGA pool to the transport cask; 6.Supporting documentation for transfer approval; 7. Conclusions. In conclusion one is stressed that, on site fuel evaluation process evidenced the existence of very good running and storage conditions in reactor pool during reactor operation and fuel storage. Only one fuel rod had to be packaged prior to placement in the shipping cask because of damaged cladding during negligent handling

Acquisition: Acquisition of Targets at the Missile Defense Agency

National Research Council Canada - National Science Library

Ugone, Mary L; Meling, John E; James, Harold C; Haynes, Christine L; Heller, Brad M; Pomietto, Kenneth M; Bobbio, Jaime; Chang, Bill; Pugh, Jacqueline

2005-01-01

.... This audit was performed in response to allegations made to the DoD Hotline in March 2003. This report addresses 10 allegations about the effectiveness of the process that the Missile Defense Agency used to manage and acquire targets...

Fission product release from TRIGA-LEU reactor fuels

International Nuclear Information System (INIS)

Baldwin, N.L.; Foushee, F.C.; Greenwood, J.S.

1980-01-01

Due to present international concerns over nuclear proliferation, TRIGA reactor fuels will utilize only low-enriched uranium (LEU) (enrichment <20%). This requires increased total uranium loading per unit volume of fuel in order to maintain the appropriate fissile loading. Tests were conducted to determine the fractional release of gaseous and metallic fission products from typical uranium-zirconium hydride TRIGA fuels containing up to 45 wt-% uranium. These tests, performed in late 1977 and early 1978, were similar to those conducted earlier on TRIGA fuels with 8.5 wt-% U. Fission gas release measurements were made on prototypic specimens from room temperature to 1100 deg. C in the TRIGA King Furnace Facility. The fuel specimens were irradiated in the TRIGA reactor at a low power level. The fractional releases of the gaseous nuclides of krypton and xenon were measured under steady-state operating conditions. Clean helium was used to sweep the fission gases released during irradiation from the furnace into a standard gas collection trap for gamma counting. The results of these tests on TRIGA-LEU fuel agree well with data from the similar, earlier tests on TRIGA fuel. The correlation used to calculate the release of fission products from 8.5 wt-% U TRIGA fuel applies equally well for U contents up to 45 wt-%. (author)

Startup of Torrey Pines Mark III and Puerto Rico Nuclear Center reactors with TRIGA-FLIP fuel

Energy Technology Data Exchange (ETDEWEB)

Chesworth, R. H. [Gulf E and ES, San Diego, CA (United States)

1972-07-01

This paper discusses the characteristics of TRIGA FLIP cores in two different geometries: the normal TRIGA single-rod geometry as typified by the installation in the Torrey Pines Mark III reactor; and the four-rod cluster geometry as typified by the conversion core installed in the Puerto Rico Nuclear Center reactor at Mayaguez. In both reactors the fuel is 8-1/2 wt % uranium, 70% enriched in U-235. The hydrogen to zirconium atom ratio is 1.5 to 1.65 and the cladding material is stainless steel. The basic neutronic characteristics of the fuel in both reactor installations are briefly discussed.

Type 1 cannabinoid receptor mapping with [18F]MK-9470 PET in the rat brain after quinolinic acid lesion: a comparison to dopamine receptors and glucose metabolism

International Nuclear Information System (INIS)

Casteels, Cindy; Martinez, Emili; Camon, Lluisa; Vera, Nuria de; Planas, Anna M.; Bormans, Guy; Baekelandt, Veerle; Laere, Koen van

2010-01-01

Several lines of evidence imply early alterations in metabolic, dopaminergic and endocannabinoid neurotransmission in Huntington's disease (HD). Using [ 18 F]MK-9470 and small animal PET, we investigated cerebral changes in type 1 cannabinoid (CB 1 ) receptor binding in the quinolinic acid (QA) rat model of HD in relation to glucose metabolism, dopamine D 2 receptor availability and amphetamine-induced turning behaviour. Twenty-one Wistar rats (11 QA and 10 shams) were investigated. Small animal PET acquisitions were conducted on a Focus 220 with approximately 18 MBq of [ 18 F]MK-9470, [ 18 F]FDG and [ 11 C]raclopride. Relative glucose metabolism and parametric CB 1 receptor and D 2 binding images were anatomically standardized to Paxinos space and analysed voxel-wise using Statistical Parametric Mapping (SPM2). In the QA model, [ 18 F]MK-9470 uptake, glucose metabolism and D 2 receptor binding were reduced in the ipsilateral caudate-putamen by 7, 35 and 77%, respectively (all p -5 ), while an increase for these markers was observed on the contralateral side (>5%, all p -4 ). [ 18 F]MK-9470 binding was also increased in the cerebellum (p = 2.10 -5 ), where it was inversely correlated to the number of ipsiversive turnings (p = 7.10 -6 ), suggesting that CB 1 receptor upregulation in the cerebellum is related to a better functional outcome. Additionally, glucose metabolism was relatively increased in the contralateral hippocampus, thalamus and sensorimotor cortex (p = 1.10 -6 ). These data point to in vivo changes in endocannabinoid transmission, specifically for CB 1 receptors in the QA model, with involvement of the caudate-putamen, but also distant regions of the motor circuitry, including the cerebellum. These data also indicate the occurrence of functional plasticity on metabolism, D 2 and CB 1 neurotransmission in the contralateral hemisphere. (orig.)

Study on the Mission, Roles, and Structure of the Missile Defense Agency (MDA)

National Research Council Canada - National Science Library

Welch, Larry D; Briggs, David L; Bleach, R. D; Canavan, G. H; Clark-Sestak, S. L; Constantine, R. W; Cook, C. W; Fries, M. S; Frost, D. E; Graham, D. R; Keane, D. J; Kramer, S. D; Major, P. L; Primmerman, C. A; Ruddy, J. M; Schneiter, G. R; Seng, J. M; Stein, R. M; Weiner, S. D; Williams, J. D

2008-01-01

...) was tasked by the Department of Defense to carry out an independent study to examine and make recommendations with respect to the long-term missions, roles, and structure of the Missile Defense Agency (MDA...

Atomic and magnetic structure of MnF3

International Nuclear Information System (INIS)

Hunter, B.A.; Kennedy, B.J.; Vogt, T.

2003-01-01

Full text: The magnetic and atomic structure of MnF 3 has been determined from 4K to 300K using neutron powder diffraction. The MnF 3 compound is the archetypical Mn-based colossal magnetoresistive compound. A Neel temperature of approximately 40K was observed from the temperature variation of the magnetic moment. Below the Neel temperature a large negative thermal expansion was observed, in striking similarity to other Mn-based colossal magnetoresistive compounds. The variation in structure is discussed in relation to other Mn-based compounds, particularly as this compound cannot support charge ordering

Fundamental approach to TRIGA steady-state thermal-hydraulic CHF analysis

International Nuclear Information System (INIS)

Feldman, E.E.

2008-01-01

Methods are investigated for predicting the power at which critical heat flux (CHF) occurs in TRIGA reactors that rely on natural convection for primary flow. For a representative TRIGA reactor, two sets of functions are created. For the first set, the General Atomics STAT code and the more widely-used RELAP5-3D code are each employed to obtain reactor flow rate as a function of power. For the second set, the Bernath correlation, the 2006 Groeneveld table, the Hall and Mudawar outlet correlation, and each of the four PG-CHF correlations for rod bundles are used to predict the power at which CHF occurs as a function of channel flow rate. The two sets of functions are combined to yield predictions of the power at which CHF occurs in the reactor. A combination of the RELAP5-3D code and the 2006 Groeneveld table predicts 67% more CHF power than does a combination of the STAT code and the Bernath correlation. (author)

Status of the TRIGA shipments to the INEEL from Asia

International Nuclear Information System (INIS)

Tyacke, M.; George, W.; Petrasek, A.; Stump, R.C.; Patterson, J.

1997-01-01

This paper will report on preparations being made for returning Training, Research, Isotope, General Atomics (TRIGA) foreign research reactor (FRR) spent fuel from South Korea and Indonesia to the Idaho National Engineering and Environmental Laboratory (INEEL). The roles of US Department of Energy, INEEL, and NAC International in implementing a safe shipment are provided. Special preparations necessitated by making a shipment through a west coast port of the US to the INEEL will be explained. The institutional planning and actions needed to meet the unique political and operational environment for making a shipment from Asia to INEEL will be discussed. Facility preparation at both the INEEL and the FRRs is discussed. Cask analysis needed to properly characterize the various TRIGA configurations, compositions, and enrichments is discussed. Shipping preparations will include an explanation of the integrated team of spent fuel transportation specialists, and shipping resources needed to retrieve the fuel from foreign research reactor sites and deliver it to the INEEL

International Atomic Energy Agency and Malaysia

International Nuclear Information System (INIS)

Abd Rahim Mohd Nor

1985-01-01

A review on IAEA (International Atomic Energy Agency) and its relation with Malaysia is given. This article also discusses the background history of IAEA, its organization and functions in the field of nuclear energy

4. TRIGA owners' conference. Papers and abstracts

International Nuclear Information System (INIS)

1976-01-01

The Conference covers the following aspects of TRIGA reactors operation: fuel utilization; TRIGA design and startup tests radiation release and unusual occurrences; operating experience; design of experimental facilities and instruments

Research with Neutrons at the TRIGA Mainz

International Nuclear Information System (INIS)

Hampel, Gabriele

2008-01-01

The TRIGA Mark II reactor at the Institut fuer Kernchemie of the Johannes Gutenberg-Universitaet in Mainz became first critical on August 3, 1965 and is still intensively used for basic research, applied science and educational purposes. Considering the past and future operation schedule and the low burn-up of the fuel elements (∼4 g 235 U/a), the reactor can be operated for at least the next decade taking into account the fresh fuel elements on stock and without changing spent fuels. The operation of the TRIGA Mainz has been extended very recently until the year 2020. The TRIGA Mainz can be operated in the steady state mode with a maximum power of 100 kWth and in the pulse mode with a peak power of 250 MWth. Until now, more than 16600 pulses have been carried out without any fuel failure. For irradiations the TRIGA Mainz has a central experimental tube, three pneumatic transfer systems and a rotary specimen rack with 40 positions which allows the irradiation of 80 samples at the same time. In addition, the TRIGA Mainz includes four horizontal beam ports penetrating the concrete shielding and extending inside the pool towards the reflector. A graphite thermal column provides a source of well-thermalized neutrons suitable for physical research or biological and medical irradiations. Important projects for the future of the TRIGA Mainz are the production of ultracold neutrons (UCN) and experiments with UCN, high precision mass measurements and laser spectroscopy of short-lived fission products (TRIGA-TRAP), the production of radionuclides for fast chemical separations, medical and radiopharmaceutical applications, and the use of the neutron activation analysis for the application in archeometry, solar energy technique, criminalistics and vine analysis. Furthermore, studies are performed to judge if the Boron Neutron Capture Therapy (BNCT) can be applied at the TRIGA Mainz for cancer treatment of liver metastases. Also, the reactor facility is used for the training

Reactor TRIGA PUSPATI (RTP) spent fuel pool conceptual design

International Nuclear Information System (INIS)

Mohd Fazli Zakaria; Tonny Lanyau; Ahmad Nabil Ab Rahim

2010-01-01

Reactor TRIGA PUSPATI (RTP) is the one and only research reactor in Malaysia that has been safely operated and maintained since 1982. In order to enhance technical capabilities and competencies especially in nuclear reactor engineering a feasibility study on RTP power upgrading was proposed to serve future needs for advance nuclear science and technology in the country with the capability of designing and develop reactor system. The need of a Spent Fuel Pool begins with the discharge of spent fuel elements from RTP for temporary storage that includes all activities related to the storage of fuel until it is either sent for reprocessed or sent for final disposal. To support RTP power upgrading there will be major RTP systems replacement such as reactor components and a new temporary storage pool for fuel elements. The spent fuel pool is needed for temporarily store the irradiated fuel elements to accommodate a new reactor core structure. Spent fuel management has always been one of the most important stages in the nuclear fuel cycle and considered among the most common problems to all countries with nuclear reactors. The output of this paper will provide sufficient information to show the Spent Fuel Pool can be design and build with the adequate and reasonable safety assurance to support newly upgraded TRIGA PUSPATI TRIGA Research Reactor. (author)

Fundamental approach to TRIGA steady-state thermal-hydraulic CHF analysis

International Nuclear Information System (INIS)

Feldman, E.

2008-01-01

Methods are investigated for predicting the power at which critical heat flux (CHF) occurs in TRIGA reactors that rely on natural convection for primary flow. For a representative TRIGA reactor, two sets of functions are created. For the first set, the General Atomics STAT code and the more widely-used RELAP5-3D code are each employed to obtain reactor flow rate as a function of power. For the second set, the Bernath correlation, the 2006 Groeneveld table, the Hall and Mudawar outlet correlation, and each of the four PG-CHF correlations for rod bundles are used to predict the power at which CHF occurs as a function of channel flow rate. The two sets of functions are combined to yield predictions of the power at which CHF occurs in the reactor. A combination of the RELAP5-3D code and the 2006 Groeneveld table predicts 67% more CHF power than does a combination of the STAT code and the Bernath correlation. Replacing the 2006 Groeneveld table with the Bernath CHF correlation (while using the RELAP5-3D code flow solution) causes the increase to be 23% instead of 67%. Additional RELAP5-3D flow-versus-power solutions obtained from Reference 1 and presented in Appendix B for four specific TRIGA reactors further demonstrates that the Bernath correlation predicts CHF to occur at considerably lower power levels than does the 2006 Groeneveld table. Because of the lack of measured CHF data in the region of interest to TRIGA reactors, none of the CHF correlations considered can be assumed to provide the definitive CHF power. It is recommended, however, to compare the power levels of the potential limiting rods with the power levels at which the Bernath and 2006 Groeneveld CHF correlations predict CHF to occur

On the International Atomic Energy Agency

Energy Technology Data Exchange (ETDEWEB)

Eklund, S [International Atomic Energy Agency, Vienna (Austria)

1963-07-15

The main concepts motivating the decision to establish an international agency for peaceful uses of atomic energy are presented in the paper. They consists of: 1) co-ordination in the fields of safety field, legal liability and safeguards; 2) ensuring that scientific and technical data are made freely accessible on a worldwide scale and 3) assisting the developing countries in benefiting from this new science and technology and use the atomic energy for economic and social development

International Nuclear Information System. 1988-2002. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2002-08-01

This catalogue lists all sales publications and products of the International Atomic Energy Agency dealing with the International Nuclear Information System (INIS), and issued during the period 1 January 1990 - 31 July 2002. Most publications are issued in English, though some are also available in other languages. This is noted as E for English, F for French, G for German, R for Russian and S for Spanish before the relevant ISBN number. Some INIS Reference Series publications are available in electronic form from the INIS Clearinghouse. For more details on the INIS publications programme, please visit the INIS web site mentioned above

Single d-metal atoms on F(s) and F(s+) defects of MgO(001): a theoretical study across the periodic table.

Science.gov (United States)

Neyman, Konstantin M; Inntam, Chan; Matveev, Alexei V; Nasluzov, Vladimir A; Rösch, Notker

2005-08-24

Single d-metal atoms on oxygen defects F(s) and F(s+) of the MgO(001) surface were studied theoretically. We employed an accurate density functional method combined with cluster models, embedded in an elastic polarizable environment, and we applied two gradient-corrected exchange-correlation functionals. In this way, we quantified how 17 metal atoms from groups 6-11 of the periodic table (Cu, Ag, Au; Ni, Pd, Pt; Co, Rh, Ir; Fe, Ru, Os; Mn, Re; and Cr, Mo, W) interact with terrace sites of MgO. We found bonding with F(s) and F(s+) defects to be in general stronger than that with O2- sites, except for Mn-, Re-, and Fe/F(s) complexes. In M/F(s) systems, electron density is accumulated on the metal center in a notable fashion. The binding energy on both kinds of O defects increases from 3d- to 4d- to 5d-atoms of a given group, at variance with the binding energy trend established earlier for the M/O2- complexes, 4d period, group 7 atoms are slightly destabilized compared to their group 6 congeners in both the F(s) and F(s+) complexes; for later transition elements, the binding energy increases gradually up to group 10 and finally decreases again in group 11, most strongly on the F(s) site. This trend is governed by the negative charge on the adsorbed atoms. We discuss implications for an experimental detection of metal atoms on oxide supports based on computed core-level energies.

10. European TRIGA users conference. Papers and abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-07-01

The Tenth European TRIGA Users Conference was held in Vienna, September 14-16, 1988 under the sponsorship of the Atominstitut. The main areas of discussions were: Reactor operation and maintenance experiences; New developments and improvements of TRIGA components and systems, including instrumentation; Fuel and fuel management; Safety aspects, licensing and radiation protection; Experiments with TRIGA reactors; Radiochemistry, radioisotope production and NAA; and Reactor physics.

10. European TRIGA users conference. Papers and abstracts

International Nuclear Information System (INIS)

1988-01-01

The Tenth European TRIGA Users Conference was held in Vienna, September 14-16, 1988 under the sponsorship of the Atominstitut. The main areas of discussions were: Reactor operation and maintenance experiences; New developments and improvements of TRIGA components and systems, including instrumentation; Fuel and fuel management; Safety aspects, licensing and radiation protection; Experiments with TRIGA reactors; Radiochemistry, radioisotope production and NAA; and Reactor physics

TRIGA Mark II Ljubljana - spent fuel transportation

International Nuclear Information System (INIS)

Ravnik, M.; Dimic, V.

2008-01-01

The most important activity in 1999 was shipment of the spent fuel elements back to the United States for final disposal. This activity started already in 1998 with some governmental support. In July 1999 all spent fuel elements (219 pieces) from the TRIGA research reactor in Ljubljana were shipped back to the United Stated by the ship from the port Koper in Slovenia. At the same time shipment of the spent fuel from the research reactor in Pitesti, Romania, and the research reactor in Rome, Italy, was conducted. During the loading the radiation exposure to the workers was rather low. The loading and shipment of the spent nuclear fuel went very smoothly and according the accepted time table. During the last two years the TRIGA research reactor in Ljubljana has been in operation about 1100 hours per year and without any undesired shut-down. (authors)

The International Atomic Energy Agency's safeguards system

International Nuclear Information System (INIS)

Wagner, W.

2000-01-01

A system of international safeguards has been established to provide assurance that nuclear materials in civilian use are not diverted from their peaceful purpose. The safeguards system is administered by the International Atomic Energy Agency/Department of Safeguards and devolves from treaties and other international agreements. Inspectors from the Agency verify reports from States about nuclear facilities by audits, observation, and measurements. (author)

Mr Nissim Dahan, MK, Minister of Health, Israel, at the ATLAS exhibition

CERN Multimedia

Laurent Guiraud

2001-01-01

Photo 01: L. to r.:Dr Jim Allaby, Dr Peter Jenni, Prof. Bracha Regev, Chief Scientist, Ministry of Health, Mr Nissim Dahan, MK, Minister of Health, Dr Boaz Lev, Director General, Ministry of Health, Dr Hans F. Hoffmann and Dr Georges Mikenberg. Photo 02: Mr Nissim Dahan, MK, Minister of Health, Israel, signing the Guest Book.

Accounting Procedures and Controls Over Financial Data Supporting Selected Other Defense Organizations

National Research Council Canada - National Science Library

2000-01-01

The DoD Agency-Wide financial statements include a reporting entity entitled "Other Defense Organizations," which represents a consolidation of financial information from various Defense organizations...

[2. European] TRIGA owners' conference. Papers and abstracts

International Nuclear Information System (INIS)

1972-01-01

The Second European TRIGA Owners' Conference was held in Pavia, Italy, September 1972. The meeting was organized by the University of Pavia Applied Nuclear Energy Laboratory (L.E.N.A.). Sixty-two attendees representing 12 TRIGA reactor centers in Europe, South America, and the United States were present at the Conference. The main areas of discussions were: Reactor operation and maintenance experience; Research programs and TRIGA technology development

[2. European] TRIGA owners' conference. Papers and abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

1972-07-01

The Second European TRIGA Owners' Conference was held in Pavia, Italy, September 1972. The meeting was organized by the University of Pavia Applied Nuclear Energy Laboratory (L.E.N.A.). Sixty-two attendees representing 12 TRIGA reactor centers in Europe, South America, and the United States were present at the Conference. The main areas of discussions were: Reactor operation and maintenance experience; Research programs and TRIGA technology development.

The research reactor TRIGA Mainz

International Nuclear Information System (INIS)

Hampel, G.; Eberhardt, K.; Trautmann, N.

2006-01-01

The TRIGA Mark II reactor at the Institut fuer Kernchemie became first critical on August 3 rd , 1965. It can be operated in the steady state mode with a maximum power of 100 kWth and in the pulse mode with a peak power of 250 MWth. A survey of the research programmes performed at the TRIGA Mainz is given covering applications in basic research as well as applied science in nuclear chemistry and nuclear physics. Furthermore, the reactor is used for neutron activation analysis and for education and training of scientists, teachers, students and technical personal. Important projects for the future of the TRIGA Mainz are the UCN (ultra cold neutrons) experiment, fast chemical separation, medical applications and the use of the NAA as well as the use of the reactor facility for the training of students in the fields of nuclear chemistry, nuclear physics and radiation protection. Taking into account the past and future operation schedule and the typically low burn-up of TRIGA fuel elements (∝4 g U-235/a), the reactor can be operated for at least the next decade taking into account the fresh fuel elements on stock and without changing spent fuels. (orig.)

TRIGA update and modification

Energy Technology Data Exchange (ETDEWEB)

Nelson, G W; Seale, R L [University of Arizona (United States)

1974-07-01

The TRIGA originally installed at the University of Arizona in 1958 has been extensively modified. A Mark III console, rack-and-pinion regulating and shim control rods equipped with fuel-followers, a pneumatic transient rod, and a modern bridge structure were installed. The original 63 aluminum-clad fuel elements were shipped to the University of Utah in Salt Lake City and 85 partially used stainless-steel clad fuel elements were obtained from General Atomic in San Diego. The transfer and remodelling operation are summarized. A little more than one year of operation following these changes has been completed. Several instrumentation problems have been encountered and will be reported. The calibration of the partially spent fuel elements has been used to generate independent evaluations of prior fuel burnup. Finally, the utility of the reactor facility has been increased by adding a neutron radiography capability and a delayed neutron uranium assay system. (author)

TRIGA reactor owners' seminar. Papers and abstracts

International Nuclear Information System (INIS)

1970-01-01

The TRIGA Reactor Owners' Conference was planned with the aim of bringing together a group of persons interested in the ownership and operation of TRIGA reactors in the hope that an interchange of viewpoints, information, and experience would prove of mutual benefit

Assessment results of the South Korea TRIGA SNF to be shipped to INEEL

International Nuclear Information System (INIS)

Cole, Charles M.; Dirk, Willam J.; Cottam, Russel E.; Paik, Sam T.

1997-01-01

This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination at the Seoul and the Taejon Research Reactor Facilities in South Korea. The examination was required before the SNF would be accepted for transportation and storage at the INEEL. The results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. A description of the examination team training, the examination work plan and examination equipment is also included. This paper also explains the technical basis for the examination and physical condition criteria used to determine what, if any, additional packaging (canning) would be required for transportation and for the receipt and storage of the fuel at the INEEL. This paper delineates the preparation activities prior to the fuel examinations and includes (1) collecting spent fuel data; (2) preparatory work by the Korean Atomic Energy Research Institute (KAERI) for fuel examination: (3) preparation of a radionuclide report, 'Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels' needed to provide input data for transportation and fuel acceptance at the Idaho National Engineering and Environmental Laboratory (INEEL); (4) gathering FRR Facility data; (5) preparation of Appendix A; (6) and coordination between the INEEL and KAERI. Included, are the unanticipated conditions encountered in the unloading of fuel from the dry storage casks in Taejon in preparation for examination, a description of the damaged condition of the fuel removed from the casks, and the apparent cause of the damages. Lessons learned from all the activities are also addressed. A brief description of the preparatory work for the shipment of the spent fuel from Korea to INEEL is included. (author)

Assessment results of the South Korea TRIGA SNF to be shipped to INEEL

International Nuclear Information System (INIS)

Cole, C.M.; Dirk, W.J.; Cottam, R.E.; Paik, S.T.

1997-01-01

This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination at the Seoul and the Taejon Research Reactor Facilities in South Korea. The examination was required before the SNF would be accepted for transportation and storage at the INEEL. The results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. A description of the examination team training, the examination work plan and examination equipment is also included. This paper also explains the technical basis for the examination and physical condition criteria used to determine what, if any, additional packaging would be required for transportation and for the receipt and storage of the fuel at the INEEL. This paper delineates the preparation activities prior to the fuel examinations and includes (1) collecting spent fuel data; (2) preparatory work by the Korean Atomic Energy Research Institute (KAERI) for fuel examination: (3) preparation of a radionuclide report, Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels needed to provide input data for transportation and fuel acceptance at the Idaho National Engineering and Environmental Laboratory (INEEL); (4) gathering FRR Facility data; and (5) coordination between the INEEL and KAERI. Included, are the unanticipated conditions encountered in the unloading of fuel from the dry storage casks in Taejon in preparation for examination, a description of the damaged condition of the fuel removed from the casks, and the apparent cause of the damages. Lessons learned from all the activities are also addressed. A brief description of the preparatory work for the shipment of the spent fuel from Korea to INEEL is included

7. biennial U.S. TRIGA users' conference. Papers and abstracts

International Nuclear Information System (INIS)

1980-01-01

The conference covers the following topics: new developments in the TRIGA system; uses of microprocessors in control and monitoring and measurement of TRIGA performance parameters; safeguards, emergency planning, reactor standards; research facilities, fuel tests and calculations; TRIGA reactor parameters: emergency training

77 FR 7613 - Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108

Science.gov (United States)

2012-02-13

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-264; NRC-2012-0026] Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108 AGENCY: Nuclear Regulatory Commission... Facility Operating License No. R-108 (``Application''), which currently authorizes the Dow Chemical Company...

Neutron flux measurement and thermal power calibration of the IAN-R1 TRIGA reactor

Energy Technology Data Exchange (ETDEWEB)

Sarta Fuentes, Jose A.; Castiblanco Bohorquez, Luis A

2008-10-29

The IAN-R1 TRIGA reactor in Colombia was initially fueled with MTR-HEU enriched to 93% U-235, operated since 1965 at 10 kW, and was upgraded to 30 kW in 1980. General Atomics achieved in 1997 the conversion of HEU fuel to LEU fuel TRIGA type, and upgraded the reactor power to 100 kW. Since the IAN-R1 TRIGA reactor was in an extended shutdown during seven years, it was necessary to repeat some results of the commissioning test conducted in 1997. The thermal power calibration was carried out using the calorimetric method. The reactor was operated approximately at 20 kW during 3.5 hours, with manual power corrections since the automatic control system failed and with the forced refrigeration off. During the calorimetric experiment, the pool temperature was measured with a RTD which is installed near to the core. The dates were collected in intervals of 30 minutes. For establishing thermal power reactor, the water temperature versus the running were registered. For a calculated tank volume of 16 m{sup 3}, the tank constant calculated for the IAN-R1 TRIGA reactor is 0.0539 C/kW-hr. The reactor power determined was 19 kW. The core configuration is a rectangular grid plate that holds a combination of 4-rod and 3-rod clusters. The core contains 50 fuel rods with LEU fuel TRIGA (UZr H1.6) type enriched to 19.7%. The radial reflector consists of twenty graphite elements six of which are used for isotope production. The top an bottom reflectors are the cylindrical graphite end reflectors which are installed above and below of the active fuel section in each fuel rod. The spatial dependence of thermal neutron flux was measured axially in the 3-rod clusters 4C, 3D, 5E and in the 4F graphite element. The spatial distribution of the thermal neutron was determined using a self-powered detector and the absolute value of thermal neutron flux was determined by a gold activation detector. The (n, b- ) reaction is applied to determine the relative spatial distribution of thermal

32 CFR 621.1 - Loan of Army/Defense Logistics Agency (DLA) owned property for use at national and State...

Science.gov (United States)

2010-07-01

... 32 National Defense 3 2010-07-01 2010-07-01 true Loan of Army/Defense Logistics Agency (DLA) owned... of Army/Defense Logistics Agency (DLA) owned property for use at national and State conventions. (a... and facilities on loan. (iv) Costs of packaging, packing, transportation and handling from source of...

Neutronic Analysis of the 3 MW TRIGA MARK II Research Reactor, Part I: Monte Carlo Simulation

International Nuclear Information System (INIS)

Huda, M.Q.; Chakrobortty, T.K.; Rahman, M.; Sarker, M.M.; Mahmood, M.S.

2003-05-01

This study deals with the neutronic analysis of the current core configuration of a 3 MW TRIGA MARK II research reactor at Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh and validation of the results by benchmarking with the experimental, operational and available Final Safety Analysis Report (FSAR) values. The three-dimensional continuous-energy Monte Carlo code MCNP4C was used to develop a versatile and accurate full-core model of the TRIGA core. The model represents in detail all components of the core with literally no physical approximation. All fresh fuel and control elements as well as the vicinity of the core were precisely described. Continuous energy cross-section data from ENDF/B-VI and S(α, β) scattering functions from the ENDF/B-V library were used. The validation of the model against benchmark experimental results is presented. The MCNP predictions and the experimentally determined values are found to be in very good agreement, which indicates that the Monte Carlo model is correctly simulating the TRIGA reactor. (author)

Introducing the Brazilian program of technical support to the International Atomic Energy Agency - Department of Safeguards

International Nuclear Information System (INIS)

Vinhas, Laercio A.; Palhares, Lilia C.; Dias, Fabio C.; Khlebnikov, Nikolai

2009-01-01

As an active Member State of the International Atomic Energy Agency (IAEA), Brazil has applied substantial resources in order to maintain the best possible cooperation with the Agency, aiming at a continuous improvement of the effectiveness and efficiency of the safeguards system. Over the last decades a number of projects, involving the participation of high-level Brazilian professionals in the nuclear area, have already been jointly completed. To continue providing this voluntary support to the IAEA Department of Safeguards for research, development and implementation, in 2006 Brazil decided to accept the IAEA's invitation to participate in the IAEA Member States Support Programmes initiative, which currently includes 21 Member States. The Research and Development (R and D) Programme for Nuclear Verification is the IAEA reference in this regard, establishing the high priority needs and describing each recognized departmental project. The Programme is issued every two years. The 'Brazilian Support Programme (BRZ SP)' was established on the basis of a set of administrative procedures titled 'Cooperation Arrangements and Guidelines', agreed between the Brazilian National Nuclear Energy Commission (CNEN) and the IAEA - Department of Safeguards. The scope of the BRZ SP includes: the participation in field tests and the evaluation of state-of-the-art technologies as requested by the IAEA for its safeguards applications; the training of safeguards personnel involved with safeguards implementation at both facility and State levels; laboratorial support in the area of destructive and nondestructive analysis of nuclear materials; the analysis of safeguards issues; information acquisition, analysis and evaluation; and the provision of human resources, such as experts and consultants to work directly with the IAEA Secretariat. The activities agreed under the BRZ SP are not restricted to CNEN staff members. Professionals from other Brazilian organizations may also be involved

77 FR 68155 - The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R-84

Science.gov (United States)

2012-11-15

... Research Institute TRIGA Reactor: Facility Operating License No. R-84 AGENCY: Nuclear Regulatory Commission... considering an application for the renewal of Facility Operating License No. R-84 (Application), which... the renewal of Facility Operating License No. R-84, which currently authorizes the licensee to operate...

Antidepressant Effects of (+)-MK-801 and (-)-MK-801 in the Social Defeat Stress Model

Science.gov (United States)

Yang, Bangkun; Ren, Qian; Ma, Min; Chen, Qian-Xue

2016-01-01

Background: Current data on antidepressant action of the N-methyl-D-aspartate receptor antagonist, (+)-MK-801, is inconsistent. This study was conducted to examine the effects of (+)-MK-801 and its less potent stereoisomer, (-)-MK-801, in the social defeat stress model of depression. Methods: The antidepressant effects of (+)-MK-801 (0.1mg/kg) and (-)-MK-801 (0.1mg/kg) in the social defeat stress model were examined. Results: In the tail suspension and forced swimming tests, both stereoisomers significantly attenuated increased immobility time in susceptible mice. In the sucrose preference test, (+)-MK-801, but not (-)-MK-801, significantly enhanced reduced sucrose consumption 2 or 4 days after a single dose. However, no antianhedonia effects were detected 7 days after a single dose of either stereoisomer. Conclusions: Both stereoisomers of MK-801 induced rapid antidepressant effects in the social defeat stress model, although neither produced a long-lasting effect (7 days). PMID:27608811

TRIGA reactor health physics considerations

International Nuclear Information System (INIS)

Johnson, A.G.

1970-01-01

The factors influencing the complexity of a TRIGA health physics program are discussed in details in order to serve as a basis for later consideration of various specific aspects of a typical TRIGA health physics program. The health physics program must be able to provide adequate assistance, control, and safety for individuals ranging from the inexperienced student to the experienced postgraduate researcher. Some of the major aspects discussed are: effluent release and control; reactor area air monitoring; area monitoring; adjacent facilities monitoring; portable instrumentation, personnel monitoring. TRIGA reactors have not been associated with many significant occurrences in the area of health physics, although some operational occurrences have had health physics implications. One specific occurrence at OSU is described involving the detection of non-fission-product radioactive particulates by the continuous air monitor on the reactor top. The studies of this particular situation indicate that most of the particulate activity is coming from the rotating rack and exhausting to the reactor top through the rotating rack loading tube

Neutronic performance of a 14 MW TRIGA reactor: LEU vs HEU fuel

International Nuclear Information System (INIS)

Bretscher, M.M.; Snelgrove, J.L.; Cornella, R.J.

1983-01-01

A primary objective of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is to develop means for replacing, wherever possible, currently used highly-enriched uranium (HEU) fuel ( 235 U enrichment > 90%) with low-enriched uranium (LEU) fuel ( 235 U enrichment < 20%) without significantly degrading the performance of research and test reactors. The General Atomic Company has developed a low-enriched but high uranium content Er-U-ZrH/sub 1.6/ fuel to enable the conversion of TRIGA reactors (and others) from HEU to LEU. One possible application is to the water-moderated 14 MW TRIGA Steady State Reactor (SSR) at the Romanian Institute for Nuclear Power Reactors. The work reported here was undertaken for the purpose of comparing the neutronic performance of the SSR for HEU fuel with that for LEU fuel. In order to make these relative comparisons as valid as possible, identical methods and models were used for the neutronic calculations

Possibilities of miniaturizing the TRIGA-reactor

International Nuclear Information System (INIS)

Bobleter, O.; Brunner, P.; Schachner, H.

1976-01-01

It is proposed to decrease the depth of the TRIGA pool in cases where the construction of the normal-sized pool causes difficulty. The loss of shielding in the vertical direction will be compensated by lead and lead glass. The influence of these changes in design on the reactor components (control rods, instrumentation, neutron beam tubes, pneumatic system, etc.) is discussed. The experimental part of the work concerns the irradiation of lead glasses with varying contents of lead and cerium, which was carried out in the pool at different distances from the TRIGA core. The advantages of a possible reduction in size of the TRIGA reactor by using lead and lead glass as shielding are compared with the main disadvantages of these materials (darkening of the glass and high prices). (author)

United States Department of Defense: Agency Financial Report Fiscal Year 2014

Science.gov (United States)

2014-01-01

associated environmental costs using two methods: physical capacity for operating landfills and life expectancy in years for all other assets. The...construction, and rehabilitation projects on inland waterways. The BFS manages and invests for the Trust Fund. Defense Commissary Agency Surcharge

14. U.S. TRIGA users conference. Final program and summary of papers

International Nuclear Information System (INIS)

1994-01-01

The following papers were presented at the Conference: Early Development and Use of the TRIGA Reactor; Results of the MCNP Analysis of 20/20 LEU Fuel for the Oregon State University TRIGA Reactor; Upgradeable 2MW TRIGA Reactor Design for the Morocco Nuclear Energy Center McClellan Nuclear Radiation Center TRIGA Reactor: Four Years of Operations

14. U.S. TRIGA users conference. Final program and summary of papers

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-07-01

The following papers were presented at the Conference: Early Development and Use of the TRIGA Reactor; Results of the MCNP Analysis of 20/20 LEU Fuel for the Oregon State University TRIGA Reactor; Upgradeable 2MW TRIGA Reactor Design for the Morocco Nuclear Energy Center McClellan Nuclear Radiation Center TRIGA Reactor: Four Years of Operations.

TREAT MK III Loop Thermoelastoplastic Stress Analysis for the L03 Experiment

Energy Technology Data Exchange (ETDEWEB)

Kennedy, James M.

1981-03-01

The STRAW code was used to analyze the static response of a TREAT MK III loop subjected to thermal and mechanical loadings arising from an accident situation for the purpose of determining the defiections and stresses. This analysis provides safety support for the L03 reactivity accident study. The analysis was subdivided into two tasks: (1) an analysis of a flow blockage accident (Cases A and B), where all the energy is assumed deposited in the test leg, resulting in a temperature increase from 530°F to 1720°F, with a small internal pressure throughout the loop and (2) an analysis of a second flow blockage accident (Cases C and D), where again, all the energy is assumed to he deposited in the test leg, resulting in a temperature rise from 530°F to 1845°F, with a small internal pressure throughout the loop. The purpose of these two tasks was to determine if loop failure can occur with the thermal differential across the pump and test legs. Also of interest is whether an undesirable amount of loop lateral deflection will be caused by the thermal differential. A two dimensional analysis of the TREAT MK III loop was performed. The analysis accounted for material nonlinearities, both as a function of temperature and stress, and geometric nonlinearities arising from large deflections. Straight beam elements with annular cross sections were used to model the loop. The analyses show that the maximum strains are less than 21% of their failure strains for all subcases of Cases A and B. For all subcases of cases C and D, the maximum strains are less than 53% of their failure strains. The failure strain is 27.9% for the material at 530°F, 38.1% at 1720°F and 17.8% at 1845°F. Large lateral deflections are observed when the loop is not constrained except at its clamped support--as much as 8.6 inches. However, by accounting for the constraint of the concrete biological shield, the maximum lateral deflection was reduced to less than 0.05 inches at the points of concern.

Operation and maintenance of 1MW PUSPATI TRIGA reactor

International Nuclear Information System (INIS)

Adnan Bokhari; Mohammad Suhaimi Kassim

2006-01-01

The Malaysian Research Reactor, Reactor TRIGA PUSPATI (RTP) has been successfully operated for 22 years for various experiments. Since its commissioning in June 1982 until December 2004, the 1MW pool-type reactor has accumulated more than 21143 hours of operation, corresponding to cumulative thermal energy release of about 14083 MW-hours. The reactor is currently in operation and normally operates on demand, which is normally up to 6 hours a day. Presently the reactor core is made up of standard TRIAGA fuel element consists of 8.5 wt%, 12 wt% and 20 wt% types; 20%-enriched and stainless steel clad. Several measures such as routine preventive maintenance and improving the reactor support systems have been taken toward achieving this long successful operation. Besides normal routine utilization like other TRIGA reactors, new strategies are implemented for effective increase in utilization. (author)

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

International Nuclear Information System (INIS)

Radulesscu, G.; Tang, J.S.

2000-01-01

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M andO [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M andO 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M andQ 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M andO 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable canisters. The intended use of this

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

Energy Technology Data Exchange (ETDEWEB)

G. Radulesscu; J.S. Tang

2000-06-07

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M&O 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M&Q 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M&O 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable

Research activities at the TRIGA Mainz

International Nuclear Information System (INIS)

Eberhardt, K.; Trautmann, N.

2002-01-01

The TRIGA Mark II reactor of the Mainz University became first critical on August 3, 1965. It can be operated in the steady state mode with a maximum power of 100 kW and in the pulse mode with a peak power of 250 MW. The TRIGA Mainz is mainly used for neutron activation analysis, isotope production, basic research in nuclear chemistry and nuclear physics as well as for education and training

4. European conference of TRIGA users. Papers and abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

1976-07-01

The main topics of the Conference are: TRIGA operating experience special experimental and maintenance experience; activation analysis and isotope production; research programs; special instrumentation testing and other TRIGA specific topics.

4. European conference of TRIGA users. Papers and abstracts

International Nuclear Information System (INIS)

1976-01-01

The main topics of the Conference are: TRIGA operating experience special experimental and maintenance experience; activation analysis and isotope production; research programs; special instrumentation testing and other TRIGA specific topics

Analysis of gamma heating at TRIGA mark reactor core Bandung using plate type fuel

International Nuclear Information System (INIS)

Setiyanto; Tukiran Surbakti

2016-01-01

In accordance with the discontinuation of TRIGA fuel element production by its producer, the operation of all TRIGA type reactor of at all over the word will be disturbed, as well as TRIGA reactor in Bandung. In order to support the continuous operation of Bandung TRIGA reactor, a study on utilization of fuel plate mode, as used at RSG-GAS reactor, to replace the cylindrical model has been done. Various assessments have been done, including core design calculation and its safety aspects. Based on the neutronic calculation, utilization of fuel plate shows that Bandung TRIGA reactor can be operated by 20 fuel elements only. Compared with the original core, the new reactor core configuration is smaller and it results in some empty space that can be used for in-core irradiation facilities. Due to the existing of in-core irradiation facilities, the gamma heating value became a new factor that should be evaluated for safety analysis. For this reason, the gamma heating for TRIGA Bandung reactor using fuel plate was calculated by Gamset computer code. The calculations based on linear attenuation equations, line sources and gamma propagation on space. Calculations were also done for reflector positions (Lazy Susan irradiation facilities) and central irradiation position (CIP), especially for any material samples. The calculation results show that gamma heating for CIP is significantly important (0.87 W/g), but very low value for Lazy Susan position (lest then 0.11 W/g). Based on this results, it can be concluded that the utilization of CIP as irradiation facilities need to consider of gamma heating as data for safety analysis report. (author)

Atoms for peace - the work of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Daglish, J.

1984-01-01

The article deals with the International Atomic Energy Agency (IAEA), which is situated in Vienna. The aims of the IAEA and its work are described. The safeguards system; promotional work; technical cooperation programme; and nuclear safety work concerned with basic safety standards for radiation protection; are all discussed. (U.K.)

Forensic INAA of bullet-lead and shotshell-pellet evidence specimens with a TRIGA reactor

International Nuclear Information System (INIS)

Guinn, Vincent P.

1988-01-01

This paper has been published earlier, in the references cited. The main purpose of this paper is to acquaint interested TRIGA reactor groups with the main features of the Forensic INAA of BL and SSP evidence specimens - and to recommend that they consider acquiring the necessary expertise and then provide such analysis services to law enforcement agencies, public defenders, and defence attorneys in their respective areas

Extension of TRIGA reactor capabilities

International Nuclear Information System (INIS)

Gietzen, A.J.

1980-01-01

The first TRIGA reactor went into operation at 10 kW about 22 years ago. Since that time 55 TRIGAs have been put into operation including steady-state powers up to 14,000 kW and pulsing reactors that pulse to 20,000,000 kW. Five more are under construction and a proposal will soon be submitted for a reactor of 25,000 kW. Along with these increases in power levels (and the corresponding fluxes) the experimental facilities have also been expanded. In addition to the installation of new TRIGA reactors with enhanced capabilities many of the older reactors have been modified and upgraded. Also, a number of reactors originally fueled with plate fuel were converted to TRIGA fuel to take advantage of the improved technical and safety characteristics, including the ability for pulsed operation. In order to accommodate increased power and performance the fuel has undergone considerable evolution. Most of the changes have been in the geometry, enrichment and cladding material. However, more recently further development on the UZrH alloy has been carried out to extend the uranium content up to 45% by weight. This increased U content is necessary to allow the use of less than 20% enrichment in the higher powered reactors while maintaining longer core lifetime. The instrumentation and control system has undergone remarkable improvement as the electronics technology has evolved so rapidly in the last two decades. The information display and the circuitry logic has also undergone improvements for enhanced ease of operation and safety. (author)

Dynamics of TRIGA-3 Salazar Reactor

International Nuclear Information System (INIS)

Gallardo S, L.F.

1990-01-01

The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author)

Presentation of Accrued Annual Leave in the FY 1996 Defense Agency Financial Statements of the Defense Business Operations Fund

National Research Council Canada - National Science Library

1997-01-01

.... We also assessed internal controls and compliance with laws and regulations. As part of that objective, we evaluated how the Defense agencies presented the accrued leave account on the FYs 1994,1995, and 1996 Statements of Financial Position...

Establishment of the Japan Atomic Energy Agency

International Nuclear Information System (INIS)

Okazaki, Toshio

2006-01-01

A goal of the 21. century is for society to pursue 'sustainable economic development and prosperous life by recycling resources', thus rejecting 'development based on the waste of resources'. For Japan, which has limited energy resources, it is important to secure safe, inexpensive, environmentally friendly energy resources having long-term availability. To contribute to long-term energy security and solve global environmental issues, and to create advanced competitive science and technology, the Japan Atomic Energy Agency (JAEA) was established by integrating the Japan Atomic Energy Research Institute (JAERI) and the Japan Nuclear Cycle Development Institute (JNC) in October 2005. JAEA is endeavoring to establish nuclear fuel cycles, to contribute to social improvement through hydrogen production initiated by atomic energy, and to pursue research and development of thermonuclear fusion and quantum beam technology. This paper reviews the main R and D activities of JAEA. The structure of the paper is the following: 1. Introduction; 2. Japan Atomic Energy Agency; 3. Efforts to Commercialize the Fast Reactor Cycle; 4. Monju Progress; 5. Geological Disposal of High-Level Radioactive Waste R and D; 6. High Temperature Gas-Cooled Reactor System R and D; 7. Fusion Research and Development; 8. LWR Spent Fuel Reprocessing Technology; 9. Quantum Beam Technologies; 10. Nuclear Safety Research and Regulatory Applications; 11. Basic Science and Engineering Research; 12. Contribution to the Enhanced International Nonproliferation Regimes; 13. Conclusions. To summarize, JAEA will promote the above R and D activities, addressing the following commitments: - On problems that atomic energy faces, we shall extend technical assistance in response to the government and the industrial sectors. - We shall produce technical options to attain political goals to secure medium to long-term stable energy supplies and to solve global environmental issues. - With the high potentials of atomic

TRIGA Research Reactor Conversion to LEU and Modernization of Safety Related Systems

Energy Technology Data Exchange (ETDEWEB)

Sanda, R. M. [Institute for Nuclear Research Piteşti (SCN-Piteşti), Piteşti (Romania)

2014-08-15

The USA and IAEA proposed an international programme to reduce the enrichment of uranium in research reactors by converting nuclear fuel containing HEU into fuel containing 20% enriched uranium. The Government of Romania joined the programme and actively supported political, scientific, technical and economic actions that led to the conversion of the active area of the 14 MW TRIGA reactor at the Institute for Nuclear Research in Piteşti in May 2006. This confirmed the continuity of the Romanian Government’s non-proliferation policy and their active support of international cooperation. Conversion of the Piteşti research reactor was made possible by completion of milestones in the Research Agreement for Reactor Conversion, a contract signed with the US Department of Energy and Argonne National Laboratory. This agreement provided scientific and technical support and the possibility of delivery of all HEU TRIGA fuel to the United States. Additionally, about 65% of the fresh LEU fuel needed to start the conversion was delivered in the period 1992–1994. Furthermore, conversion was promoted through IAEA Technical Cooperation project ROM/4/024 project funded primarily by the United States that supported technical and scientific efforts and the delivery of the remaining required LEU nuclear fuel to complete the conversion. Nuclear fuel to complete the conversion was made by the French company CERCA with a tripartite contract among the IAEA, CERCA and Romania. The contract was funded by the US Department of Energy with a voluntary contribution by the Romanian Government. The contract stipulated manufacturing and delivery of LEU fuel by CERCA with compliance measures for quality, delivery schedule and safety requirements set by IAEA standards and Romanian legislation. The project was supported by the ongoing technical cooperation, safeguards, legal and procurement assistance of the IAEA, in particular its Department of Nuclear Safety. For Romanian research, the

Dynamics of TRIGA-3 Salazar Reactor.; Dinamica del Reactor TRIGA Mark III del Centro Nuclear de Mexico.

Energy Technology Data Exchange (ETDEWEB)

Gallardo S, L F

1991-12-31

The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author).

Evaluation of the Defense Contract Audit Agency Audit Coverage of Tricare Contracts

National Research Council Canada - National Science Library

Brannin, Patricia

2000-01-01

Our objective was to evaluate the adequacy of the Defense Contract Audit Agency (DCAA) audit coverage of contracts for health care provided under TRICARE and the former Civilian Health Care and Medical Program of the Uniformed Services...

18F in hot atom chemistry and equilibrium chemical kinetics

International Nuclear Information System (INIS)

Root, J.W.; Tomiyoshi, Katsumi; Knickelbein, M.B.

1993-01-01

Superexcited molecules are unusual species that at present can only be investigated using nuclear recoil methods. The thermochemical technique for measuring the excitation energy distributions of superexcited molecules is reviewed and applied to recent studies of CF 3 18 F and C 2 F 5 18 F formed from high energy atomic exchange reactions in CF 4 and C 2 F 6 . The nascent CF 3 18 F and C 2 F 5 18 F range in energy from 1.7 to about 45 eV. The average energies of these products range from 15 to 20 eV. The internal excitation that accompanies these reactions is initially localized near the 18 F bonding site, and the C 2 F 5 18 F decomposition mechanism is non-statistical. Moderated nuclear recoil experiments yield mechanisms and rates for the reactions of thermal 18 F atoms. Under our standard experimental conditions from 3.4 x 10 4 to 3.4 x 10 8 labeled product molecules are available for radioassay. This procedure is free from systematic error and the measurements yield exceptional precision and sensitivity because (1) high energy reactions with the thermally active reagents are suppressed. (2) the host environment is rigorously controlled, and (3) the molecular products from many single atom reactions are directly counted. The limitations of this technique are described and results are presented for the reactions of thermal 18 F atoms with CH 4 and C 2 H 4 . (J.P.N.)

Crucial roles of the protein kinases MK2 and MK3 in a mouse model of glomerulonephritis.

Directory of Open Access Journals (Sweden)

Adam J Guess

Full Text Available Elevated mitogen-activated protein kinase p38 (p38 MAPK signaling has been implicated in various experimental and human glomerulopathies, and its inhibition has proven beneficial in animal models of these diseases. p38 MAPK signaling is partially mediated through MK2 and MK3, two phylogenetically related protein kinases that are its direct substrates. The current study was designed to determine the specific roles of MK2 and MK3 in a mouse model of acute proliferative glomerulonephritis, using mice with disrupted MK2 and/or MK3 genes. We found that the absence of MK3 alone worsened the disease course and increased mortality slightly compared to wild-type mice, whereas the absence of MK2 alone exhibited no significant effect. However, in an MK3-free background, the disease course depended on the presence of MK2 in a gene dosage-dependent manner, with double knock-out mice being most susceptible to disease induction. Histological and renal functional analyses confirmed kidney damage following disease induction. Because the renal stress response plays a crucial role in kidney physiology and disease, we analyzed the stress response pattern in this disease model. We found that renal cortices of diseased mice exhibited a pronounced and specific pattern of expression and/or phosphorylation of stress proteins and other indicators of the stress response (HSPB1, HSPB6, HSPB8, CHOP, eIF2α, partially in a MK2/MK3 genotype-specific manner, and without induction of a general stress response. Similarly, the expression and activation patterns of other protein kinases downstream of p38 MAPK (MNK1, MSK1 depended partially on the MK2/MK3 genotype in this disease model. In conclusion, MK2 and MK3 together play crucial roles in the regulation of the renal stress response and in the development of glomerulonephritis, which can potentially be exploited to develop novel therapeutic approaches to treat glomerular disease.

Neutronics analysis of the proposed 25-MW leu TRIGA Multipurpose Research Reactor

International Nuclear Information System (INIS)

Nurdin, M.; Bretscher, M.M.; Snelgrove, J.L.

1982-01-01

More than two years ago the government of Indonesia announced plans to purchase a research reactor for the Puspiptek Research Center in Serpong Indonesia to be used for isotope production, materials testing, neutron physics measurements, and reactor operator training. Reactors using low-enriched uranium (LEU) plate-type and rod-type fuel elements were considered. This paper deals with the neutronic evaluation of the rod-type 25-MW LEU TRIGA Multipurpose Research Reactor (MPRR) proposed by the General Atomic Company of the United States of America

Environmental performance data in 'Japan Atomic Energy Agency Report 2016'

International Nuclear Information System (INIS)

Suzuki, Yurina; Kanai, Katsuta; Sato, Sadayuki; Tatebe, Kazuaki

2017-03-01

In September, 2016 Japan Atomic Energy Agency (JAEA) published results of environmental activity as a part of 'Japan Atomic Energy Agency Report 2016' concerning the activities of FY 2015 under 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc., by Facilitating Access to Environmental Information, and Other Measures'. This report has been edited to show detailed environmental performance data in FY 2015 as the base of the 'Japan Atomic Energy Agency Report 2016'. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA. (author)

Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Zakaria, Norasalwa; Mustafa, Muhammad Khairul Ariff; Anuar, Abul Adli; Idris, Hairul Nizam; Ba'an, Rohyiza

2014-01-01

Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning of nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future

Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Norasalwa Zakaria; Muhammad Khairul Ariff Mustafa; Abul Adli Anuar; Hairul Nizam Idris; Rohyiza Baan

2013-01-01

Full-text: Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning of nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future. (author)

Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

Energy Technology Data Exchange (ETDEWEB)

Zakaria, Norasalwa, E-mail: norasalwa@nuclearmalaysia.gov.my; Mustafa, Muhammad Khairul Ariff, E-mail: norasalwa@nuclearmalaysia.gov.my; Anuar, Abul Adli, E-mail: norasalwa@nuclearmalaysia.gov.my; Idris, Hairul Nizam, E-mail: norasalwa@nuclearmalaysia.gov.my; Ba' an, Rohyiza, E-mail: norasalwa@nuclearmalaysia.gov.my [Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia)

2014-02-12

Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning of nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future.

7. European conference of TRIGA reactor users. Conference papers

Energy Technology Data Exchange (ETDEWEB)

NONE

1982-07-01

At the Seventh European Conference of TRIGA Users, held in September 1982, in Istanbul, Turkey, the following aspects are discussed: safety aspects of TRIGA reactors; developments and improvements; operating and maintenance experiences; applications; reactor calculations; fuel cycle aspects and research programs.

5. European conference of TRIGA users. Papers and abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

1978-07-01

The main conference topics were: Operation and maintenance experience of the TRIGA reactors; Development of new Low Enrichment Fuels (LEU); Dose assessments noble gas releases; Radiation protection and dosimetry measurements; Research reactors programs and experiments; and Application of TRIGA reactors.

7. European conference of TRIGA reactor users. Conference papers

International Nuclear Information System (INIS)

1982-01-01

At the Seventh European Conference of TRIGA Users, held in September 1982, in Istanbul, Turkey, the following aspects are discussed: safety aspects of TRIGA reactors; developments and improvements; operating and maintenance experiences; applications; reactor calculations; fuel cycle aspects and research programs

5. European conference of TRIGA users. Papers and abstracts

International Nuclear Information System (INIS)

1978-01-01

The main conference topics were: Operation and maintenance experience of the TRIGA reactors; Development of new Low Enrichment Fuels (LEU); Dose assessments noble gas releases; Radiation protection and dosimetry measurements; Research reactors programs and experiments; and Application of TRIGA reactors

Review of dosimetry for the atomic bomb survivors

International Nuclear Information System (INIS)

Kerr, G.D.

1981-01-01

This paper summarizes and discusses results of some 1980-1981 studies of neutron and γ-ray exposure to the atomic bomb survivors by W.E. Loewe and E. Mendelsohn of the Lawrence Livermore National Laboratory, D.C. Kaul and W.H. Scott of Science Applications, Inc., and J.V. Pace of the Oak Ridge National Laboratory. Some other special studies which are now underway to complete the review will also be discussed. The expert assistance of others in these special studies is being supported in part by the US Department of Energy and in part by the US Defense Nuclear Agency

IPR-R1 TRIGA research reactor decommissioning plan

International Nuclear Information System (INIS)

Andrade Grossi, Pablo; Oliveira de Tello, Cledola Cassia; Mesquita, Amir Zacarias

2008-01-01

The International Atomic Energy Agency (IAEA) is concerning to establish or adopt standards of safety for the protection of health, life and property in the development and application of nuclear energy for peaceful purposes. In this way the IAEA recommends that decommissioning planning should be part of all radioactive installation licensing process. There are over 200 research reactors that have either not operated for a considerable period of time and may never return to operation or, are close to permanent shutdown. Many countries do not have a decommissioning policy, and like Brazil not all installations have their decommissioning plan as part of the licensing documentation. Brazil is signatory of Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, but until now there is no decommissioning policy, and specifically for research reactor there is no decommissioning guidelines in the standards. The Nuclear Technology Development Centre (CDTN/CNEN) has a TRIGA Mark I Research Reactor IPR-R1 in operation for 47 years with 3.6% average fuel burn-up. The original power was 100 k W and it is being licensed for 250 k W, and it needs the decommissioning plan as part of the licensing requirements. In the paper it is presented the basis of decommissioning plan, an overview and the end state / final goal of decommissioning activities for the IPR-R1, and the Brazilian ongoing activities about this subject. (author)

Preparation and planning for the replacement of the Oregon State University TRIGA reactor rotary specimen rack assembly

International Nuclear Information System (INIS)

Anderson, T.V.; Dodd, B.; Johnson, A.G.; Carpenter, W.T.

1984-01-01

Recently there have been a number of indications that the rotating rack may be approaching the end of its useful life. In order to benefit from the experience of other reactors who have removed and replaced their rotating racks, General Atomic (GA) was contacted and previous TRIGA Conference proceedings were scanned. It was determined that a number of facilities, had experienced difficulties with their lazy susans and eventually had to replace them. However, most of the written descriptions of this project were not sufficiently detailed to be of great use. The purpose of this paper is to identify some of the more important questions related to the replacement of our rotating rack assembly and OSU's currently proposed solutions, with a view towards soliciting ideas from other members of the TRIGA reactor community

Decontamination and decommissioning project status of the TRIGA mark-2±3 research reactors

International Nuclear Information System (INIS)

Jung, K. J.; Baek, S. T.; Jung, W. S.; Park, S. K.; Jung, K. H.

1999-01-01

TRIGA Mark-II, the first research reactor in Korea, has operated since 1962, and the second one, TRIGA Mark-III since 1972. Both of them had their operation phased out in 1995 due to their lives and operation of the new research reactor, HANARO at the Korea Atomic Energy Research Institute (KAERI) in Taejeon. Decontamination and decommissioning (D and D) project of the TRIGA Mark-II and Mark-III was started in January 1997 and will be completed in December 2002. In the first year of the project, work was performed in preparation of the decommissioning plan, start of the environmental impact assessment and setup licensing procedure and documentation for the project with cooperation of Korea Institute of Nuclear Safety (KINS). In 1998, Hyundai Engineering Company (HEC) is the main contractor to do design and licensing documentation for the D and D of both reactors. British Nuclear Fuels plc (BNFL) is technical assisting partner of HEC. The decommissioning plan document was submitted to the Ministry of Science and Technology (MOST) for the decommissioning license in December 1998, and it expecting to be issued a license at the end of September 1999. The goal of this project is to release the reactor site and buildings as an unrestricted area. This paper summarizes current status and future plan for the D and D project

Decontamination and decommissioning project status of the TRIGA Mark II and III in Korea

International Nuclear Information System (INIS)

Paik, S.T.; Park, S.K.; Chung, K.W.; Chung, U.S.; Jung, K.J.

1999-01-01

TRIGA Mark-II, the first research reactor in Korea, has operated since 1962, and the second one, TRIGA Mark-III since 1972. Both of them had their operation phased out in 1995 due to their lives and operation of the new research reactor, HANARO (High-flux Advanced Neutron Application Reactor) at the Korea Atomic Energy Institute (KAERI) in Taejon. Decontamination and decommissioning (D and D) project of TRIGA Mark-II and Mark-III was started in January 1997 and will be completed in December 2002. The first year of the project, work was performed in preparation of the decommissioning plan, start of the environmental impact assessment and setup licensing procedure and documentation for the project with cooperation of Korea Institute of Nuclear Safety (KINS). Hyundai Engineering Company (HEC) is the main contractor to do design and licensing documentation for the D and D of both reactors. British Nuclear Fuels plc (BNFL) is the technical assisting partner of HEC. The decommissioning plan document was submitted to the Ministry of Since and Technology (MOST) for the decommissioning license in December 1998, and it expecting to be issued a license in mid 1999. The goal of this project is to release the reactor site and buildings as an unrestricted area. This paper summarizes current status and future plan for the D and D project. (author)

TRIGA criticality experiment for testing burn-up calculations

International Nuclear Information System (INIS)

Persic, Andreja; Ravnik, Matjaz; Zagar, Tomaz

1999-01-01

A criticality experiment with partly burned TRIGA fuel is described. 20 wt % enriched standard TRIGA fuel elements initially containing 12 wt % U are used. Their average burn-up is 1.4 MWd. Fuel element burn-up is calculated in 2-D four group diffusion approximation using TRIGLAV code. The burn-up of several fuel elements is also measured by reactivity method. The excess reactivity of several critical and subcritical core configurations is measured. Two core configurations contain the same fuel elements in the same arrangement as were used in the fresh TRIGA fuel criticality experiment performed in 1991. The results of the experiment may be applied for testing the computer codes used for fuel burn-up calculations. (author)

Hope over fear. The establishment of the International Atomic Energy Agency

Energy Technology Data Exchange (ETDEWEB)

Forland, A.

1995-12-01

President Eisenhower`s ``Atoms for Peace`` speech in 1953 started a process that led to the establishment of the International Atomic Energy Agency (IAEA). This study analyses the negotiations of the Statute of the Agency. It focuses on how the Agency`s scope of action regarding safeguards was negotiated. The Statute is seen as a reflection of the dual purpose of the new Agency to promote peaceful uses of nuclear energy, and to control that peaceful nuclear activities receiving IAEA assistance are not diverted to military purposes. On one hand, the countries receiving assistance from the Agency accepted a degree of international control that represented a breakthrough in international relations. On the other hand, many countries strongly resented controls. Consequently, compromises had to be made in the course of the negotiations in order to reach a consensus. Thus, although the IAEA was established as a competent and technical body, the underlying compromises meant that its scope of actions was restricted. 6 refs.

Evaluation Of Fire Safety And Protection At PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Ahmad Nabil Ab Rahim; Alfred Sanggau Ligam; Nurhayati Ramli; Mohd Fazli Zakaria; Naim Syauqi Hamzah; Phongsakorn Prak; Mohammad Suhaimi Kassim; Zarina Masood

2014-01-01

Fire hazard is one of many risks that can affect the safety operation of PUSPATI TRIGA Reactor. Reactor building in Malaysian Nuclear Agency was built in 1980s and the fire system has been introduced since then. The evaluation of the fire safety system at this time is important to ensure the efficiency of fire prevention, fighting and mitigation task that probably occurs. This evaluation involves with the fire fighting system and equipment, integrity of the system from the perspective of management and equipment, fire fighting procedure and fire fighting response team. (author)

The research reactor TRIGA Heidelberg II

International Nuclear Information System (INIS)

Maier-Borst, W.; Krauss, O.

1988-01-01

The reactor is in operation since the beginning of 1978. On the base of the working experience gathered during that time employing the TRIGA in biomedical research, especially the irradiation units have been extended or newly developed. Several TRIGA users have reported difficulties in using the rotary irradiation system. It became obvious that the alternatives to the original Lazy Susan are not commonly known. In this report, the open rotary system fed by a hydraulic rabbit system, which has proved successful in this form during the past ten years is presented

Research activities at the TRIGA Mainz

International Nuclear Information System (INIS)

Eberhardt, K.

1994-01-01

The experimental programme at the TRIGA Mainz covers a wide range of applications in different fields. Two of the four beam tubes are used for the development of fast and mainly continuous chemical separation procedures. These procedures are applied for the investigation of short-lived nuclides and for studies of the chemical behaviour of the heaviest elements. At the third beam tube an on-line mass-separator facility with a microwave-induced plasma as an ion source is installed. Very recently the fourth beam tube has been modified for the production of polarized neutrons by interaction with optically pumped 3 He atoms. The other irradiation facilities are used for Neutron Activation Analysis (NAA) of different samples, among them geological and environmental ones, tracer production for chemical investigations, neutron irradiations of rat brain tissue to explore the utility of 157 Gd for cancer therapy and γ-ray irradiations for biological purposes. (author)

Proceedings of the 4. World TRIGA Users Conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-10-29

This document gathers 30 presentations given at the 2008 Conference of the World TRIGA reactor Users. Most presentations are in the form of slides only, and few ones have an additional summary or are presented as an article only. All aspects of TRIGA-type reactors are approached, from upgrading to decommissioning, from radiotherapy to isotope production, from research program management to training, etc.

Proceedings of the 4. World TRIGA Users Conference

International Nuclear Information System (INIS)

2008-01-01

This document gathers 30 presentations given at the 2008 Conference of the World TRIGA reactor Users. Most presentations are in the form of slides only, and few ones have an additional summary or are presented as an article only. All aspects of TRIGA-type reactors are approached, from upgrading to decommissioning, from radiotherapy to isotope production, from research program management to training, etc

Evaluation of TRIGA Mark II reactor in Turkey

International Nuclear Information System (INIS)

Bilge, Ali Nezihi

1990-01-01

There are two research reactors in Turkey and one of them is the university Triga Mark II reactor which was in service since 1979 both for education and industrial application purposes. The main aim of this paper is to evaluate the spectrum of the services carried by Turkish Triga Mark II reactor. In this work, statistical distribution of the graduate works and applications, by using Triga Mark II reactor is examined and evaluated. In addition to this, technical and scientific uses of this above mentioned reactor are also investigated. It was already showed that the uses and benefits of this reactor can not be limited. If the sufficient work and service is given, NDT and industrial applications can also be carried economically. (orig.)

ANALYSIS OF GAMMA HEATING AT TRIGA MARK REACTOR CORE BANDUNG USING PLATE TYPE FUEL

Directory of Open Access Journals (Sweden)

Setiyanto Setiyanto

2016-10-01

Full Text Available ABSTRACT In accordance with the discontinuation of TRIGA fuel element production by its producer, the operation of all TRIGA type reactor of at all over the word will be disturbed, as well as TRIGA reactor in Bandung. In order to support the continuous operation of Bandung TRIGA reactor, a study on utilization of fuel plate mode, as used at RSG-GAS reactor, to replace the cylindrical model has been done. Various assessments have been done, including core design calculation and its safety aspects. Based on the neutronic calculation, utilization of fuel plate shows that Bandung TRIGA reactor can be operated by 20 fuel elements only. Compared with the original core, the new reactor core configuration is smaller and it results in some empty space that can be used for in-core irradiation facilities. Due to the existing of in-core irradiation facilities, the gamma heating value became a new factor that should be evaluated for safety analysis. For this reason, the gamma heating for TRIGA Bandung reactor using fuel plate was calculated by Gamset computer code. The calculations based on linear attenuation equations, line sources and gamma propagation on space. Calculations were also done for reflector positions (Lazy Susan irradiation facilities and central irradiation position (CIP, especially for any material samples. The calculation results show that gamma heating for CIP is significantly important (0,87 W/g, but very low value for Lazy Susan position (lest then 0,11 W/g. Based on this results, it can be concluded that the utilization of CIP as irradiation facilities need to consider of gamma heating as data for safety analysis report. Keywords: gamma heating, nuclear reactor, research reactor, reactor safety.   ABSTRAK Dengan dihentikannya produksi elemen bakar reaktor jenis Triga oleh produsen, maka semua reaktor TRIGA di dunia terganggu operasinya, termasuk juga reaktor TRIGA 2000 di Bandung. Untuk mendukung pengoperasian reaktor TRIGA Bandung

International Atomic Energy Agency: Highlights of activities

International Nuclear Information System (INIS)

Gillen, A.

1992-09-01

This document provides a brief, well-illustrated summary of the activities of the International Atomic Energy Agency in the months up to September 1992. Especially mentioned are the programmes to enhance the safety of nuclear power, from the study of nuclear reactors to assessing the radiological consequences of reactor accidents, and the areas of non-proliferation and safeguards

International Atomic Energy Agency. Highlights of activities

International Nuclear Information System (INIS)

Gillen, V.A.

1991-09-01

This document provides a brief, well-illustrated summary of the activities of the International Atomic Energy Agency in the months up to September 1991. Especially mentioned are the programmes to enhance the safety of nuclear power, from the study of nuclear reactors to assessing the radiological consequences of reactor accidents, and the areas of non-proliferation and safeguards

6. European conference of TRIGA reactor users. Conference papers

International Nuclear Information System (INIS)

1980-01-01

The Sixth European Conference of TRIGA Users was held in September 1980, in Mainz, Germany under the joint sponsorship of INTERATOM and the Institut fur Kernchemie. The main areas of discussions were: Fuel cycle aspects; New reactor developments and improvements; TRIGA applications; Operating and maintenance experiences and Instrumentation

Hope over fear. The establishment of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Forland, A.

1995-01-01

President Eisenhower's ''Atoms for Peace'' speech in 1953 started a process that led to the establishment of the International Atomic Energy Agency (IAEA). This study analyses the negotiations of the Statute of the Agency. It focuses on how the Agency's scope of action regarding safeguards was negotiated. The Statute is seen as a reflection of the dual purpose of the new Agency to promote peaceful uses of nuclear energy, and to control that peaceful nuclear activities receiving IAEA assistance are not diverted to military purposes. On one hand, the countries receiving assistance from the Agency accepted a degree of international control that represented a breakthrough in international relations. On the other hand, many countries strongly resented controls. Consequently, compromises had to be made in the course of the negotiations in order to reach a consensus. Thus, although the IAEA was established as a competent and technical body, the underlying compromises meant that its scope of actions was restricted. 6 refs

12. U.S. TRIGA users conference. Papers and abstracts

International Nuclear Information System (INIS)

1990-01-01

The Conference presentations were devoted to the following topics: new developments and improvements, including modifications of TRIGA reactors and equipment; experiments with TRIGA reactors (Neutron Radiography); radiochemistry, radioisotope production and beam irradiations (experiment applications, simulation); reactor physics - fuel utilization; reactor operation and maintenance experience; safety aspects, licensing and radiation protection

Safeguards and legal matters 1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-01-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Safeguards and Legal Matters issued during the period 1970-1994. Most publications are published in English, through some are also available in French, Russian and Spanish. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all of these papers have abstracts in English. If publications are also available in other languages than English, this is noted as C for Chinese, F for French, R for Russian and S for Spanish by the relevant ISBN number. It should be noted that prices of books are quoted in Austrian Schillings. The prices do not include local taxes and are subject to change without notice. All books in this catalogue are 16 x 24 cm, paper-bound, unless otherwise stated

3. world TRIGA users conference. Papers and abstracts

International Nuclear Information System (INIS)

2006-01-01

The Conference is focused on TRIGA reactors operation and applications. The main topics are: use of the reactor as a research tool; inspection of spent fuel elements; integrity of fuel rods cladding checks; evaluation of corrosion of aluminum-base fuel cladding materials; Pitting behavior of Aluminum alloys; Monte Carlo simulation of TRIGA: reactivity worth, burnup, flux and power; irradiation facilities; thermal hydraulics analyses etc

Dynamics model for real time diagnostics of Triga RC-1 system

International Nuclear Information System (INIS)

Gadomski, A.M.; Nanni, V.; Meo, G.

1988-01-01

This paper presents dynamics model of TRIGA RC-1 reactor system. The model is dedicated to the real-time early fault detection during a reactor operation in one week exploitation cycle. The algorithms are specially suited for real-time, long time and also accelerated simulations with assumed diagnostic oriented accuracy. The approximations, modular structure, numerical methods and validation are discussed. The elaborated model will be build in the TRIGA Supervisor System and TRIGA Diagnostic Simulator

MK3 modulation affects BMI1-dependent and independent cell cycle check-points.

Directory of Open Access Journals (Sweden)

Peggy Prickaerts

Full Text Available Although the MK3 gene was originally found deleted in some cancers, it is highly expressed in others. The relevance of MK3 for oncogenesis is currently not clear. We recently reported that MK3 controls ERK activity via a negative feedback mechanism. This prompted us to investigate a potential role for MK3 in cell proliferation. We here show that overexpression of MK3 induces a proliferative arrest in normal diploid human fibroblasts, characterized by enhanced expression of replication stress- and senescence-associated markers. Surprisingly, MK3 depletion evokes similar senescence characteristics in the fibroblast model. We previously identified MK3 as a binding partner of Polycomb Repressive Complex 1 (PRC1 proteins. In the current study we show that MK3 overexpression results in reduced cellular EZH2 levels and concomitant loss of epigenetic H3K27me3-marking and PRC1/chromatin-occupation at the CDKN2A/INK4A locus. In agreement with this, the PRC1 oncoprotein BMI1, but not the PCR2 protein EZH2, bypasses MK3-induced senescence in fibroblasts and suppresses P16INK4A expression. In contrast, BMI1 does not rescue the MK3 loss-of-function phenotype, suggesting the involvement of multiple different checkpoints in gain and loss of MK3 function. Notably, MK3 ablation enhances proliferation in two different cancer cells. Finally, the fibroblast model was used to evaluate the effect of potential tumorigenic MK3 driver-mutations on cell proliferation and M/SAPK signaling imbalance. Taken together, our findings support a role for MK3 in control of proliferation and replicative life-span, in part through concerted action with BMI1, and suggest that the effect of MK3 modulation or mutation on M/SAPK signaling and, ultimately, proliferation, is cell context-dependent.

Environment. 1990-2001. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2001-05-01

This catalog lists all sales publications of the International Atomic Energy Agency dealing with the Environment, and issued during the period 1 January 1990 - 30 April 2001. Most publications are issued in English, though some are also available in other languages. These are noted in the catalogue

Implementation of the Finnish Triga reactor and short lived isotopes for diagnostic and irradiation services. Otaniemen Triga-reaktorin ja sillae tuotettujen radioisotooppien saeteilytekniset sovellutukset

Energy Technology Data Exchange (ETDEWEB)

Hiismaeki, P.

1992-01-01

The spectrum of radiation diagnostic methods and irradiation services, already implemented or under development at the Finnish Triga laboratory is discussed. Most attention is devoted to the boron neutron capture therapy project, which has lead to a very encouraging assessment of this modality at the Triga. (orig.).

Dynamics model for real time diagnostics of TRIGA RC-1 system

International Nuclear Information System (INIS)

Gadomski, A.M.; Nanni, V.; Meo, G.B.

1986-01-01

This paper presents dynamics model of TRIGA RC-1 reactor system. The model is dedicated to the real-time early fault detection during a reactor operation in one week exploitation cycle. The algorithms are specially suited for real-time, long time and also accelerated simulations with assumed diagnostic oriented accuracy. The approximations, modular structure, numerical methods and validation are discussed. The elaborated model will be build in the TRIGA Supervisory System and TRIGA Diagnostic Simulator. (author)

An Overview of Ageing Management Programme for PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Syahirah Abdul Rahman; Mohamad Azman Che Mat Isa; Mohd Zaid Mohamed

2011-01-01

The PUSPATI TRIGA reactor (RTP) at Malaysian Nuclear Agency which has been operating for 29 years now faces increasingly serious aging problems. Many components are obsolete whereas genuine parts are no longer in the market. Currently, the aging problem is addressed through periodic maintenance on all systems, structures and components (SSC). As a holistic measure, the Aging Management Program (AMP) was formulated to solve the problems from the grassroots. This paper describes the first stage of the AMP which identifies the strengths and capabilities. This includes identifying the types of aging, responsible parties and relationship between aging problems and safety of RTP. (author)

Time Evolution of Selected Actinides in TRIGA MARK-II Fuel

International Nuclear Information System (INIS)

Usang, M.D.; Naim Shauqi Hamzah; Mohamad Hairie Rabir

2011-01-01

Study is made on the evolution of several actinides capable of undergoing fission or breeding available on the Malaysian Nuclear Agency (MNA) TRIGA MARK-II fuel. Population distribution of burned fuel in the MNA reactor is determined with a model developed using WIMS. This model simulates fuel conditions in the hottest position in the reactor, thus the location where most of the burn up occurs. Theoretical basis of these nuclide time evolution are explored and compared with the population obtained from our models. Good agreements are found for the theoretical time evolution and the population of Uranium-235, Uranium-236, Uranium-238 and Plutonium-239. (author)

Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2014-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

The origins of the International Atomic Energy Agency

Energy Technology Data Exchange (ETDEWEB)

Goldschmidt, B [Commissariat a l' Energie Atomique, International Relations (France)

1977-08-15

On 23 October 1956 in New York, 81 member countries of the United Nations Organization or of its specialized agencies adopted the Statute of the International Atomic Energy Agency, which was to go into formal operation before the end of 1957. A major step towards world-wide control of nuclear energy thus came to be taken more than ten years after the idea of establishing such control had been launched - the first tentative efforts, from 1946 to 1948, having ended in failure. The account follows in an attempt to retrace this 'prehistory' of the IAEA.

The origins of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Goldschmidt, B.

1977-01-01

On 23 October 1956 in New York, 81 member countries of the United Nations Organization or of its specialized agencies adopted the Statute of the International Atomic Energy Agency, which was to go into formal operation before the end of 1957. A major step towards world-wide control of nuclear energy thus came to be taken more than ten years after the idea of establishing such control had been launched - the first tentative efforts, from 1946 to 1948, having ended in failure. The account follows in an attempt to retrace this 'prehistory' of the IAEA

Conceptual Design of a Clinical BNCT Beam in an Adjacent Dry Cell of the Jozef Stefan Institute TRIGA Reactor

International Nuclear Information System (INIS)

Maucec, Marko

2000-01-01

The MCNP4B Monte Carlo transport code is used in a feasibility study of the epithermal neutron boron neutron capture therapy facility in the thermalizing column of the 250-kW TRIGA Mark II reactor at the Jozef Stefan Institute (JSI). To boost the epithermal neutron flux at the reference irradiation point, the efficiency of a fission plate with almost 1.5 kg of 20% enriched uranium and 2.3 kW of thermal power is investigated. With the same purpose in mind, the TRIGA reactor core setup is optimized, and standard fresh fuel elements are concentrated partly in the outermost ring of the core. Further, a detailed parametric study of the materials and dimensions for all the relevant parts of the irradiation facility is carried out. Some of the standard epithermal neutron filter/moderator materials, as well as 'pressed-only' low-density Al 2 O 3 and AlF 3 , are considered. The proposed version of the BNCT facility, with PbF 2 as the epithermal neutron filter/moderator, provides an epithermal neutron flux of ∼1.1 x 10 9 n/cm 2 .s, thus enabling patient irradiation times of nfast /φ epi -13 Gy.cm 2 /n and [overdot]D γ /φ epi -13 Gy.cm 2 /n), the in-air performances of the proposed beam are comparable to all existing epithermal BNCT facilities. The design presents an equally efficient alternative to the BNCT beams in TRIGA reactor thermal columns that are more commonly applied. The cavity of the dry cell, a former JSI TRIGA reactor spent-fuel storage facility, adjacent to the thermalizing column, could rather easily be rearranged into a suitable patient treatment room, which would substantially decrease the overall developmental costs

Benchmarking criticality analysis of TRIGA fuel storage racks.

Science.gov (United States)

Robinson, Matthew Loren; DeBey, Timothy M; Higginbotham, Jack F

2017-01-01

A criticality analysis was benchmarked to sub-criticality measurements of the hexagonal fuel storage racks at the United States Geological Survey TRIGA MARK I reactor in Denver. These racks, which hold up to 19 fuel elements each, are arranged at 0.61m (2 feet) spacings around the outer edge of the reactor. A 3-dimensional model was created of the racks using MCNP5, and the model was verified experimentally by comparison to measured subcritical multiplication data collected in an approach to critical loading of two of the racks. The validated model was then used to show that in the extreme condition where the entire circumference of the pool was lined with racks loaded with used fuel the storage array is subcritical with a k value of about 0.71; well below the regulatory limit of 0.8. A model was also constructed of the rectangular 2×10 fuel storage array used in many other TRIGA reactors to validate the technique against the original TRIGA licensing sub-critical analysis performed in 1966. The fuel used in this study was standard 20% enriched (LEU) aluminum or stainless steel clad TRIGA fuel. Copyright © 2016. Published by Elsevier Ltd.

X-ray photoelectron spectroscopy as detection tool for coordinated or uncoordinated fluorine atoms demonstrated on fluoride systems NaF, K2TaF7, K3TaF8, K2ZrF6, Na7Zr6F31 and K3ZrF7

Science.gov (United States)

Boča, Miroslav; Barborík, Peter; Mičušík, Matej; Omastová, Mária

2012-07-01

While systems K3TaF8 and K3ZrF7 were prepared by modified molten salt method modified wet pathway was used for reproducible preparation of Na7Zr6F31. Its congruently melting character was demonstrated on simultaneous TG/DSC measurements and XRD patterns. X-ray photoelectron spectroscopy was applied for identification of differently bonded fluorine atoms in series of compounds NaF, K2TaF7, K3TaF8, K2ZrF6, Na7Zr6F31 and K3ZrF7. Three different types of fluorine atoms were described qualitatively and quantitatively. Uncoordinated fluorine atoms (F-) provide signals at lowest binding energies, followed by signals from terminally coordinated fluorine atoms (M-F) and then bridging fluorine atoms (M-F-M) at highest energy. Based on XPS F 1s signals assigned to fluorine atoms in compounds with correctly determined structure it was suggested that fluorine atoms in K3ZrF7 have partially bridging character.

A digital data acquisition and display system for ITU TRIGA Mark II reactor

International Nuclear Information System (INIS)

Can, B.; Omuz, S.

2008-01-01

Full text: In this study, a digital data acquisition and display system realized for ITU TRIGA Mark-II Reactor is described. This system is realized in order to help the reactor operator and to increase reactor console capacity. The system consists of two main units, which are host computers and RTI-815F, analog devices, data acquisition card. RTI-815F is multi-function analog/digital input/output board that plugs into one of the available long expansion slots in the IBM-PC, PC/XT, PC/AT, or equivalent personal computers. It has 16 analog input channels for single-ended input signals or 8 analog input channels for differential input signals. But its channel capacity can be increased to 32 input channels for single-ended input signals or 16 input channels for differential input signals. RTI-815F board contains 2 analog output channels, 8 digital input channels and 8 digital output channels. In the ITD TRIGA Mark-II Reactor, 6 fuel temperature channels, 3 water temperature channels, 3 control rod position channels and 4 power channels are chosen as analog input signals for RTI-815F. Its digital outputs are assigned to cooling tower fan, primary and secondary pump reactor scram, control rod rundown. During operation, data are automatically archived to disk and displayed on screen. The channel selection time and sampling time can be adjusted. The simulated movement and position of control rods in the reactor core can be noted and displayed. The changes of power, fuel temperature and water temperature can be displayed on the screen as a graphic. In this system both period and reactivity are calculated and displayed on the screen. (authors)

International Atomic Energy Agency Publications. Catalogue 1986-1999

International Nuclear Information System (INIS)

2000-11-01

This catalogue lists all sales publications of the International Atomic Energy Agency issued from 1986 up to the end of 1999 and still available. Some earlier titles which form part of an established series or are still considered important have also been included. The catalogue is in CD-ROM format

Calculations and selection of a TRIGA core for the Nuclear Reactor IAN-R1

International Nuclear Information System (INIS)

Castiblanco, L.A.; Sarta, J.A.

1997-01-01

The Reactor Group used the code WIMS reduced to five groups of energy, together with the code CITATION, and evaluated four configurations for a core, according to the grid actually installed. The four configurations were taken from the two proposals presented to the Instituto de Ciencias Nucleares y Energias Alternativas by General Atomics Company. In this paper, the Authors selected the best configuration according to the performance of flux distribution and excess reactivity, for a TRIGA core to be installed in the Nuclear Reactor IAN-R1

An fMRI study of Agency

DEFF Research Database (Denmark)

Charalampaki, Angeliki

2017-01-01

Motor area has a distinct directionality, depending on the stage of the volitional movement. In this study, we were interested in assessing the neuronal mechanism underlying this phenomenon. We therefore performed an fMRI study of Agency, to exploit the high spatial resolution this imaging technique...... displays. For the purposes of our study twenty participants were recruited. The experimental procedure we considered appropriate to study the Sense of Agency, involved participants laying inside the fMRI scanner and while they had no visual feedback of their hand, they were instructed to draw straight...... lines on a tablet with a digital pen. They could only see the consequences of their movement as a cursor’s movement on a screen. After finishing their movement, participants were requested to make a judgment over whether they felt they were the Agent of the observed movement or not. The analysis of our...

A New Department of Defense Framework for Efficient Defense Support of Civil Authorities

National Research Council Canada - National Science Library

Liberato, Rodney

2007-01-01

...) capabilities support to civilian authorities during emergencies. Hurricane Katrina added to this national attention on the role the Department of Defense should play in responding to emergencies...

Thermal hydraulic analysis of the IPR-R1 TRIGA reactor; Analise termo-hidraulica do reator TRIGA IPR-R1

Energy Technology Data Exchange (ETDEWEB)

Veloso, Marcelo Antonio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); Fortini, Maria Auxiliadora [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

2002-07-01

The subchannel approach, normally employed for the analysis of power reactor cores that work under forced convection, have been used for the thermal hydraulic evaluation of a TRIGA Mark I reactor, named IPR-R1, at 250 kW power level. This was accomplished by using the PANTERA-1P subchannel code, which has been conveniently adapted to the characteristics of natural convection of TRIGA reactors. The analysis of results indicates that the steady state operation of IPR-R1 at 250 kW do not imply risks to installations, workers and public. (author)

An analysis of decommissioning costs for the AFRRI TRIGA reactor facility

International Nuclear Information System (INIS)

Forsbacka, Matt

1990-01-01

A decommissioning cost analysis for the AFRRI TRIGA Reactor Facility was made. AFRRI is not at this time suggesting that the AFRRI TRIGA Reactor Facility be decommissioned. This report was prepared to be in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations which requires the assurance of availability of future decommissioning funding. The planned method of decommissioning is the immediate decontamination of the AFRRI TRIGA Reactor site to allow for restoration of the site to full public access - this is called DECON. The cost of DECON for the AFRRI TRIGA Reactor Facility in 1990 dollars is estimated to be $3,200,000. The anticipated ancillary costs of facility site demobilization and spent fuel shipment is an additional $600,000. Thus the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for this cost estimate is a study of the decommissioning costs of a similar reactor facility that was performed by Battelle Pacific Northwest Laboratory (PNL) as provided in USNRC publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA. (author)

Some possibilities of utilisation of TRIGA reactors in the future

International Nuclear Information System (INIS)

Stegnar, Peter; Byrne, Anthony R.

2008-01-01

Full text. In this presentation, some possibilities for the future use of TRIGA reactors are discussed. The use and practical applications of neutron activation analysis, both in instrumental and radiochemical analysis, is presented based on the experience of the Institute's TRIGA Mark II Reactor in Ljubljana. The limited use of isotope production for medicine and industry is also discussed as well as some other potential applications, i.e. prompt gamma neutron activation analysis and an approach to BNCT (Boron Neutron Capture Therapy). The possibility of using TRIGA reactors for training in nuclear safety, radiological protection and other relevant fields of science and technology is also addressed in the presentation

Nuclear-driven flashlamp pumping of the atomic iodine laser

International Nuclear Information System (INIS)

Miley, G.H.

1992-03-01

This report is a study of the atomic iodine laser pumped with nuclear- excited XeBr fluorescence. Preliminary experiments, conducted in the TRIGA reactor investigated the fluorescence of the excimer XeBr under nuclear pumping with 10 B and 3 He, for use as a flashlamp gas to stimulate the laser. These measurements included a determination of the fluorescence efficiency (light emitted in the wavelength region of interest, divided by energy deposited in the gas) of XeBr under nuclear pumping, with varying excimer mixtures. Maximum fluorescence efficiencies were approximately 1%. In order to better understand XeBr under nuclear excitation, a kinetics model of the system was prepared. The model generated the time-dependant concentrations of 20 reaction species for three pulse sizes, a TRIGA pulse, a fast burst reactor pulse, and an e-beam pulse. The modeling results predicted fluorescence efficiencies significantly higher (peak efficiencies of approximately 10%) than recorded in the fluorescence experiments. The cause of this discrepancy was not fully determined. A ray tracing computer model was also prepared to evaluate the efficiency with which nuclear-induced fluorescence generated in one cavity of a laser could be coupled into another cavity containing an iodine lasant. Finally, an experimental laser cell was constructed to verify that nuclear-induced XeBr fluorescence could be used to stimulate a laser. Lasing was achieved at 1.31 micron in the TRIGA using C 3 F 7 I, a common iodine lasant. Peak laser powers were approximately 20 mW. Measured flashlamp pump powers at threshold agreed well with literature values, as did lasant pressure dependency on laser operation

TRIGA research reactors with higher power density

International Nuclear Information System (INIS)

Whittemore, W.L.

1994-01-01

The recent trend in new or upgraded research reactors is to higher power densities (hence higher neutron flux levels) but not necessarily to higher power levels. The TRIGA LEU fuel with burnable poison is available in small diameter fuel rods capable of high power per rod (≅48 kW/rod) with acceptable peak fuel temperatures. The performance of a 10-MW research reactor with a compact core of hexagonal TRIGA fuel clusters has been calculated in detail. With its light water coolant, beryllium and D 2 O reflector regions, this reactor can provide in-core experiments with thermal fluxes in excess of 3 x 10 14 n/cm 2 ·s and fast fluxes (>0.1 MeV) of 2 x 10 14 n/cm 2 ·s. The core centerline thermal neutron flux in the D 2 O reflector is about 2 x 10 14 n/cm 2 ·s and the average core power density is about 230 kW/liter. Using other TRIGA fuel developed for 25-MW test reactors but arranged in hexagonal arrays, power densities in excess of 300 kW/liter are readily available. A core with TRIGA fuel operating at 15-MW and generating such a power density is capable of producing thermal neutron fluxes in a D 2 O reflector of 3 x 10 14 n/cm 2 ·s. A beryllium-filled central region of the core can further enhance the core leakage and hence the neutron flux in the reflector. (author)

Tumor radiosensitizers - current status of development of various approaches: Report of an International Atomic Energy Agency meeting

DEFF Research Database (Denmark)

Horsman, Michael Robert; Bohm, Lothar; Margison, Geoffrey P.

2006-01-01

PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those well-established in clinical practice, that operated through a variety of mechanisms to sensitize tumors to radiation and (2) to compare...... and contrast their tumor efficacy, normal tissue toxicity, and status of development regarding clinical application. The aim was to advise the IAEA as to which developing agent or class of agents would be worth promoting further, by supporting additional laboratory research or clinical trials...... and for clinical trials that would be suitable for industrialized countries, as well as trials that were considered more appropriate for developing countries.PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those...

RIA Analysis of Unprotected TRIGA Reactor

Directory of Open Access Journals (Sweden)

M.H. Altaf

2017-07-01

Full Text Available An RIA (reactivity initiated accident analysis has been carried out for the TRIGA Mark II research reactor considering both step and ramp reactivity ranges within 0.5 % dk/k (< $1 to 2.0 % dk/k (>$2. The insertion time was set at 10 s. Based on the fact that a reactor becomes unprotected if scram does not work at the event of danger, to define unprotected conditions, the time to actuate scram (trip was taken as close to total simulation time. In this long duration of scram inactivity, it is obtained from the present analysis that the reactor remained safe to up to 1.8 % dk/k ($2.57 for step reactivity and 1.99 % dk/k ($2.84 for ramp reactivity. In addition to negative temperature coefficient of reativity, probably the longer time of reactivity insertion keeps TRIGA safe even at larger magnitudes of reactivity during unprotected reactor transients. Coupled point kinetics, neutronics, and thermal hydraulics code EUREKA-2/R has been utilized for this work. It appears that EUREKA-2/RR predicts the sequence of unprotected transient scenario of TRIGA core with good approximation and the results will definitely be helpful for the reactor operators.

Operational experience at the AFRRI-TRIGA reactor facility (1972-1974)

Energy Technology Data Exchange (ETDEWEB)

McKenzie, J L [Armed Forces Radiobiology Research Institute, Bethesda, MD (United States)

1974-07-01

The Armed Forces Radiobiology Research Institute operates a TRIGA Mark-F Reactor which has a movable core, and the capability to operate in the steady state mode up to a maximum power level of one megawatt and in the pulse mode up to a maximum peak power of 2600 MW (10 millisecond pulse). The reactor experienced three operational incidents during the period from February 1972 to February 1974, and two of these incidents were reportable to the Atomic Energy Commission. The first incident consisted of a failure of a weld at the top of the tri-flute on an instrumented fuel element which allowed the tri-flute to move up about one-half inch from its normal position. The instrumented fuel element was removed from the reactor core and replaced with a new instrumented fuel element. The second incident consisted of a malfunction of the reactor core position safety interlock which resulted in the lead shield doors closing around the reactor core shroud. The lead shield doors did not make contact with the reactor core shroud and therefore no damage occurred. The incident was reported to the Atomic Energy Commission. The third incident consisted of a failure of the threaded connector on the top of the transient control rod which allowed the transient control rod to separate from the connecting rod and drop to the bottom of the guide tube. The damaged transient control rod was removed from the guide tube and a new transient rod was installed in the reactor core. This incident was reported to the Atomic Energy Commission. A modification was made to Exposure Room 2 which consisted of placing panels, painted with gadolinium oxide paint, on the walls, ceiling, and reactor core tank projection. This resulted in the {sup 41}Ar production rate and the effluent release to the environment being reduced by a factor of 10 to 20, depending upon the position of the reactor core. (author)

Operational experience at the AFRRI-TRIGA reactor facility (1972-1974)

International Nuclear Information System (INIS)

McKenzie, J.L.

1974-01-01

The Armed Forces Radiobiology Research Institute operates a TRIGA Mark-F Reactor which has a movable core, and the capability to operate in the steady state mode up to a maximum power level of one megawatt and in the pulse mode up to a maximum peak power of 2600 MW (10 millisecond pulse). The reactor experienced three operational incidents during the period from February 1972 to February 1974, and two of these incidents were reportable to the Atomic Energy Commission. The first incident consisted of a failure of a weld at the top of the tri-flute on an instrumented fuel element which allowed the tri-flute to move up about one-half inch from its normal position. The instrumented fuel element was removed from the reactor core and replaced with a new instrumented fuel element. The second incident consisted of a malfunction of the reactor core position safety interlock which resulted in the lead shield doors closing around the reactor core shroud. The lead shield doors did not make contact with the reactor core shroud and therefore no damage occurred. The incident was reported to the Atomic Energy Commission. The third incident consisted of a failure of the threaded connector on the top of the transient control rod which allowed the transient control rod to separate from the connecting rod and drop to the bottom of the guide tube. The damaged transient control rod was removed from the guide tube and a new transient rod was installed in the reactor core. This incident was reported to the Atomic Energy Commission. A modification was made to Exposure Room 2 which consisted of placing panels, painted with gadolinium oxide paint, on the walls, ceiling, and reactor core tank projection. This resulted in the 41 Ar production rate and the effluent release to the environment being reduced by a factor of 10 to 20, depending upon the position of the reactor core. (author)

Environment. 1980-1994. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1995-06-01

The catalogue lists all publications of the International Atomic Energy Agency dealing with the Environment issued during the period 1980-1993. The major subjects covered include: effect of agrochemical residues on soils and aquatic ecosystems, application of radioisotopes in conservation of the environment, siting of nuclear power plants, environmental isotope data and environmental contamination due to nuclear accidents

University of Arizona TRIGA reactor. Annual utilization report, 1984-1985

International Nuclear Information System (INIS)

Nelson, G.W.

1986-01-01

This is the annual report for the University of Arizona TRIGA Reactor under Contract No. DE-AC02-76ER02096 covering the period July 1, 1984 through June 30, 1985, including the 1984-85 Academic Year. The purpose of this report is to document the facility usage which is possible because of DOE support under the contract. The reactor is operated under License R-52 with the United States Nuclear Regulatory Commission

75 FR 52732 - Renewal of Department of Defense Federal Advisory Committee; Missile Defense Advisory Committee

Science.gov (United States)

2010-08-27

... Committee; Missile Defense Advisory Committee AGENCY: Department of Defense (DoD). ACTION: Renewal of..., the Department of Defense gives notice that it is renewing the charter for the Missile Defense... Director, Missile Defense Agency, independent advice and recommendations on all matters relating to missile...

Status of the TRIGA user facility in Mainz

Energy Technology Data Exchange (ETDEWEB)

Kories, Fabian; Heil, Werner; Karch, Jan Peter; Sobolev, Yury [Institut fuer Physik, Johannes Gutenberg Universitaet Mainz (Germany); Eberhardt, Klaus; Hampel, Gabriele; Reich, Tobias; Trautmann, Norbert [Institut fuer Kernchemie, Johannes Gutenberg Universitaet Mainz (Germany)

2014-07-01

Ultra-cold neutrons (UCN) offer unique opportunities for investigating the properties of the free neutron with exceptionally high precision such as the measurement of its lifetime. At the pulsed TRIGA reactor in Mainz, a superthermal UCN source using solid deuterium as converter is operational and delivers up to 10 UCN/cm{sup 3} in typical storage volumes of 10 l. Within PRISMA Cluster of excellence, this source will be upgraded to a targeted strength of 100 UCN/cm{sup 3} in order to transform TRIGA Mainz into a world-leading user facility for UCN research. Besides the installation of a He liquefier to sustain long-term experiments, the existing neutron guides have to be replaced by high-quality guides with low surface roughness which are internally coated with Ni-58 to increase the phase space for UCN transport. The poster gives a status report on the activities at the UCN source at TRIGA Mainz.

Atomic structure calculations for F-like tungsten

Science.gov (United States)

Sunny, Aggarwal

2014-09-01

Energy levels, wavefunction compositions and lifetimes have been computed for all levels of 1s22s22p5, 1s22s2p6, 1s22s22p43s, 1s22s22p43p, and 1s22s22p43d configurations in highly charged F-like tungsten ion. The multiconfigurational Dirac—Fock method (MCDF) is adopted to generate the wavefunctions. We have also presented the transition wavelengths, oscillator strengths, transition probabilities, and line strengths for the electric dipole (E1) and magnetic quadrupole (M2) transition from the 1s22s22p5 ground configuration. We have performed parallel calculations with the flexible atomic code (FAC) for comparing the atomic data. The reliability of present data is assessed by comparison with other theoretical and experimental data available in the literature. Good agreement is found between our results and those obtained using different approaches confirm the quality of our results. Additionally, we have predicted some new atomic data for F-like W that were not available so far and may be important for plasma diagnostic analysis in fusion plasma.

Comparative examination of the fresh and spent nuclear TRIGA fuel by neutron radiography

International Nuclear Information System (INIS)

Dinca, M.

2016-01-01

At the Institute for Nuclear Research (INR) there is in operation an underwater (wet) neutron radiography facility (INUM) designed especially for nuclear fuel investigation. INUM was involved in CANDU experimental type and TRIGA type nuclear fuel investigations. In this paper are presented the results after investigation of the nuclear fuel TRIGA-HEU and TRIGA-LEU, fresh and spent, using transfer method with metallic foils of dysprosium and indium and radiographic films (38 cm x 10 cm). This method is the most suitable for spent fuel and offers a high geometrical resolution of the images that subsequently are digitalized with a professional scanner for films. From the images obtained for TRIGA-HEU and TRIGA-LEU with different degree of burn-up there are established the opportunities to use dysprosium or indium converter foils based on their response to thermal or epithermal neutrons to evaluate the degree of burn-up, dimensional measurements, defects etc. (authors)

The stationary neutron radiography system: a TRIGA-based production neutron radiography facility

International Nuclear Information System (INIS)

Chesworth, Robert H.; Hagmann, Dean B.

1988-01-01

General Atomics (GA) is under contract to construct a Stationary Neutron Radiography System (SNRS) - on a turnkey basis - at McClellan Air Force Base in Sacramento, California. The SNRS is a custom designed neutron radiography system which will utilize a 1000 KW TRIGA reactor as the neutron source. The partially below-ground reactor will be equipped with four inclined beam tubes originating near the top of the reactor graphite reflector and installed tangential to the reactor core to provide a strong current of thermal neutrons with minimum gamma ray contamination. The inclined beam tubes will terminate in four large bays and will interface with rugged component positioning systems designed to handle intact aircraft wings, other honeycomb aircraft structures, and pyrotechnics. The SNRS will be equipped with real-time, near real-time, and film radiographic imaging systems to provide a broad spectrum of capability for detection of entrained moisture or corrosion in large aircraft panels. GA is prime contractor to the Air Force for the SNRS and is specifically responsible for the TRIGA reactor system and a portion of the neutron beam system design. Science Applications International Corporation and the Lionakis-Beaumont Design Group are principal subcontractors to GA on the project. (author)

International Atomic Energy Agency Safeguards: Challenge and response

Science.gov (United States)

Spector, Leonard S.

2017-11-01

This article provides a critical review of the nuclear accounting and inspection system of the International Atomic Energy Agency (IAEA), known as "IAEA safeguards." The article focuses on the multiple challenges the Agency confronts in verifying that all nuclear activities in the countries under its safeguards system are being pursued for exclusively peaceful purposes. The principal challenges noted are those posed by: undeclared facilities, the development of enrichment and reprocessing capabilities, illicit procurement activities, denial of inspector access, difficulties in verifying absence of weaponization activities, and difficulties in establishing that all nuclear-relevant activities in a state are peaceful. The article is in the form of annotated PowerPoint briefing slides.

Malaysian perspective on the contribution of nuclear science and technology to national development

Energy Technology Data Exchange (ETDEWEB)

Alang Md Rashid, Nahrul Khair [Unit Tenaga Nuklear, Bangi, Selangor (Malaysia)

1994-04-01

The development of nuclear science and technology in Malaysia began with the inception of The Nuclear Energy Unit (UTN) in 1972. In 1985, the Atomic Energy Licensing Board was set up as a regulatory body to enforce the Atomic Energy Licensing Act. Ten years after UTN`s establishment, the first of its major facilities, a one Megawatt TRIGA MkII nuclear research reactor (RTP), was commissioned. This is the first step of any type of nuclear reactor for Malaysia. The healthy development of peaceful uses of nuclear science and technology in malaysia has enabled UTN to acquire several other major facilities. These facilities support research and development, in line with UTN`s mission, viz, to enhance national development through the applications of nuclear science and technology. This paper describes selected activities at UTN and some of its successes in linking the results of research and development to real-world applications through services and/or technology transfers.

Malaysian perspective on the contribution of nuclear science and technology to national development

International Nuclear Information System (INIS)

Nahrul Khair Alang Md Rashid

1994-01-01

The development of nuclear science and technology in Malaysia began with the inception of The Nuclear Energy Unit (UTN) in 1972. In 1985, the Atomic Energy Licensing Board was set up as a regulatory body to enforce the Atomic Energy Licensing Act. Ten years after UTN's establishment, the first of its major facilities, a one Megawatt TRIGA MkII nuclear research reactor (RTP), was commissioned. This is the first step of any type of nuclear reactor for Malaysia. The healthy development of peaceful uses of nuclear science and technology in malaysia has enabled UTN to acquire several other major facilities. These facilities support research and development, in line with UTN's mission, viz, to enhance national development through the applications of nuclear science and technology. This paper describes selected activities at UTN and some of its successes in linking the results of research and development to real-world applications through services and/or technology transfers

Radiation therapy. 1990-2001. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2001-04-01

This catalog lists all sales publications of the International Atomic Energy Agency dealing with Radiation Therapy, and issued during the period 1 January 1990 - 30 April 2001. Most publications are issued in English, though some are also available in other languages. These are noted in the catalogue

Acquisition Planning at the Defense Communications Agency.

Science.gov (United States)

1984-04-01

guidelines for interaction are developed under the leadership of DCA agencywide integrators with the participation of personnel from DCA, the Services...Communications System DCSO - Defense Communications System Organizatin . DDN - Defense Data Network DEC - Decision Making DG - Defense Guidance DIA - Defense

78 FR 59854 - Defense Federal Acquisition Regulation Supplement: Acquisitions in Support of Operations in...

Science.gov (United States)

2013-09-30

...)(xxvi); 0 b. Removing paragraph (f)(xxvii) and redesignating paragraphs (f)(xxviii) through (xxxii) as.... Adding a new paragraph (f)(xxxii); and 0 e. Revising paragraphs (f)(xxxiv) and (xxxv). The revisions and... National Defense Authorization Act for Fiscal Year 2008 (Pub. L. 110-181). * * * * * (xxxii) Use the clause...

Monte Carlo modelling of TRIGA research reactor

Science.gov (United States)

El Bakkari, B.; Nacir, B.; El Bardouni, T.; El Younoussi, C.; Merroun, O.; Htet, A.; Boulaich, Y.; Zoubair, M.; Boukhal, H.; Chakir, M.

2010-10-01

The Moroccan 2 MW TRIGA MARK II research reactor at Centre des Etudes Nucléaires de la Maâmora (CENM) achieved initial criticality on May 2, 2007. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes for their use in agriculture, industry, and medicine. This study deals with the neutronic analysis of the 2-MW TRIGA MARK II research reactor at CENM and validation of the results by comparisons with the experimental, operational, and available final safety analysis report (FSAR) values. The study was prepared in collaboration between the Laboratory of Radiation and Nuclear Systems (ERSN-LMR) from Faculty of Sciences of Tetuan (Morocco) and CENM. The 3-D continuous energy Monte Carlo code MCNP (version 5) was used to develop a versatile and accurate full model of the TRIGA core. The model represents in detailed all components of the core with literally no physical approximation. Continuous energy cross-section data from the more recent nuclear data evaluations (ENDF/B-VI.8, ENDF/B-VII.0, JEFF-3.1, and JENDL-3.3) as well as S( α, β) thermal neutron scattering functions distributed with the MCNP code were used. The cross-section libraries were generated by using the NJOY99 system updated to its more recent patch file "up259". The consistency and accuracy of both the Monte Carlo simulation and neutron transport physics were established by benchmarking the TRIGA experiments. Core excess reactivity, total and integral control rods worth as well as power peaking factors were used in the validation process. Results of calculations are analysed and discussed.

Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

International Nuclear Information System (INIS)

Salam, M. A.

2013-01-01

The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

Energy Technology Data Exchange (ETDEWEB)

Salam, M. A. [Atomic Energy Research Establishment, Dhaka (Bangladesh)

2013-07-01

The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

Operation experience with the TRIGA reactor Wien 2004

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2004-01-01

The TRIGA Mark-II reactor in Vienna is now in operation for more than 42 years. The average operation time is about 230 days per year with 90 % of this time at nominal power of 250 kW. The remaining 10 % operation time is used for students' training courses at low power level. Pulse operation is rather infrequent with about 5 to 10 pulses per year. The utilization of this facility is excellent, the number of students participating in practical exercises has strongly increased, and also training courses for outside groups such as the IAEA or for the 2004 Eugene Wigner Course are using the reactor, because it is the only TRIGA reactor remaining in Austria. Therefore, there is no need for decommissioning and it is intended to operate it as long as possible into the next decade. Nevertheless, in early 2004 it was decided to prepare a report on a decommissioning procedure for a typical TRIGA Mark II reactor which lists the volumes, the activity and the weight of individual materials such as concrete, aluminium, stainless steel, graphite and others which will accumulate during this process (a summary of possible activated and contaminated materials and the activity of a single TRIGA fuel element as a function of fuel type and decay time in Bq is presented). The status of the reactor (instrumentation, fuel elements, cooling circuit, ventilation system, re-inspection and maintenance program, cost/benefit) is outlined. (nevyjel)

Department of Defense Research, Development, Test, and Evaluation (RDT and E): Appropriations Structure

Science.gov (United States)

2016-12-13

Research Projects Agency website, accessed December 5, 2016, http://www.darpa.mil/about-us/mission. Appropriations Structure of Defense RDT&E...funding streams. Among the many other factors that may affect the effectiveness of the performance of RDT&E are: organizational structures and...Department of Defense Research, Development, Test, and Evaluation (RDT&E): Appropriations Structure John F. Sargent Jr. Specialist in

The law for the Independent Administrative Institution Japan Atomic Energy Agency

International Nuclear Information System (INIS)

2005-07-01

The Law no.155 of 3 Dec. 2004(the latest revision, Law no.87 of 26 July 2005) is the law to define the objective, scope of activities, etc. of the independent administrative institution Japan Atomic Energy Agency. The agency is established under the atomic energy basic law to make comprehensive research and development associated with nuclear energy and establishment of nuclear fuel cycle and to contribute to promote research, development and utilization of it. The agency has its main office in Ibaraki prefecture and its capital is the amount of contributions by the government and persons other than the government. The officers are consisted of a president, an executive vice president, less than 7 executive directors and 2 auditors. The president is appointed by the Minister of Ministry of Education, Culture, Sports, Science and Technology with the consent of the atomic energy commission. The term of the president is from the day of the appointment to the end of midterm goal period and that of auditors is 2 years. Activities of the agency include basic and application research of nuclear energy, technical establishment of nuclear fuel cycle (R and D of Fast Breeder Reactor, nuclear fuel for FBR, reprocessing and treatment and disposal of HLW), promotion of application of R and D results of above areas, utilization sharing of facility and equipment, human resource development of nuclear energy field, collection, arrangement and dissemination of nuclear information and study and analysis requested by the government. (T. Tanaka)

Applications of Oregon State University's TRIGA reactor in health physics education

International Nuclear Information System (INIS)

Higginbotham, J.F.

1990-01-01

The Oregon State University TRIGA reactor (OSTR) is used to support a broad range of traditional academic disciplines, including anthropology, oceanography, geology, physics, nuclear chemistry, and nuclear engineering. However, it also finds extensive application in the somewhat more unique area of health physics education and research. This paper summarizes these health physics applications and briefly describes how the OSTR makes important educational contributions to the field of health physics

Enrichment measurement in TRIGA type fuels; Medicion de enriquecimiento en combustibles tipo Triga

Energy Technology Data Exchange (ETDEWEB)

Aguilar H, F.; Mazon R, R. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2001-05-15

The Department of Energy of the United States of North America, through the program 'Idaho Operations Nuclear Spent Fuel Program' of the Idaho National Engineering and Environmental Laboratory (INEEL), in Idaho Falls; Idaho USA, hires to Global Technologies Inc. (GTI) to develop a prototype device of detection enrichment uranium (DEU Detection of Enrichment of Uranium) to determine quantitatively the enrichment in remainder U-235 in a TRIGA fuel element at the end of it useful life. The characteristics of the prototype developed by GTI are the following ones: It allows to carry out no-destructive measurements of TRIGA type fuel. Easily transportable due to that reduced of it size. The determination of the enrichment (in grams of U-235) it is obtained with a precision of 5%. The National Institute of Nuclear Research (ININ), in its facilities of the Nuclear Center of Mexico, it has TRIGA type fuel of high and low enrichment (standard and FLIP) fresh and with burnt, it also has the infrastructure (hot cells, armor-plating of transport, etc) and qualified personnel to carry out the necessary maneuvers to prove the operation of the DEU prototype. For this its would be used standard type fuel elements and FLIP, so much fresh as with certain burnt one. In the case of the fresh fuels the measurement doesn't represent any risk, the fuels before and after the measurement its don't contain a quantity of fission products that its represent a radiological risk in its manipulation; but in the case of the fuels with burnt the handling of the same ones represents an important radiological risk reason why for its manipulation it was used the transport armor-plating and the hot cells. (Author)

United States Department of Defense Agency Financial Report for Fiscal Year 2013. Financial Section

Science.gov (United States)

2013-01-01

capacity for operating landfills and life expectancy in years for all other assets. The Department expenses the full cost to clean up contamination for...construction, and rehabilitation projects on inland waterways. The BFS manages and invests for the Trust Fund. Defense Commissary Agency Surcharge Trust

TRIGA reactor as an experimental tool

Energy Technology Data Exchange (ETDEWEB)

Nahrul Khair bin Alang Mohammad Rashid (PUSPATI, Selangor (Malaysia))

1981-01-01

Article reviewed on the general features, operation and capabilities, and utilization of a research reactor, PUSPATI TRIGA MARK II. The paper also described the arrangements for the use of the PUSPATI reactor.

Triga reactor as an experimental tool

International Nuclear Information System (INIS)

Nahrul Khair bin Alang Mohammad Rashid

1981-01-01

Article reviewed on the general features, operation and capabilities, and utilization of a research reactor, PUSPATI TRIGA MARK II. The paper also described the arrangements for the use of the PUSPATI reactor

Fluid Flow Characteristic Simulation of the Original TRIGA 2000 Reactor Design Using Computational Fluid Dynamics Code

International Nuclear Information System (INIS)

Fiantini, Rosalina; Umar, Efrizon

2010-01-01

Common energy crisis has modified the national energy policy which is in the beginning based on natural resources becoming based on technology, therefore the capability to understanding the basic and applied science is needed to supporting those policies. National energy policy which aims at new energy exploitation, such as nuclear energy is including many efforts to increase the safety reactor core condition and optimize the related aspects and the ability to build new research reactor with properly design. The previous analysis of the modification TRIGA 2000 Reactor design indicates that forced convection of the primary coolant system put on an effect to the flow characteristic in the reactor core, but relatively insignificant effect to the flow velocity in the reactor core. In this analysis, the lid of reactor core is closed. However the forced convection effect is still presented. This analysis shows the fluid flow velocity vector in the model area without exception. Result of this analysis indicates that in the original design of TRIGA 2000 reactor, there is still forced convection effects occur but less than in the modified TRIGA 2000 design.

Ab Initio Study of Chemical Reactions of Cold SrF and CaF Molecules with Alkali-Metal and Alkaline-Earth-Metal Atoms: The Implications for Sympathetic Cooling.

Science.gov (United States)

Kosicki, Maciej Bartosz; Kędziera, Dariusz; Żuchowski, Piotr Szymon

2017-06-01

We investigate the energetics of the atom exchange reaction in the SrF + alkali-metal atom and CaF + alkali-metal atom systems. Such reactions are possible only for collisions of SrF and CaF with the lithium atoms, while they are energetically forbidden for other alkali-metal atoms. Specifically, we focus on SrF interacting with Li, Rb, and Sr atoms and use ab initio methods to demonstrate that the SrF + Li and SrF + Sr reactions are barrierless. We present potential energy surfaces for the interaction of the SrF molecule with the Li, Rb, and Sr atoms in their energetically lowest-lying electronic spin states. The obtained potential energy surfaces are deep and exhibit profound interaction anisotropies. We predict that the collisions of SrF molecules in the rotational or Zeeman excited states most likely have a strong inelastic character. We discuss the prospects for the sympathetic cooling of SrF and CaF molecules using ultracold alkali-metal atoms.

The International Atomic Energy Agency - Organization, Work and Services in Selected Fields

International Nuclear Information System (INIS)

Köteles, G.J.

1979-01-01

In an address to the 8th General Assembly of the United Nations (1953) the President of the United States suggested that Governments should begin to make joint contributions from their stockpiles of fissile materials to an international atomic energy agency which would be set up under the aegis of the United Nations. The fissile material so collected would be used to serve the peaceful pursuits of mankind. Experts would be mobilized to apply atomic energy to the needs of agriculture, medicine and other peaceful purposes and a special effort would be made to provide abundant electrical energy in the power-starved areas of the world. This suggestion was taken up. A Statute which defines the structure and purpose of the International Atomic Energy Agency (IAEA) was prepared by a group of nations and approved by a conference at the United Nations Headquarters in 1956. The Statute entered into force on 29 July 1957. The Agency's objectives, as defined in its Statute, are that it ''shall seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world. It shall ensure, as far as it is able, that assistance provided by it or at its request or under its supervision or control is not used in such a way as to further any military purpose''. To attain these objectives, the IAEA is authorized ''to encourage and assist research on, and development and practical application of, atomic energy for peaceful uses throughout the world; and, if requested to do so, to act as an intermediary for the purposes of securing the performance of services or the supplying of materials, equipment, or facilities by one member of the Agency for another''; to ''... assemble and make available in an accessible form the [scientific] information made available to it...'' and furthermore ''to make provision, ... for materials, services, equipment, and facilities to meet the

Physics and Its Multiple Roles in the International Atomic Energy Agency

Science.gov (United States)

Massey, Charles D.

2017-01-01

The IAEA is the world's centre for cooperation in the nuclear field. It was set up as the world's ``Atoms for Peace'' organization in 1957 within the United Nations family. The Agency works with its Member States and multiple partners worldwide to promote the safe, secure and peaceful use of nuclear technologies. Three main areas of work underpin the IAEA's mission: Safety and Security, Science and Technology, and Safeguards and Verification. To carry out its mission, the Agency is authorized to encourage and assist research on, and development and practical application of, atomic energy for peaceful uses throughout the world; foster the exchange of scientific and technical information on peaceful uses of atomic energy; and encourage the exchange of training of scientists and experts in the field of peaceful uses of atomic energy. Nowadays, nuclear physics and nuclear technology are applied in a great variety of social areas, such as power production, medical diagnosis and therapies, environmental protection, security control, material tests, food processing, waste treatments, agriculture and artifacts analysis. This presentation will cover the role and practical application of physics at the IAEA, and, in particular, focus on the role physics has, and will play, in nuclear security.

The role of TRIGA reactors in pure and applied nuclear research outside the United States in the last couple of years

International Nuclear Information System (INIS)

Rollier, M.A.

1972-01-01

The last two years trend of research in European TRIGA plants, which reported to the 1970 TRIGA Owners' Conference in Helsinki, is presented. The report discusses also new TRIGA plants in Europe, 1971-72; Research at TRIGA plants and new TRIGA reactors outside Europe and the U.S.A., 1971-72; Safety, health, environment, egomania and TRIGA reactors

Defense Threat Reduction Agency Radiochemical Needs

Science.gov (United States)

Walsh, Michael A. R.; Velazquez, Daniel L.

2009-08-01

The United States Government (USG) first developed nuclear forensics-related capabilities to analyze radiological and nuclear materials, including underground nuclear test debris and interdicted materials. Nuclear forensics is not a new mission for Department of Defense (DoD). The department's existing nuclear forensics capability is the result of programs that span six (6) decades and includes activities to assess foreign nuclear weapons testing activities, monitor and verify nuclear arms control treaties, and to support intelligence and law enforcement activities. Today, nuclear forensics must support not only weapons programs and nuclear smuggling incidents, but also the scientific analysis and subsequent attribution of terrorists' use of radiological or nuclear materials/devices. Nuclear forensics can help divulge the source of origin of nuclear materials, the type of design for an interdicted or detonated device, as well as the pathway of the materials or device to the incident. To accomplish this mission, the USG will need trained radiochemists and nuclear scientists to fill new positions and replace the retiring staff.

Defense Threat Reduction Agency Radiochemical Needs

International Nuclear Information System (INIS)

Walsh, Michael A. R.; Velazquez, Daniel L.

2009-01-01

The United States Government (USG) first developed nuclear forensics-related capabilities to analyze radiological and nuclear materials, including underground nuclear test debris and interdicted materials. Nuclear forensics is not a new mission for Department of Defense (DoD). The department's existing nuclear forensics capability is the result of programs that span six (6) decades and includes activities to assess foreign nuclear weapons testing activities, monitor and verify nuclear arms control treaties, and to support intelligence and law enforcement activities. Today, nuclear forensics must support not only weapons programs and nuclear smuggling incidents, but also the scientific analysis and subsequent attribution of terrorists' use of radiological or nuclear materials/devices. Nuclear forensics can help divulge the source of origin of nuclear materials, the type of design for an interdicted or detonated device, as well as the pathway of the materials or device to the incident. To accomplish this mission, the USG will need trained radiochemists and nuclear scientists to fill new positions and replace the retiring staff.

Operation and maintenance experiences at the C.R.E. Casaccia TRIGA reactor

International Nuclear Information System (INIS)

Festinesi, A.

1988-01-01

The memoir explains TRIGA RC-1 plant activities from last European TRIGA Users' Conference till today. In particular, measures following reactor exercise license renewing (March 1987) are described. Finally, difficulties and measures about shielding tank's water funguses and spores contamination, are explained. (author)

Development of JOYO MK-II core characteristics database

International Nuclear Information System (INIS)

Tabuchi, Shiro; Aoyama, Takafumi

2000-01-01

The MK-II core of the experimental fast reactor JOYO served as the irradiation bed for testing fuels and materials for FBR development since 1982 for 15 years. During the MK-II operation, extensive data were accumulated from the core management calculations and characteristics tests conducted in thirty-one duty operations and thirteen special test operations. These core management data and core characteristics data were compiled into a database recorded on CD-ROM for user convenience. The calculated core management data are the text style data. The 'Configuration Data' include the history of the fuel exchange and core arrangement for each cycle. The Subassembly Library Data' include the atomic number density, neutron fluence, burn-up, integral power of about 300 fuel subassemblies, and 60 irradiation subassemblies. The 'Output Data' include the neutron fluxes, gamma fluxes, power density, linear heat rates, coolant and fuel temperature distributions of each core position at the beginning and end of each cycle. The measured core characteristics data, such as the excess reactivity, control rod worths, temperature coefficient, power coefficient, and burn-up coefficient are also included along with the measurement conditions. (J.P.N.)

Present and future use of TRIGA reactors in the Federal Republic of Germany

International Nuclear Information System (INIS)

Menke, H.; Junker, D.; Krauss, O.

1986-01-01

In the Federal Republic of Germany nine research reactors are presently in operation, three of which are TRIGA reactors. These are the TRIGA Mark I reactors at Hannover and Heidelberg with a steady state power of 250 kW and the TRIGA Mark II reactor at Mainz with a steady power of 100 kW and a peak pulsing power of 250 MW. The decommissioning of a number of research reactors, including the TRIGA Mark III reactor at Neuherberg near Munich, is reason enough to think about the present and future use of our reactors. The German TRIGA reactors met a lively interest of scientists, since they went into operation. Presently they are well used especially in biomedical (Hannover, Heidelberg) and basic research (Mainz). In the course of about 20 years of operation the techniques and requirements of experiments changed and consequently the use of the reactors too. Certainly this will be so in the future. But thanks to its versatile experimental facilities, this type of reactor can meet the various experimental demands. So we are looking forward to a good utilisation of our German TRIGA reactors in future and taking into account the low costs for personal, energy and fuel, we are quite confident that they will be in operation still for many years. (author)

Agreement on the Privileges and Immunities of the International Atomic Energy Agency

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-08-17

The text of the Agreement on the Privileges and Immunities of the International Atomic Energy Agency, as approved by the Board of Governors on 1 July 1959, is re produced in this document for the information of all Members of the Agency. As required by section 38 of the Agreement, the Director General will transmit certified copies, in the Agency's four working languages, to the Government of each Member State.

Agreement on the Privileges and Immunities of the International Atomic Energy Agency

International Nuclear Information System (INIS)

1959-01-01

The text of the Agreement on the Privileges and Immunities of the International Atomic Energy Agency, as approved by the Board of Governors on 1 July 1959, is re produced in this document for the information of all Members of the Agency. As required by section 38 of the Agreement, the Director General will transmit certified copies, in the Agency's four working languages, to the Government of each Member State

INR TRIGA Research Reactors: A Neutron Source for Radioisotopes and Materials Investigation

International Nuclear Information System (INIS)

Barbos, D.; Ciocanescu, M.; Paunoiu, C.; Bucsa, A.F.

2013-01-01

At the INR there are 2 high intensity neutron sources. These sources are in fact the two nuclear TRIGA reactors: TRIGA SSR 14 MW and TRIGA ACPR. TRIGA stationary reactor is provided with several in-core irradiation channels. Other several out-of-core irradiation channels are located in the vertical channels in the beryllium reflector blocks. The maximum value of the thermal neutron flux (E 14 cm -2 s -1 and of fast neutron flux (E>1 MeV) is 6.89×10 13 cm -2 s -1 . For neutron activation analysis both reactors are used and k0-NAA method has been implemented. At INR Pitesti a prompt gamma ray neutron activation analysis devices has been designed, manufactured ant put into operation. For nuclear materials properties investigation neutron radiography methods was developed in INR. For these purposes two neutron radiography devices were manufacture, one of them underwater and other one dry. The neutron beams are used for investigation of materials properties and components produced or under development for applications in the energy sector (fission and fusion). At TRIGA 14 MW reactor a neutron difractormeter and a SANS devices are available for material residual stress and texture measurements. TRIGA 14 MW reactor is used for medical and industrial radioisotopes production ( 131 I, 125 I, 192 Ir, etc) and a method for 99 Mo- 99 Tc production from fission is under developing. At INR Pitesti several special programmes for new types of nuclear fuel behavior characterization are under development. (author)

Testing of cross section libraries for TRIGA criticality benchmark

International Nuclear Information System (INIS)

Snoj, L.; Trkov, A.; Ravnik, M.

2007-01-01

Influence of various up-to-date cross section libraries on the multiplication factor of TRIGA benchmark as well as the influence of fuel composition on the multiplication factor of the system composed of various types of TRIGA fuel elements was investigated. It was observed that keff calculated by using the ENDF/B VII cross section library is systematically higher than using the ENDF/B-VI cross section library. The main contributions (∼ 2 20 pcm) are from 235 U and Zr. (author)

The evaluation of isotopic composition for TRIGA 14 MW spent fuel

International Nuclear Information System (INIS)

Covaci, St.; Toma, C.; Preda, M.

2008-01-01

In the summer of 1999 year, a first shipment of TRIGA HEU spent fuel to INEEL U.S.A. has taken place. he TRIGA HEU fuel was burned in the TRIGA steady state 14 MW reactor between 1980 and 1996 years. At the moment of prepared documentation for the shipment (July 1999), the evaluation of isotopic composition was calculated with ORIGEN-2 code with an irradiation history adequately prepared. Subsequently (May - June 2000), the evaluation was repeated with SAS2H module of SCALE 4.4a system. In the paper the results and the comparisons of the codes are presented, and the accuracy and convenient application of SCALE 4.4a system are emphasized. (authors)

Macroscopic quantum tunneling in 1 μm Nb junctions below 100mK

International Nuclear Information System (INIS)

Voss, R.F.; Webb, R.A.

1981-01-01

The transition probabilities out of the superconducting state of low current density 1 μm Nb Josephson junctions with capacitance < 0.15 pF have been measured as a function of temperature T down to 3 mK. Below 100 mK the distribution widths become independent of T. Junctions with critical currents that differ by an order of magnitude have the same dependence of relative width on T. The low T results are interpreted in terms of quantum tunneling of the (macroscopic) junction phase. The observed low temperature widths are smaller than expected indicating the necessity of corrections to the simple WKB tunneling rates. (orig.)

Reference design (MK-I and MK-II) for experimental multi-purpose VHTR

International Nuclear Information System (INIS)

Miyamoto, Yoshiaki; Suzuki, Kunihiko; Sato, Sadao

1975-10-01

This report summarizes the results of a study on thermal and mechanical performances of the core, which are obtained in course of reference design (Mk-I and Mk-II) for the experimental multi-purpose VHTR: (1) Design criteria, design methods and design data. These bases are also discussed in order to refer in the case of proceeding a next design work. (2) The results of performance analysis such as the initial core and its prediction for the irradiated core. (auth.)

Characterization of the TRIGA Mark III reactor for k0-neutron activation analysis

International Nuclear Information System (INIS)

Diaz R, O.; Herrera P, E.; Lopez R, M.C.

1997-01-01

The non-ideality of the epithermal neutron flux distribution in a a reactor site parameter (α), the thermal-to-epithermal neutron ratio (f), the irradiation channel neutron temperature (T n ) and the k 0 -factors for more than 20 isotopes were determined in the 3 typical irradiation positions of the TRIGA Mark III reactor of the National Nuclear Research Institute, Salazar, Mexico, using different experimental methods with conventional and non-conventional monitors. This characterization is used in the k 0 -method of NAA, recently introduced at the Institute. (author). 21 refs., 3 figs., 5 tabs

Environmental radiation monitoring from the decommission of TRIGA

Energy Technology Data Exchange (ETDEWEB)

Choi, Geun Sik; Lee, Chang Woo

2000-03-01

Environmental radiation monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around TRIGA Research Reactor. The results of environmental radiation monitoring around TRIGA Research Reactor are the follows: The average level of environmental radiation measured by potable ERM and accumulated radiation dose by TLD was almost same level compared with thepast years. Gross {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. but only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. (author)

Survey of nuclear parameters from the TRIGA Mark I IPR R1 Brazilian reactor with concentric configuration aiming the application of K{sub 0} neutron activation technique; Levantamento de parametros nucleares do reator TRIGA Mark I IPR R1 com configuracao concentrica visando a aplicacao da tecnica de ativacao neutronica K{sub 0}

Energy Technology Data Exchange (ETDEWEB)

Franco, Milton Batista

2006-07-01

This research intended to determine the nuclear parameters a, f, spectral index and neutron temperature in several irradiations positions of the TRIGA Mark 1 IPR-R1 reactor, for use on the parametric method K{sub 0} in the CDTN. K{sub 0} is a monostandard method of neutron activation analysis. It is, on the whole, experimentally simple, flexible and an important tool for accurate and convenient standardization in instrumental multi-element analysis. At the time the parameters were determined at the rotatory rack, lower layer and in the central thimble: alpha was calculated applying the three bare monitor method using {sup 197}Au, {sup 94}Zr and {sup 96}Zr; f determination was done according to the bare bi-isotopic method; neutron temperature was calculated through the direct method using {sup 176}Lu, {sup 94}Zr, {sup 96}Zr and {sup 197}Au and the Westcott's g(Tn) function for the {sup 176}Lu was calculated and the result was interpolated in the Grintakis and Kim (1975) Table, determining the neutron temperature. The procedure to check the parameters consisted in using standard solutions of Au (metal foil, NBS), Lu (LuO{sub 2}, Johnson Mattey Company - JMC) and Zr (ZrO{sub 2} and metal foil, Johnson Mattey Company 99,99% and Zry - 4: 98,14% of Zr, National Bureau of Standard- NBS). Several certified reference materials and two samples of intercomparisons (samples of sediment of the IAEA/ARCAL XXVI project) have been analysed by means of k{sub 0}- INAA in order to verify the efficiency of the method and the quality of the parameters. The certified reference materials were: GXR-2, GXR-5 and GXR-6 of the United States Geological Survey (USGS) and Soil-5, Soil-7 and SL-1 of the International Atomic Energy Agency (IAEA). (author)

International Atomic Energy Agency. Highlights of activities. September 1993

International Nuclear Information System (INIS)

Gillen, V.A.

1993-09-01

This document describes the most important activities of the International Atomic Energy Agency during the period September 1992 - September 1993, in particular in the following areas: (i) nuclear power; (ii) nuclear fuel cycle; (iii) radioactive waste management; (iv) comparative assessment of energy sources; (v) IAEA laboratory activities; (vi) nuclear applications in the food industry and in agriculture; (vii) human health applications of nuclear techniques, especially in the treatment and prevention of diseases and in the analysis of health problems related to the environment; (viii) industry and earth sciences; (ix) physical and chemical sciences; (x) radiation protection; (xi) safety of nuclear installations; (xii) safeguards and non-proliferation activities; (xiii) activities in the area of public and technical information such as the International Nuclear Information System (INIS) and other IAEA computerized databases and reference systems, the publication Nuclear Fusion, a monthly scientific journal of articles on thermonuclear fusion research and development, and the organization of meetings on atomic energy; and (xiv) a description of the Agency's technical assistance activities, including financial data

Boiling burnout in the inner annulus of the MK-IV fuel configuration containing ''W'' spring supports

International Nuclear Information System (INIS)

McSweeney, T.I.; Thorne, W.L.; Fitzsimmons, D.E.; Anderson, J.K.

1978-09-01

The establishment of reactor power limits for the NPR is based, to some extent, on the burnout heat transfer results obtained from electrically heated hydraulic models of the reactor coolant passages. Past tests have shown that the outer surface of the middle annulus of the MK-IV fuel configuration goes into burnout before any other surface. Past models have contained no supports in the region where burnout has occurred, yet the reactor configuration must contain supports. The primary purpose of this study is to determine the support influence on the location and magnitude of the burnout heat flux. A second purpose is to establish burnout limits at higher coolant enthalpies. A 2-foot long electrically heated model of the coolant passage, containing supports, has been tested in the high pressure loop of the Thermal Hydraulics Laboratory. Although several supports were located in the active region, a ''W'' spring support was placed in at the channel location where burnout occurred in previous test sections. Thus, the influence of this support has been determined experimentally. Analytically, it has been possible to extend this information to other possible configurations at low quality. A suggested method for using these initial high quality data in the setting of the reactor operating limits is presented

Report to the International Atomic Energy Agency

International Nuclear Information System (INIS)

Woznicka, U.

1986-07-01

The results of research done under the International Atomic Energy Agency Contract no 4121/RB: 'Measurement of the thermal neutron macroscopic absorption cross-section on small samples' at the Institut of Nuclear Physics during the period from July 1, 1985 to June 30, 1986 are presented. The research was based on the Plexiglass thermal neutron diffusion parameters and on the method of preparation of the rock samples for the measurements according to the INP method. Three rock samples delivered by the IAEA: Ottawa Sand, Royer Dolomite and Dunite Sand have been measured. (author)

A spare-parts inventory program for TRIGA reactors

Energy Technology Data Exchange (ETDEWEB)

Anderson, T V; Ringle, J C; Johnson, A G [Oregon State University (United States)

1974-07-01

As is fairly common with new reactor facilities, we had a few spare parts on hand as part of our original purchase when the OSU TRIGA first went critical in March of 1967. Within a year or so, however, it became apparent that we should critically examine our spare parts inventory in order to avoid unnecessary or prolonged outages due to lack of a crucial piece of equipment. Many critical components (those which must be present and operable according to our license or technical specifications) were considered, and a priority list of acquiring these was established. This first list was drawn up in March, 1969, two years after initial criticality, and some key components were ordered. The availability of funds was the overriding restriction then and now. This spare-parts list is reviewed and new components purchased annually; the average amount spent has been about $2,000 per year. This inventory has proved invaluable more than once; without it, we would have had lengthy shutdowns awaiting the arrival of the needed component. The sobering thought, however, is that our spare-parts inventory is still not complete-far from it, in fact, because this would be prohibitively expensive. It is very difficult to guess with 100% accuracy just which component might need replacing, and your $10,000 inventory of spare parts is useless in that instance if it doesn't include the needed part. An idea worth considering is to either (a) encourage General Atomic, through the collective voice of all TRIGA owners, to maintain a rather complete inventory of replacement parts, or (b) maintain an owner's spare-parts pool, financed by contributions from all the facilities. If either of these pools was established, the needed part could reach any facility within the U.S. within a few days, minimizing reactor outage time. (author)

A spare-parts inventory program for TRIGA reactors

International Nuclear Information System (INIS)

Anderson, T.V.; Ringle, J.C.; Johnson, A.G.

1974-01-01

As is fairly common with new reactor facilities, we had a few spare parts on hand as part of our original purchase when the OSU TRIGA first went critical in March of 1967. Within a year or so, however, it became apparent that we should critically examine our spare parts inventory in order to avoid unnecessary or prolonged outages due to lack of a crucial piece of equipment. Many critical components (those which must be present and operable according to our license or technical specifications) were considered, and a priority list of acquiring these was established. This first list was drawn up in March, 1969, two years after initial criticality, and some key components were ordered. The availability of funds was the overriding restriction then and now. This spare-parts list is reviewed and new components purchased annually; the average amount spent has been about $2,000 per year. This inventory has proved invaluable more than once; without it, we would have had lengthy shutdowns awaiting the arrival of the needed component. The sobering thought, however, is that our spare-parts inventory is still not complete-far from it, in fact, because this would be prohibitively expensive. It is very difficult to guess with 100% accuracy just which component might need replacing, and your $10,000 inventory of spare parts is useless in that instance if it doesn't include the needed part. An idea worth considering is to either (a) encourage General Atomic, through the collective voice of all TRIGA owners, to maintain a rather complete inventory of replacement parts, or (b) maintain an owner's spare-parts pool, financed by contributions from all the facilities. If either of these pools was established, the needed part could reach any facility within the U.S. within a few days, minimizing reactor outage time. (author)

Environment, 1986-1997. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1998-04-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Environment and issued during the period of 1986-1997. Some earlier titles which form part of an established series or are still considered of importance have been included. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain papers in languages other than English, but all of these papers have abstracts in English

5. TRIGA owners' conference. Papers and abstracts

International Nuclear Information System (INIS)

1977-01-01

The main topics of the Conference are: research reactor licensing and regulation; standards and public relations programs; operating problems and operating programs of research reactors; security requirements for TRIGA reactors

Evaluation of caesium atomic fountain NICT-CsF1

International Nuclear Information System (INIS)

Kumagai, M.; Ito, H.; Kajita, M.; Hosokawa, M.

2008-01-01

In this paper, we describe the first caesium atomic fountain primary frequency standard NICT-CsF1 of National Institute of Information Communications Technology (NICT) in Tokyo, Japan. The structure of the NICT-CsF1 system and evaluation procedure of the systematic frequency shifts and their uncertainties are presented. Typically, NICT-CsF1 has a frequency stability of 4 * 10 -13 /τ 1/2 and a frequency uncertainty of 1.9 * 10 -15 . (authors)

Generic Procedures for Response to a Nuclear or Radiological Emergency at Triga Research Reactors. Attachment 1 (2011)

International Nuclear Information System (INIS)

2011-01-01

The publication provides guidance for response to emergencies at TRIGA research reactors in Threat Category II and III. It contains information on the unique behaviour of TRIGA fuel during accident conditions; it describes design characteristics of TRIGA research reactors and provides specific symptom-based emergency classification for this type of research reactor. This publication covers the determination of the appropriate emergency class and protective actions for a nuclear or radiological emergency at TRIGA research reactors. It does not cover nuclear security at TRIGA research reactors. The term 'threat category' is used in this publication as described in Ref. [6] and for the purposes of emergency preparedness and response only; this usage does not imply that any threat, in the sense of an intention and capability to cause harm, has been made in relation to facilities, activities or sources. The threat category is determined by an analysis of potential nuclear and radiological emergencies and the associated radiation hazard that could arise as a consequence of those emergencies. STRUCTURE. The attachment consists of an introduction which defines the background, objective, scope and structure, two sections covering technical aspects and appendices. Section 2 describes the characteristics of TRIGA fuel in normal and accident conditions. Section 3 contains TRIGA research reactor specific emergency classification tables for Threat Category II and III. These tables should be used instead of the corresponding emergency classification tables presented in Ref. [1] while developing the emergency response arrangements at TRIGA research reactors. The appendices present some historical overview and typical general data for TRIGA research reactor projects and the list of TRIGA installations around the world. The terms used in this document are defined in the IAEA Safety Glossary and the IAEA Code of Conduct on the Safety of Research Reactors.

A 20mK temperature sensor

International Nuclear Information System (INIS)

Wang, N.; Sadoulet, B.; Shutt, T.

1987-11-01

We are developing a 20mK temperature sensor made of neutron transmutation doped (NTD) germanium for use as a phonon detector in a dark matter search. We find that NTD germanium thermistors around 20mK have resistances which are a strong function of temperature, and have sufficient sensitivity to eventually reach a base line rms energy fluctuation of 6eV at 25mK. Further work is needed to understand the extreme sensitivity of the thermistors to bias power. 13 refs., 18 figs

Qualitative assessment of the value of the Ohio State University TRIGA reactor

International Nuclear Information System (INIS)

Binney, S.E.; Johnson, A.G.

1989-01-01

The Oregon State University (OSU) TRIGA Reactor (OSTR) is a major regional research, training, and service facility. The OSTR supports a wide variety of organizations at the local, state, regional, national, and international levels. Examples of usage of the OSTR are given in this paper to serve as a basis for assessing the value of the OSTR to its user organizations. It is difficult to assess the value of a facility such as the OSTR quantitatively, primarily because a dollar value cannot be assigned to many of the services that the OSTR performs, e.g., forensic analysis to assist police agencies in criminal cases. Significant qualitative statements can be made, however, to demonstrate the fact that the value of a research reactor facility such as the OSTR substantially outweighs the capital and operating costs of such a facility. Analysis of the data presented above clearly indicates that the value of the OSTR facility is overwhelmingly positive, i.e., the benefits associated with the services provided by the OSTR facility outweigh the cost of providing such services by perhaps as much as an order of magnitude

Oregon State University TRIGA Reactor annual report

Energy Technology Data Exchange (ETDEWEB)

Anderson, T.V.; Johnson, A.G.; Bennett, S.L.; Ringle, J.C.

1979-08-31

The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included.

Oregon State University TRIGA Reactor annual report

International Nuclear Information System (INIS)

Anderson, T.V.; Johnson, A.G.; Bennett, S.L.; Ringle, J.C.

1979-01-01

The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included

Prototypic fabrication of TRIGA irradiated fuel shipping casks

International Nuclear Information System (INIS)

Kim, B.K.; Lee, Y.W.; Whang, C.K.; Lee, J.B.

1980-01-01

This is the safety analysis report on the prototypic fabrication of ''TRIGA Irradiated Fuel Shipping Cask'' conducted by KAERI in 1980. The results of the evaluation show that the shipping cask is in compliance with the applicable regulation for the normal conditions of transport as well as hypothetical accident conditions. The prototypic fabrication of the shipping cask (type B) was carried out for the first time in Korea after getting technical experience from fabrication of the ''TRIGA Spent Fuel Shipping Cask'' and ''the KO-RI Unit 1 surveillance capsule shipping cask'' in 1979. This report contains structural evaluation, thermal evaluation, shielding, criticality, quality assurance, and handling procedures of the shipping cask

Environmental radiation monitoring from the decommission of TRIGA

Energy Technology Data Exchange (ETDEWEB)

Choi Geun Sik; Lee, Chang Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-02-01

Environmental Radiation Monitoring was carried out with measurement of environment radiation and environment radioactivity analysis around TRIGA Research Reactor. The results of environmental radiation monitoring around TRIGA Research Reactor are the follows: The average level of environmental radiation dose measured by potable ERM and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {beta} radioactivity in environmental samples showed a environmental level. v-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. 37 refs., 12 figs., 31 tabs. (Author)

76 FR 11410 - Defense Federal Acquisition Regulation Supplement; Increase the Use of Fixed-Price Incentive...

Science.gov (United States)

2011-03-02

... military departments and directors of defense agencies on obtaining greater efficiency and productivity in defense spending. In support of this initiative, DoD is proposing to amend DFARS subpart 216.4 to require...

Characterization of the TRIGA Mark II reactor full-power steady state

Energy Technology Data Exchange (ETDEWEB)

Cammi, Antonio, E-mail: antonio.cammi@polimi.it [Politecnico di Milano – Department of Energy, CeSNEF (Enrico Fermi Center for Nuclear Studies), via La Masa 34, 20156 Milano (Italy); Zanetti, Matteo [Politecnico di Milano – Department of Energy, CeSNEF (Enrico Fermi Center for Nuclear Studies), via La Masa 34, 20156 Milano (Italy); Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica [University of Milano-Bicocca, Physics Department “G. Occhialini” and INFN Section, Piazza dell’Ateneo Nuovo, 20126 Milan (Italy); Magrotti, Giovanni; Prata, Michele; Salvini, Andrea [University of Pavia, Applied Nuclear Energy Laboratory (L.E.N.A.), Via Gaspare Aselli 41, 27100 Pavia (Italy)

2016-04-15

Highlights: • Full-power steady state characterization of the TRIGA Mark II reactor. • Monte Carlo and Multiphysics simulation of the TRIGA Mark II reactor. • Sub-cooled boiling effects in the TRIGA Mark II reactor. • Thermal feedback effects in the TRIGA Mark II reactor. • Experimental data based validation. - Abstract: In this paper, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor at the University of Pavia is achieved by coupling the Monte Carlo (MC) simulation for neutronics with the “Multiphysics” model for thermal-hydraulics. Neutronic analyses have been carried out with a MCNP5 based MC model of the entire reactor system, already validated in fresh fuel and zero-power configurations (in which thermal effects are negligible) and using all available experimental data as a benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core must be established. To evaluate this, a thermal-hydraulic model has been developed, using the power distribution results from the MC simulation as input. The thermal-hydraulic model is focused on the core active region and takes into account sub-cooled boiling effects present at full reactor power. The obtained temperature distribution is then entered into the MC model and a benchmark analysis is carried out to validate the model in fresh fuel and full-power configurations. An acceptable correspondence between experimental data and simulation results concerning full-power reactor criticality proves the reliability of the adopted methodology of analysis, both from the perspective of neutronics and thermal-hydraulics.

Development of a standard data base for FBR core nuclear design. 10. Reevaluation of atomic number density of JOYO Mk-II core

Energy Technology Data Exchange (ETDEWEB)

Numata, Kazuyuki; Sato, Wakaei [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Ishikawa, Makoto; Arii, Yoshio [Nuclear Energy System Incorporation, Tokyo (Japan)

1999-07-01

The material composition of JOYO Mk-II core components in its initial core was reevaluated as a part of the effort for developing a standard data base for FBR core nuclear design. The special feature of the reevaluation is to treat the decay of Pu-241 isotope, so that the atomic number densities of Pu-241 and Am-241 in fuel assemblies can be exactly evaluated on the initial critical date, Nov. 22nd, 1982. Further, the atomic number densities of other core components were also evaluated to improve the analytical accuracy. Those include the control rods which were not so strictly evaluated in the past, and the dummy fuels and the neutron sources which were not treated in the analytical model so far. The results of the present reevaluation were as follows: (1) The changes of atomic number densities of the major nuclides such as Pu-239, U-235 and U-238 were about {+-}0.2 to 0.3%. On the other hand, the number density of Pu-241, which was the motivation of the present work, was reduced by 12%. From the fact, the number densities in the past analysis might be based on the isotope measurement of the manufacturing point of time without considering the decay of Pu-241. (2) As the other core components, the number densities of control rods and outer reflector-type A were largely improved. (author)

Inter-atomic force constants of BaF{sub 2} by diffuse neutron scattering measurement

Energy Technology Data Exchange (ETDEWEB)

Sakuma, Takashi, E-mail: sakuma@mx.ibaraki.ac.jp; Makhsun,; Sakai, Ryutaro [Institute of Applied Beam Science, Ibaraki University, Mito 310-8512 (Japan); Xianglian [College of Physics and Electronics Information, Inner Mongolia University for the Nationalities, Tongliao 028043 (China); Takahashi, Haruyuki [Institute of Applied Beam Science, Ibaraki University, Hitachi 316-8511 (Japan); Basar, Khairul [Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Bandung 40132 (Indonesia); Igawa, Naoki [Quantum Beam Science Directorate, Japan Atomic Energy Agency, Tokai 319-1195 (Japan); Danilkin, Sergey A. [Bragg Institute, Australian Nuclear Science and Technology Organisation, Kirrawee DC NSW 2232 (Australia)

2015-04-16

Diffuse neutron scattering measurement on BaF{sub 2} crystals was performed at 10 K and 295 K. Oscillatory form in the diffuse scattering intensity of BaF{sub 2} was observed at 295 K. The correlation effects among thermal displacements of F-F atoms were obtained from the analysis of oscillatory diffuse scattering intensity. The force constants among neighboring atoms in BaF{sub 2} were determined and compared to those in ionic crystals and semiconductors.

Effective atomic numbers (Z_e_f_f) of based calcium phosphate biomaterials: a comparative study

International Nuclear Information System (INIS)

Fernandes Zenobio, Madelon Aparecida; Gonçalves Zenobio, Elton; Silva, Teógenes Augusto da; Socorro Nogueira, Maria do

2016-01-01

This study determined the interaction of radiation parameters of four biomaterials as attenuators to measure the transmitted X-rays spectra, the mass attenuation coefficient and the effective atomic number by spectrometric system comprising the CdTe detector. The biomaterial BioOss"® presented smaller mean energy than the other biomaterials. The μ/ρ and Z_e_f_f of the biomaterials showed their dependence on photon energy. The data obtained from analytical methods of x-ray spectra, µ/ρ and Z_e_f_f_, using biomaterials as attenuators, demonstrated that these materials could be used as substitutes for dentin, enamel and bone. Further, they are determinants for the characterization of the radiation in tissues or equivalent materials. - Highlights: • Measure of the transmitted x-rays spectra using based calcium phosphate biomaterials as attenuators. • Determination effective atomic number using four dental biomaterials. • Determination of the mass attenuation coefficient (µ/ρ) of the biomaterials samples calculated by the WinXCOM software. • Determination of the chemical composition of calcium phosphate biomaterials.

Safety Evakuation Of Triga-2000 Reactor Operation Viewed From Safety Culture

International Nuclear Information System (INIS)

Karliana, Itjeu

2001-01-01

The safety evaluation activities of TRIGA-2000 operation viewed from safety culture performed by questioners data collected from the operators and supervisor site of TRIGA-2000 P3TN, Bandung. There are 9 activity aspects surveyed, for instant to avail the policy of safety from their chairman, safety management, education and training, emergency aids planning, safety consultancy, accident information, safety analysis, safety devices, safety and occupational health. The surveying undertaken by filling the questioner that containing of 9 activity aspects and 20 samples of employees. The safety evaluation results' of the operation personnel in TRIGA-2000 P3TN are good implemented by both the operators and supervisors should be improve and attention need to provide the equipment's. The education and training especially for safety refreshment must be performing

TRIGA out of core gamma irradiation facility

International Nuclear Information System (INIS)

Rant, J.; Pregl, G.

1988-01-01

A possibility to irradiate extended objects in a gamma field inside the shielding water tank and above the core of operating TRIGA Mark II Reactor has been investigated. The irradiation cask is shielded with Cd cover to filter out thermal neutrons. The dose rate of the gamma field strongly depends on the distance of the irradiation position above the core. At 25 cm above the core, the gamma dose rate is 2.2 Gy/s and epithermal neutron flux is ∼ 8.10 6 ncm -2 s -1 ∼ 3 as measured by TLD (CaF 2 : Mn) dosimeters and Au foils respectively. Tentative applications of the gamma irradiation facility are in the studies of radiation induced accelerated aging and within the Nuclear Power Plant Equipment Qualification Program (EQP). A complete characterization of the neutron spectrum and optimization of the 7 radiation field within the cask has still to be performed. (author)

Ten years of TRIGA reactor research at the University of Texas

International Nuclear Information System (INIS)

O'Kelly, Sean

2002-01-01

The 1 MW TRIGA Research Reactor at the Nuclear Engineering Teaching Laboratory is the second TRIGA at the University of Texas at Austin (UT). A small (10 kW-1963, 250 kW-1968) TRIGA Mark I was housed in the basement of the Engineering Building until is was shutdown and decommissioned in 1989. The new TRIGA Mark II with a licensed power of 1.1 MW reached initial criticality in 1992. Prior to 1990, reactor research at UT usually consisted of projects requiring neutron activation analysis (NAA) but the step up to a much larger reactor with neutron beam capability required additional personnel to build the neutron research program. The TCNS is currently used to perform Prompt Gamma Activation Analysis to determine hydrogen and boron concentrations of various composite materials. The early 1990s was a very active period for neutron beam projects at the NETL. In addition to the TCNS, a real-time neutron radiography facility (NIF) and a high-resolution neutron depth profiling facility (NDP) were installed in two separate beam ports. The NDP facility was most recently used to investigate alpha damage on stainless steel in support of the U.S. Nuclear Weapons Stewardship programs. In 1999, a sapphire beam filter was installed in the NDP system to reduce the fast neutron flux at the sample location. A collaborative effort was started in 1997 between UT-Austin and the University of Texas at Arlington to build a reactor-based, low-energy positron beam (TIPS). The limited success in obtaining funding has placed the project on hold. The Nuclear and Radiation Engineering Program has grown rapidly and effectively doubled in size over the past 5 years but years of low nuclear research funding, an overall stagnation in the U.S. nuclear power industry and a persuasive public distrust of nuclear energy has caused a precipitous decline in many programs. Recently, the U.S. DOE has encouraged University Research Reactors (URR) in the U.S. to collaborate closely together by forming URR

Thirteen[th] European TRIGA users conference. Proceedings

International Nuclear Information System (INIS)

1994-01-01

The conference covers topic related to TRIGA reactor, such as reactor operation and maintenance experience - safety aspects; research activities and applications; boron neutron capture therapy (BNCT) projects and other design operational and safety issues

The UK MK III GCR experimental physics programme at AEE Winfrith

Energy Technology Data Exchange (ETDEWEB)

Johnstone, I

1972-06-15

The UK programme of reactor physics experiments in support of the Mk III GCR project started in 1968/69 and has now reached its third main phase. The overall programme is broadly summarised in this report.

Survey of nuclear parameters from the TRIGA Mark I IPR R1 Brazilian reactor with concentric configuration aiming the application of K0 neutron activation technique

International Nuclear Information System (INIS)

Franco, Milton Batista

2006-01-01

This research intended to determine the nuclear parameters a, f, spectral index and neutron temperature in several irradiations positions of the TRIGA Mark 1 IPR-R1 reactor, for use on the parametric method K 0 in the CDTN. K 0 is a monostandard method of neutron activation analysis. It is, on the whole, experimentally simple, flexible and an important tool for accurate and convenient standardization in instrumental multi-element analysis. At the time the parameters were determined at the rotatory rack, lower layer and in the central thimble: alpha was calculated applying the three bare monitor method using 197 Au, 94 Zr and 96 Zr; f determination was done according to the bare bi-isotopic method; neutron temperature was calculated through the direct method using 176 Lu, 94 Zr, 96 Zr and 197 Au and the Westcott's g(Tn) function for the 176 Lu was calculated and the result was interpolated in the Grintakis and Kim (1975) Table, determining the neutron temperature. The procedure to check the parameters consisted in using standard solutions of Au (metal foil, NBS), Lu (LuO 2 , Johnson Mattey Company - JMC) and Zr (ZrO 2 and metal foil, Johnson Mattey Company 99,99% and Zry - 4: 98,14% of Zr, National Bureau of Standard- NBS). Several certified reference materials and two samples of intercomparisons (samples of sediment of the IAEA/ARCAL XXVI project) have been analysed by means of k 0 - INAA in order to verify the efficiency of the method and the quality of the parameters. The certified reference materials were: GXR-2, GXR-5 and GXR-6 of the United States Geological Survey (USGS) and Soil-5, Soil-7 and SL-1 of the International Atomic Energy Agency (IAEA). (author)

Establishment of 'Japan Atomic Energy Agency'. Its role and expectation

International Nuclear Information System (INIS)

Nakahara, Toru; Itakura, Shuichiro; Shiozawa, Shusaku; Hino, Ryutaro; Fujii, Yasuhiko; Sakurada, Michio; Kimura, Itsuro; Kikuyama, Kaoru

2005-01-01

In October 2005, the Japan Atomic Energy Agency (JAEA) was established as an independent administrative institution with the integration of the Japan Atomic Energy Research Institute (JAERI) and the Japan Nuclear Cycle Development Institute (JNC). JAEA is the only institute in Japan dedicated to comprehensive research and development in the field of nuclear energy. This paper put together a special article on its role and expectation. Firstly the essentials of comprehensive nuclear research and its future perspective were discussed mainly based on 'Framework for Nuclear Energy Policy' of the Atomic Energy Commission of Japan. Eight articles were followed on specific items such as quantum beams utilization, hydrogen production with nuclear heat, neutron science and ITER project, and put stress on joint works and smooth transfer of related technology to the private sector. (T. Tanaka)

Computer code for the thermal-hydraulic analysis of ITU TRIGA Mark-II reactor

International Nuclear Information System (INIS)

Ustun, G.; Durmayaz, A.

2002-01-01

Istanbul Technical University (ITU) TRIGA Mark-II reactor core consists of ninety vertical cylindrical elements located in five rings. Sixty-nine of them are fuel elements. The reactor is operated and cooled with natural convection by pool water, which is also cooled and purified in external coolant circuits by forced convection. This characteristic leads to consider both the natural and forced convection heat transfer in a 'porous-medium analysis'. The safety analysis of the reactor requires a thermal-hydraulic model of the reactor to determine the thermal-hydraulic parameters in each mode of operation. In this study, a computer code cooled TRIGA-PM (TRIGA - Porous Medium) for the thermal-hydraulic analysis of ITU is considered. TRIGA Mark-II reactor code has been developed to obtain velocity, pressure and temperature distributions in the reactor pool as a function of core design parameters and pool configuration. The code is a transient, thermal-hydraulic code and requires geometric and physical modelling parameters. In the model, although the reactor is considered as only porous medium, the other part of the reactor pool is considered partly as continuum and partly as porous medium. COMMIX-1C code is used for the benchmark purpose of TRIGA-PM code. For the normal operating conditions of the reactor, estimations of TRIGA-PM are in good agreement with those of COMMIX-1C. After some more improvements, this code will be employed for the estimation of LOCA scenario, which can not be analyses by COMMIX-1C and the other multi-purpose codes, considering a break at one of the beam tubes of the reactor

9. European TRIGA users' conference. Papers and abstracts

International Nuclear Information System (INIS)

1986-01-01

Operation and maintenance experience, new developments and improvements of TRIGA reactors, fuel management, radiation protection, licensing, uses for research and isotope production are discussed at the Conference

Analysis of Environmental Data During TRIGA 2000 Reactor Operation in PTNBR-BATAN Bandung

International Nuclear Information System (INIS)

Zulfakhri

2009-01-01

The radioactivity data of grass and soil obtained from environmental monitoring during 2000-2008 have been quantitatively and qualitatively analyzed. The data were analyzed using statistical method of the population homogeneity varians test and the average equality test, whereas qualitative analysis have been carried out by gamma spectrometry. From the data analysis, using homogeneity varians test (X 2 test) and average equality test (F test) it was obtained that X 2 calculation , F calculation > X 2 table , F table , so it can be assumed that operation of TRIGA 2000 reactor has no effect to the radioactivity of the environment. The qualitative analysis of grass and soil samples shows no visible peak of gamma ray from fission or activation products from the reactor, but the natural radionuclide such as 214 Bi, 228 Ac, 212 Bi, and 40 K were detected. It can be concluded that reactor operation have no effect to the environmental radioactivity. (author)

Photoassociation of cold metastable helium atoms

NARCIS (Netherlands)

Woestenenk, G.R.

2001-01-01

During the last decades the study of cold atoms has grown in a great measure. Research in this field has been made possible due to the development of laser cooling and trapping techniques. We use laser cooling to cool helium atoms down to a temperature of 1 mK and we are able to

PUSPATI Triga Reactor pulsing parameters

Energy Technology Data Exchange (ETDEWEB)

Auu, Gui Ah; Abu, Puad Haji; Yunus, Yaziz [PUSPATI, Selangor (Malaysia)

1984-06-01

The pulsing experiment was carried out as part of the commissioning activites of PUSPATI TRIGA Reactor (PTR). Several parameters of PTR were deduced from the experiment. It was found that the maximum temperature of the fuel was far below the safety limit when the maximum allowable positive reactivity of $3.00 was inserted into the core. The peak power achieved was 1354 Mw.

Annual report 2003[International Atomic Energy Agency

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The Annual Report reviews the results of the Agency's programme according to the three 'pillars' of technology, safety and verification. The main part of the report, starting on page 9, generally follows the programme structure as it applied in 2003. The introductory chapter, seeks to provide a thematic analysis, based on the three pillars, of the Agency's activities within the overall context of notable developments during the year. Additional information on specific issues can be found in the latest editions of the Agency's Nuclear Safety Review, Nuclear Technology Review and Technical Co-operation Report. This material is also available on the Agency's WorldAtom web site (http://www.iaea.org/Worldatom/Documents/Anrep/Anrep2003/). All sums of money are expressed in United States dollars. The designations employed and the presentation of material in this document do not imply the expression of any opinion whatsoever on the part of the Secretariat concerning the legal status of any country or territory or of its authorities, or concerning the delimitation of its frontiers. The topics covered in the chapter related to Technology are: Nuclear Power; Nuclear Fuel Cycle and Material Technologies; Analysis for Sustainable Energy Development; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications. Topics related to safety discussed in this report are: Safety of Nuclear Installations; Radiation Safety; Management of Radioactive Waste; Security of Material. Topics related to Verification are Safeguards and Verification in Iraq Pursuant to UNSC Resolutions. A separate chapter is devoted to Management of Technical Cooperation for Development.

A 30 mK, 13.5 T scanning tunneling microscope with two independent tips

Energy Technology Data Exchange (ETDEWEB)

Roychowdhury, Anita [Laboratory for Physical Sciences, College Park, Maryland 20742 (United States); Center for Nanophysics and Advanced Materials, Department of Physics, University of Maryland, College Park, Maryland 20740 (United States); Gubrud, M. A.; Dana, R.; Dreyer, M. [Laboratory for Physical Sciences, College Park, Maryland 20742 (United States); Anderson, J. R.; Lobb, C. J.; Wellstood, F. C. [Center for Nanophysics and Advanced Materials, Department of Physics, University of Maryland, College Park, Maryland 20740 (United States)

2014-04-15

We describe the design, construction, and performance of an ultra-low temperature, high-field scanning tunneling microscope (STM) with two independent tips. The STM is mounted on a dilution refrigerator and operates at a base temperature of 30 mK with magnetic fields of up to 13.5 T. We focus on the design of the two-tip STM head, as well as the sample transfer mechanism, which allows in situ transfer from an ultra high vacuum preparation chamber while the STM is at 1.5 K. Other design details such as the vibration isolation and rf-filtered wiring are also described. Their effectiveness is demonstrated via spectral current noise characteristics and the root mean square roughness of atomic resolution images. The high-field capability is shown by the magnetic field dependence of the superconducting gap of Cu{sub x}Bi{sub 2}Se{sub 3}. Finally, we present images and spectroscopy taken with superconducting Nb tips with the refrigerator at 35 mK that indicate that the effective temperature of our tips/sample is approximately 184 mK, corresponding to an energy resolution of 16 μeV.

A 30 mK, 13.5 T scanning tunneling microscope with two independent tips.

Science.gov (United States)

Roychowdhury, Anita; Gubrud, M A; Dana, R; Anderson, J R; Lobb, C J; Wellstood, F C; Dreyer, M

2014-04-01

We describe the design, construction, and performance of an ultra-low temperature, high-field scanning tunneling microscope (STM) with two independent tips. The STM is mounted on a dilution refrigerator and operates at a base temperature of 30 mK with magnetic fields of up to 13.5 T. We focus on the design of the two-tip STM head, as well as the sample transfer mechanism, which allows in situ transfer from an ultra high vacuum preparation chamber while the STM is at 1.5 K. Other design details such as the vibration isolation and rf-filtered wiring are also described. Their effectiveness is demonstrated via spectral current noise characteristics and the root mean square roughness of atomic resolution images. The high-field capability is shown by the magnetic field dependence of the superconducting gap of CuxBi2Se3. Finally, we present images and spectroscopy taken with superconducting Nb tips with the refrigerator at 35 mK that indicate that the effective temperature of our tips/sample is approximately 184 mK, corresponding to an energy resolution of 16 μeV.

Synthesis and receptor binding studies of (+/-)1-iodo-MK-801

International Nuclear Information System (INIS)

Yang, D.J.; Ciliax, B.J.; Van Dort, M.E.; Gildersleeve, D.; Pirat, J.L.; Young, A.B.; Wieland, D.M.

1989-01-01

The glutamate analogue N-methyl-D-aspartate (NMDA) binds to a subset of glutamate receptors that are coupled to a voltage-sensitive cation channel. This NMDA-linked channel is the likely binding locus of the potent anticonvulsant MK-801. To develop single-photon emission computed tomography (SPECT) probes of this brain channel, we synthesized (+/)1-iodo-MK-801 and (+/-)1-[ 125 I]iodo-MK-801. The effect of (+/-)1-iodo-MK-801 on ligand binding to the NMDA-linked glutamate receptor site was assessed using a rat brain homogenate assay. (+/-)1-Iodo-MK-801 displaced the dissociative anesthetic ligand [ 3 H]N-[1-(2-thienyl)cyclohexyl]piperidine ([ 3 H]TCP) binding with an IC50 of 1 microM, which is a 10-fold lower binding affinity than that of (+/-)MK-801. In in vivo autoradiographic studies, (+/-)MK-801 failed to block selective uptake of (+/-)1-iodo-MK-801 in rat brain. These results suggest that (+/-)1-iodo-MK-801 may not be a suitable ligand for mapping NMDA-linked glutamate receptor channels

Defense Support of Civil Authorities - Are We Organized Right?

National Research Council Canada - National Science Library

Austin, Joseph

2007-01-01

The Department of Defense (DoD) has a long history of supporting civil authorities in the wake of catastrophic events with specialized skills and assets that can rapidly stabilize and improve the situation...

ENEA TRIGA RC-1 reactor activities in the fields of nuclear medicine and neutron radiography

International Nuclear Information System (INIS)

Chiesa, Gianni; Festinesi, Armando; Palomba, Mario; Rosa, Roberto; Rossi, Gabriela; Sangiovanni, Gino; Santoro, Emilio; Sedda, Antioco Franco; Storelli, Lucio

2008-01-01

In the last three years, TRIGA RC-1 plant staff is involved in collaborations with some roman hospitals for the production of particular radioisotopes for the diagnosis and therapy in the field of human cancer. Further, the thermal column of TRIGA reactor has been prepared for neutron radiography and tomography. For another channel, instruments and equipment above neutron radiography and tomography are in preparation phase. This paper includes an overview of the experimental equipment properly developed by TRIGA staff. (authors)

Reactor instrumentation renewal of the TRIGA reactor Vienna, Austria

International Nuclear Information System (INIS)

Boeck, H.; Weiss, H.; Hood, W.E.; Hyde, W.K.

1992-01-01

The TRIGA Mark-II reactor at the Atominstitut in Vienna, Austria is replacing its twenty-four year old instrumentation system with a microprocessor based control system supplied by General Atomics. Ageing components, new governmental safety requirements and a need for state of the art instrumentation for training students has spurred the demand for new reactor instrumentation. In Austria a government appointed expert is assigned the responsibility of reviewing the proposed installation and verifying all safety aspects. After a positive review, final assembly and checkout of the instrumentation system may commence. The instrumentation system consists of three basic modules: the control system console, the data acquisition console and the NH-1000 wide range channel. Digital communications greatly reduce interwiring requirements. Hardwired safety channels are independent of computer control, thus, the instrumentation system in no way relies on any computer intervention for safety function. In addition, both the CSC and DAC computers are continuously monitored for proper operation via watchdog circuits which are capable of shutting down the reactor in the event of computer malfunction. Safety channels include two interlocked NMP-1000 multi-range linear channels for steady state mode, an NPP-1000 linear safety channel for pulse mode and a set of three independent fuel temperature monitoring channels. The microprocessor controlled wide range NM- 1000 digital neutron monitor (fission chamber based) functions as a startup/operational channel, and provides all power level related Interlocks. The Atominstitut TRIGA reactor is configured for four modes of operation: manual mode, automatic mode (servo control), pulsing mode and square wave mode. Control of the standard control rods is via stepping motor control rod drives, which offers the operator the choice of which control rods are operated by the servo system in automatic and square wave model. (author)

75 FR 1567 - Defense Federal Acquisition Regulation Supplement; Foreign Participation in Acquisitions in...

Science.gov (United States)

2010-01-12

..., ammunition, or war materials) from the SC/CASA states to support operations in Afghanistan. The end of the... in Support of Operations in Afghanistan AGENCY: Department of Defense (DoD). ACTION: Proposed rule...

Dynamics and applications of excited cold atoms

NARCIS (Netherlands)

Claessens, B.J.

2006-01-01

In a Magneto-Optical Trap (MOT), realized for the first time in 1987, one can trap and cool neutral atoms to temperatures below a mK. The invention of this device caused a revolution in atomic physics. With an MOT collision and spectroscopy experiments could be performed with unprecedented accuracy.

75 FR 57906 - Membership of the Defense Contract Audit Agency Senior Executive Service Performance Review Boards

Science.gov (United States)

2010-09-23

... publication of this notice. FOR FURTHER INFORMATION CONTACT: Sandra L. Burrell, Chief, Human Resources Management Division, Defense Contract Audit Agency, 8725 John J. Kingman Road, Suite 2133, Fort Belvoir... following are the names and titles of DCAA career executives appointed to serve as members of the DCAA...

76 FR 59664 - Membership of the Defense Contract Audit Agency Senior Executive Service Performance Review Boards

Science.gov (United States)

2011-09-27

... Date: Upon publication of this notice. FOR FURTHER INFORMATION CONTACT: Sandra L. Burrell, Chief, Human Resources Management Division, Defense Contract Audit Agency, 8725 John J. Kingman Road, Suite 2133, Fort...(c)(4), the following are the names and titles of DCAA career executives appointed to serve as...

Thermal hydraulic analysis of the IPR-R1 TRIGA reactor

International Nuclear Information System (INIS)

Veloso, Marcelo Antonio; Fortini, Maria Auxiliadora

2002-01-01

The subchannel approach, normally employed for the analysis of power reactor cores that work under forced convection, have been used for the thermal hydraulic evaluation of a TRIGA Mark I reactor, named IPR-R1, at 250 kW power level. This was accomplished by using the PANTERA-1P subchannel code, which has been conveniently adapted to the characteristics of natural convection of TRIGA reactors. The analysis of results indicates that the steady state operation of IPR-R1 at 250 kW do not imply risks to installations, workers and public. (author)

Defense Treaty Inspection Readiness Program

International Nuclear Information System (INIS)

Cronin, J.J.; Kohen, M.D.; Rivers, J.D.

1996-01-01

The Defense Treaty Inspection Readiness Program (DTIRP) was established by the Department of Defense in 1990 to assist defense facilities in preparing for treaty verification activities. Led by the On-Site Inspection Agency (OSIA), an element of the Department of Defense, DTIRP''s membership includes representatives from other Department of Defense agencies, the Department of Energy (DOE), the Central Intelligence Agency, the Federal Bureau of Investigation, the Department of Commerce, and others. The Office of Safeguards and Security has a significant interest in this program, due to the number of national defense facilities within its purview that are candidates for future inspections. As a result, the Office of Safeguards and Security has taken a very active role in DTIRP. This paper discusses the Office of Safeguards and Security''s increasing involvement in various elements of the DTIRP, ranging from facility assessments to training development and implementation

Shipment of TRIGA spent fuel to DOE's INEEL site - a status report

International Nuclear Information System (INIS)

Patterson, John; Viebrock, James; Shelton, Tom; Parker, Dixon

1998-01-01

DOE placed its transportation services contract with NAC International in April 1997 and awarded the first task to NAC for return of TRIGA fuel in July 1997. This initial shipment of TRIGA fuel, scheduled for early 1998, is reflective of many of the difficulties faced by DOE and the transportation services contractor in return of the foreign research reactor fuel to the United States: 1) First time use of the INEEL dry storage facility for receipt of research reactor fuel; 2) Safety analysis of the INEEL facility for the NAC-LWT shipping cask; 3) Cask certification for a mixed loading of high enriched and low enriched TRIGA fuels; 4) Cask loading for standard length and extended length rods (instrumented and fuel follower control rods); 5) Design and certification of a canister for degraded TRIGA fuel; 6) Initial port entry through the Naval Weapons Station in Concord, California; 7) Initial approval of the rail route for shipment from Concord to INEEL. In this presentation we describe the overall activities involved in the first TRIGA shipment, discuss the actions required to resolve the difficulties identified above, and provide a status report of the initial shipment from South Korea and Indonesia. Recommendations are presented as to actions that can be taken by the research reactor operator, by DOE, and by the transportation services agent to speed and simplify the transportation process. Actions having the potential to reduce costs to DOE and to reactor operators from high-income economies will be identified. (author)

Pharmacodynamics of Imipenem in Combination with β-Lactamase Inhibitor MK7655 in a Murine Thigh Model

Science.gov (United States)

Mavridou, Eleftheria; Melchers, Ria J. B.; van Mil, Anita C. H. A. M.; Mangin, E.; Motyl, Mary R.

2014-01-01

MK7655 is a newly developed beta-lactamase inhibitor of class A and class C carbapenemases. Pharmacokinetics (PK) of imipenem-cilastatin (IMP/C) and MK7655 were determined for intraperitoneal doses of 4 mg/kg to 128 mg/kg of body weight. MIC and pharmacodynamics (PD) studies of MK7655 were performed against several beta-lactamase producing Pseudomonas aeruginosa and Klebsiella pneumoniae strains to determine its effect in vitro and in vivo. Neutropenic mice were infected in each thigh 2 h before treatment with an inoculum of approximately 5 × 106 CFU. They were treated with IMP/C alone (every 2 hours [q2h], various doses) or in combination with MK7655 in either a dose fractionation study or q2h for 24 h and sacrificed for CFU determinations. IMP/MK7655 decreased MICs regarding IMP MIC. The PK profiles of IMP/C and MK7655 were linear over the dosing range studied and comparable with volumes of distribution (V) of 0.434 and 0.544 liter/kg and half-lives (t1/2) of 0.24 and 0.25 h, respectively. Protein binding of MK7655 was 20%. A sigmoidal maximum effect (Emax) model was fit to the PK/PD index responses. The effect of the inhibitor was not related to the maximum concentration of drug in serum (Cmax)/MIC, and model fits for T>MIC and area under the concentration-time curve (AUC)/MIC were comparable (R2 of 0.7 and 0.75), but there appeared to be no significant relationship of effect with dose frequency. Escalating doses of MK7655 and IMP/C showed that the AUC of MK7655 required for a static effect was dependent on the dose of IMP/C and the MIC of the strain, with a mean area under the concentration-time curve for the free, unbound fraction of the drug (fAUC) of 26.0 mg · h/liter. MK7655 shows significant activity in vivo and results in efficacy of IMP/C in otherwise resistant strains. The exposure-response relationships found can serve as a basis for establishing dosing regimens in humans. PMID:25403667

Operational parameters study of IPR-R1 TRIGA research reactor using virtual instruments

International Nuclear Information System (INIS)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares

2013-01-01

The instrumentation of nuclear reactors is designed with the principle of reliability, redundancy and diversification of control systems. Reliable monitoring of the parameters involved in the chain reaction is of great importance regarding efficiency and operational safety of the installation. The main goal of the simulation system in this proposed paper is to provide the study and improvement in understanding how these operational variables are interrelated and their behavior especially those related to neutronic and thermohydraulics. The work will be developed using the software LabVIEW ® (Laboratory Virtual Instruments Engineering Workbench). The program will enable the study of the variables involved in the operation of the installation throughout its operating range, for instance, a few mW up to 250 kW. The IPR-R1 TRIGA is a research nuclear reactor placed in open pool and cooled by light water with natural circulation. It is located at the Nuclear Technology Development Center (CDTN), in Belo Horizonte Brazil. The developing system employs the modern concept of virtual instruments (VIs), using microprocessors and visual interface on video monitors. LabVIEW ® breaks the paradigm of text-based programming language, for programming based on icons. The system will enable the use of this reactor in training and personnel training in the nuclear field. The work follows the recommendations of the International Atomic Energy Agency (IAEA), which has encouraged its members to develop strategic plans in order to use their research reactors. (author)

Operational parameters study of IPR-R1 TRIGA research reactor using virtual instruments

Energy Technology Data Exchange (ETDEWEB)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares, E-mail: ajp@cdtn.br, E-mail: amir@cdtn.br, E-mail: fsl@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2013-07-01

The instrumentation of nuclear reactors is designed with the principle of reliability, redundancy and diversification of control systems. Reliable monitoring of the parameters involved in the chain reaction is of great importance regarding efficiency and operational safety of the installation. The main goal of the simulation system in this proposed paper is to provide the study and improvement in understanding how these operational variables are interrelated and their behavior especially those related to neutronic and thermohydraulics. The work will be developed using the software LabVIEW ® (Laboratory Virtual Instruments Engineering Workbench). The program will enable the study of the variables involved in the operation of the installation throughout its operating range, for instance, a few mW up to 250 kW. The IPR-R1 TRIGA is a research nuclear reactor placed in open pool and cooled by light water with natural circulation. It is located at the Nuclear Technology Development Center (CDTN), in Belo Horizonte Brazil. The developing system employs the modern concept of virtual instruments (VIs), using microprocessors and visual interface on video monitors. LabVIEW ® breaks the paradigm of text-based programming language, for programming based on icons. The system will enable the use of this reactor in training and personnel training in the nuclear field. The work follows the recommendations of the International Atomic Energy Agency (IAEA), which has encouraged its members to develop strategic plans in order to use their research reactors. (author)

Preliminary neutronic design of TRIGA Mark II Reactor

International Nuclear Information System (INIS)

Sarikaya, B.; Tombakoglu, M.; Cecen, Y.; Kadiroglu, O. K.

2001-01-01

It is very important to analyse the behaviour of the research reactors, since, they play a key role in developing the power reactor technology and radiation applications such as isotope generation for medical treatments. In this study, the neutronic behaviour of the TRIGA MARK II reactor, owned and operated by Istanbul Technical University is analysed by using the SCALE code system. In the analysis, in order to overcome the disadvantages of special TRIGA codes, such as TRIGAP, the SCALE code system is chosen to perform the calculations. TRIGAP and similar codes have limited geometrical (one-dimensional geometry) and cross sectional options (two-group calculations), however, SCALE has the capability of wider range of geometrical modelling capability (three-dimensional modelling is possible) and multi-group calculations are possible

Detection and location of leaking TRIGA fuel elements

International Nuclear Information System (INIS)

Bouchey, G.D.; Gage, S.J.

1970-01-01

Several TRIGA facilities have experienced difficulty resulting from cladding failures of aluminum clad TRIGA fuel elements. Recently, at the University of Texas at Austin reactor facility, fission product releases were observed during 250 kW operation and were attributed to a leaking fuel element. A rather extensive testing program has been undertaken to locate the faulty element. The used sniffer device is described, which provides a quick, easily constructed, and extremely sensitive means of locating leaking fuel elements. The difficulty at The University of Texas was compounded by extremely low levels and the sporadic nature of the releases. However, in the more typical situation, in which a faulty element consistently releases relatively large quantities of fission gas, such a device should locate the leak with little difficulty

Five years of operating the TRIGA Mainz reactor

International Nuclear Information System (INIS)

Benedict, Georg

1970-01-01

Considerable obstacles had to be surmounted before TRIGA MAINZ, first TRIGA reactor built in Germany, reached initial criticality in 1965. Subsequent five years' operation did not raise any major problems. The facility has proven quite reliable and particularly well suited for the purposes of the nuclear chemistry research program pursued at Mainz University. Extensive use is made of the pulse mode of operation. As a result, fuel elements are obviously somewhat overstressed, even though most pulses performed are of the 1.50 dollar size. Maximum licensed steady state power of 100 kW till now has met the requirements of most experiments. However, efforts are in progress to improve irradiation conditions by increasing the reactor power to 300 kW. (author)

Isothermal temperature reactivity coefficient measurement in TRIGA reactor

International Nuclear Information System (INIS)

Zagar, T.; Ravnik, M.; Trkov, A.

2002-01-01

Direct measurement of an isothermal temperature reactivity coefficient at room temperatures in TRIGA Mark II research reactor at Jozef Stefan Institute in Ljubljana is presented. Temperature reactivity coefficient was measured in the temperature range between 15 o C and 25 o C. All reactivity measurements were performed at almost zero reactor power to reduce or completely eliminate nuclear heating. Slow and steady temperature decrease was controlled using the reactor tank cooling system. In this way the temperatures of fuel, of moderator and of coolant were kept in equilibrium throughout the measurements. It was found out that TRIGA reactor core loaded with standard fuel elements with stainless steel cladding has small positive isothermal temperature reactivity coefficient in this temperature range.(author)

Sipping test update device for fuel elements cladding inspections in IPR-r1 TRIGA reactor

Energy Technology Data Exchange (ETDEWEB)

Rodrigues, R.R.; Mesquita, A.Z.; Andrade, E.P.D.; Gual, Maritza R., E-mail: rrr@cdtn.br, E-mail: amir@cdtn.br, E-mail: edson@cdtn.br, E-mail: maritzargual@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

It is in progress at the Centro de Desenvolvimento da Tecnologia Nuclear - CDTN (Nuclear Technology Development Center), a research project that aims to investigate possible leaks in the fuel elements of the TRIGA reactor, located in this research center. This paper presents the final form of sipping test device for TRIGA reactor, and results of the first experiments setup. Mechanical support strength tests were made by knotting device on the crane, charged with water from the conventional water supply, and tests outside the reactor pool with the use of new non-irradiated fuel elements encapsulated in stainless steel, and available safe stored in this unit. It is expected that tests with graphite elements from reactor pool are done soon after and also the test experiment with the first fuel elements in service positioned in the B ring (central ring) of the reactor core in the coming months. (author)

Sipping test update device for fuel elements cladding inspections in IPR-r1 TRIGA reactor

International Nuclear Information System (INIS)

Rodrigues, R.R.; Mesquita, A.Z.; Andrade, E.P.D.; Gual, Maritza R.

2015-01-01

It is in progress at the Centro de Desenvolvimento da Tecnologia Nuclear - CDTN (Nuclear Technology Development Center), a research project that aims to investigate possible leaks in the fuel elements of the TRIGA reactor, located in this research center. This paper presents the final form of sipping test device for TRIGA reactor, and results of the first experiments setup. Mechanical support strength tests were made by knotting device on the crane, charged with water from the conventional water supply, and tests outside the reactor pool with the use of new non-irradiated fuel elements encapsulated in stainless steel, and available safe stored in this unit. It is expected that tests with graphite elements from reactor pool are done soon after and also the test experiment with the first fuel elements in service positioned in the B ring (central ring) of the reactor core in the coming months. (author)

Fuel element burnup determination in HEU-LEU mixed TRIGA research reactor core

International Nuclear Information System (INIS)

Zagar, Tomaz; Ravnik, Matjaz

2000-01-01

This paper presents the results of a burnup calculations and burnup measurements for TRIGA FLIP HEU fuel elements and standard TRIGA LEU fuel elements used simultaneously in small TRIGA Mark II research reactor in Ljubljana, Slovenija. The fuel element burnup for approximately 15 years of operation was calculated with two different in house computer codes TRIGAP and TRIGLAV (both codes are available at OECD NEA Data Bank). The calculation is performed in one-dimensional radial geometry in TRIGAP and in two-dimensional (r,φ) geometry in TRIGLAV. Inter-comparison of results shows important influence of in-core water gaps, irradiation channels and mixed rings on burnup calculation accuracy. Burnup of 5 HEU and 27 LEU fuel elements was also measured with reactivity method. Measured and calculated burnup values are inter-compared for these elements (author)

5 CFR 3601.102 - Designation of separate agency components.

Science.gov (United States)

2010-01-01

... Service; (8) Defense Information Systems Agency; (9) Defense Intelligence Agency; (10) Defense Logistics Agency; (11) Defense Security Service; (12) Defense Threat Reduction Agency; (13) National Imagery and... outside sources and 5 CFR 2635.807 governing teaching, speaking and writing: (1) Armed Services Board of...

PUSPATI Triga Reactor pulsing parameters

International Nuclear Information System (INIS)

Gui Ah Auu; Puad Haji Abu; Yaziz Yunus

1984-01-01

The pulsing experiment was carried out as part of the commissioning activites of PUSPATI TRIGA Reactor (PTR). Several parameters of PTR were deduced from the experiment. It was found that the maximum temperature of the fuel was far below the safety limit when the maximum allowable positive reactivity of $3.00 was inserted into the core. The peak power achieved was 1354 Mw. (author)

Verification of excess defense material

International Nuclear Information System (INIS)

Fearey, B.L.; Pilat, J.F.; Eccleston, G.W.; Nicholas, N.J.; Tape, J.W.

1997-01-01

The international community in the post-Cold War period has expressed an interest in the International Atomic Energy Agency (IAEA) using its expertise in support of the arms control and disarmament process in unprecedented ways. The pledges of the US and Russian presidents to place excess defense materials under some type of international inspections raises the prospect of using IAEA safeguards approaches for monitoring excess materials, which include both classified and unclassified materials. Although the IAEA has suggested the need to address inspections of both types of materials, the most troublesome and potentially difficult problems involve approaches to the inspection of classified materials. The key issue for placing classified nuclear components and materials under IAEA safeguards is the conflict between these traditional IAEA materials accounting procedures and the US classification laws and nonproliferation policy designed to prevent the disclosure of critical weapon-design information. Possible verification approaches to classified excess defense materials could be based on item accountancy, attributes measurements, and containment and surveillance. Such approaches are not wholly new; in fact, they are quite well established for certain unclassified materials. Such concepts may be applicable to classified items, but the precise approaches have yet to be identified, fully tested, or evaluated for technical and political feasibility, or for their possible acceptability in an international inspection regime. Substantial work remains in these areas. This paper examines many of the challenges presented by international inspections of classified materials

Agreement on the Privileges and Immunities of the International Atomic Energy Agency

International Nuclear Information System (INIS)

1967-01-01

The Agreement on the Privileges and Immunities of the International Atomic Energy Agency, the text of which is reproduced herein, was approved by the Board of Governors on 1 July 1959. As required by section 38, the Director General has transmitted a certified copy of the Agreement to the Government of each Member of the Agency, and will transmit such a copy to the Government of every State that becomes a Member hereafter [fr

Agreement on the Privileges and Immunities of the International Atomic Energy Agency

International Nuclear Information System (INIS)

1967-01-01

The Agreement on the Privileges and Immunities of the International Atomic Energy Agency, the text of which is reproduced herein, was approved by the Board of Governors on 1 July 1959. As required by section 38, the Director General has transmitted a certified copy of the Agreement to the Government of each Member of the Agency, and will transmit such a copy to the Government of every State that becomes a Member hereafter [ru

Agreement on the Privileges and Immunities of the International Atomic Energy Agency

International Nuclear Information System (INIS)

1967-01-01

The Agreement on the Privileges and Immunities of the International Atomic Energy Agency, the text of which is reproduced herein, was approved by the Board of Governors on 1 July 1959. As required by section 38, the Director General has transmitted a certified copy of the Agreement to the Government of each Member of the Agency, and will transmit such a copy to the Government of every State that becomes a Member hereafter

Agreement on the Privileges and Immunities of the International Atomic Energy Agency

International Nuclear Information System (INIS)

1967-01-01

The Agreement on the Privileges and Immunities of the International Atomic Energy Agency, the text of which is reproduced herein, was approved by the Board of Governors on 1 July 1959. As required by section 38, the Director General has transmitted a certified copy of the Agreement to the Government of each Member of the Agency, and will transmit such a copy to the Government of every State that becomes a Member hereafter [es

Programs with societal benefits at the Cornell University TRIGA reactor

International Nuclear Information System (INIS)

Clark, D.D.; Aderhold, H.C.; Hossain, T.Z.

1993-01-01

In its 30 yr of operation, the Cornell TRIGA reactor has been used for many educational and research programs that provide general benefits to society. In addition to supporting graduate-level education of nuclear scientists and engineers, it has been extensively used in undergraduate and graduate courses and research by nonspecialists and, through the medium of tours, in education of the general public. Some educational functions have been described previously. In this paper, examples are presented of research of societal interest in nonnuclear fields. The first two rely mainly on radiography, and the remaining five on neutron activation analysis (NAA)

The N-Methyl-d-Aspartate Receptor Antagonist MK-801 Prevents Thallium-Induced Behavioral and Biochemical Alterations in the Rat Brain.

Science.gov (United States)

Osorio-Rico, Laura; Villeda-Hernández, Juana; Santamaría, Abel; Königsberg, Mina; Galván-Arzate, Sonia

2015-01-01

Thallium (Tl(+)) is a toxic heavy metal capable of increasing oxidative damage and disrupting antioxidant defense systems. Thallium invades the brain cells through potassium channels, increasing neuronal excitability, although until now the possible role of glutamatergic transmission in this event has not been investigated. Here, we explored the possible involvement of a glutamatergic component in the Tl(+)-induced toxicity through the N-methyl-d-aspartate (NMDA) receptor antagonist dizocilpine (MK-801) in rats. The effects of MK-801 (1 mg/kg, intraperitoneally [ip]) on early (24 hours) motor alterations, lipid peroxidation, reduced glutathione (GSH) levels, and GSH peroxidase activity induced by Tl(+) acetate (32 mg/kg, ip) were evaluated in adult rats. MK-801 attenuated the Tl(+)-induced hyperactivity and lipid peroxidation in the rat striatum, hippocampus and midbrain, and produced mild effects on other end points. Our findings suggest that glutamatergic transmission via NMDA receptors might be involved in the Tl(+)-induced altered regional brain redox activity and motor performance in rats. © The Author(s) 2015.

A 10 mK scanning tunneling microscope operating in ultra high vacuum and high magnetic fields.

Science.gov (United States)

Assig, Maximilian; Etzkorn, Markus; Enders, Axel; Stiepany, Wolfgang; Ast, Christian R; Kern, Klaus

2013-03-01

We present design and performance of a scanning tunneling microscope (STM) that operates at temperatures down to 10 mK providing ultimate energy resolution on the atomic scale. The STM is attached to a dilution refrigerator with direct access to an ultra high vacuum chamber allowing in situ sample preparation. High magnetic fields of up to 14 T perpendicular and up to 0.5 T parallel to the sample surface can be applied. Temperature sensors mounted directly at the tip and sample position verified the base temperature within a small error margin. Using a superconducting Al tip and a metallic Cu(111) sample, we determined an effective temperature of 38 ± 1 mK from the thermal broadening observed in the tunneling spectra. This results in an upper limit for the energy resolution of ΔE = 3.5 kBT = 11.4 ± 0.3 μeV. The stability between tip and sample is 4 pm at a temperature of 15 mK as demonstrated by topography measurements on a Cu(111) surface.

Determination of dissociation enthalpies of KPbF3, RbPbF3, CsPbF3 complex molecules

International Nuclear Information System (INIS)

Boltalin, A.I.; Rykov, A.N.; Korenev, Yu.M.

1990-01-01

Isomolecular reactions in MPbF 3(g) -BeF 2(g) systems where M=K, Rb, Cs are studied using Knudsen effusion technique with mass-spectral analysis of evaporation products. Enthalpy values of dissociation of MPbF 3 molecules per lead difluoride and alkali metal fluoride which are equal to 212.1±12.6 kJ/mol for CsPbF 3 are determined

McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: Four years of operations

International Nuclear Information System (INIS)

Heidel, C.C.; Richards, W.J.

1994-01-01

McClellan Air Force Base, at Sacramento, California, is headquarters for the Sacramento Air Force Logistics Center (SM-ALC). McClellan Air Force Base provides extensive inspection and maintenance capabilities for the F-111, F-1 5, and other military aircraft. Criticality of the MNRC TRIGA reactor was obtained on January 20, 1990 with 63 standard TRIGA fuel elements, three fuel-followed control rods and one air-followed control rod. Presently there are 93 fuel elements in the reactor core. The reactor can be operated at 1 MW steady state power, producing pulses up to three dollars worth of reactivity addition, and can be square waved up to 1 MW. The reactor core contains a circular grid plate and a graphite reflector assembly surrounding the core. Four tangential beam ports installed in the reflector assembly provide a thermal neutron flux to four radiography bays. The reactor tank is twenty-four (24) feet deep, seven and one-half (7.5) feet in diameter, and has a protrusion in the upper portion of the reactor tank. This protrusion is scheduled for use as a neutron thermal collimator in the future. Besides the neutron radiography capabilities, the reactor contains a pneumatic rabbit system, a central thimble, an in-core irradiation facility, and three additional cutouts that provide locations for additional irradiation facilities. The central thimble can be removed along with the B-ring locations of the upper portion of the grid plate to provide an additional and larger in-core irradiation facility. A new upper grid plate has been manufactured to expand one triangular cutout so that larger experiments can be inserted directly into the reactor core. Some operational problems experienced during the first four years of operations are the timeout of the CSC and DAC watchdogs, deterioration of the heat exchanger gaskets, and loss of thermocouples in the instrumented fuel elements. (author)

Defense Support of Civil Authorities. Handbook No. 1.04

National Research Council Canada - National Science Library

2005-01-01

This supplemental handbook presents an appreciation of U.S. military forces and their roles as part of Department of Defense support to Federal emergency response in a terrorist Weapons of Mass Destruction or Effect (WMD/E) incident...

Annual report 2001[International Atomic Energy Agency

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

Article VI.J of the Agency's Statute requires the Board of Governors to submit 'an annual report to the General Conference concerning the affairs of the Agency and any projects approved by the Agency'. This report covers the period 1 January to 31 December 2001. The report outlines the IAEA activities in the following fields: nuclear power, nuclear fuel cycle and waste management technology, comparative assessment for sustainable energy development; food and agriculture, human health, marine environment and water resources, applications of physical and chemical sciences, nuclear safety, radiation safety, radioactive waste safety, co-ordination of safety activities, safeguards, security of material, verification in Iraq pursuant to UNSC resolutions, management of technical co-operation for development, policy-making, management and support.

Neutron beam utilization at the TRIGA Mark II reactor Vienna

International Nuclear Information System (INIS)

Villa, M.; Boeck, H.; Ismail, S.; Koerner, S.; Baron, M.; Hainbuchner, M.; Badurek, G.; Buchelt, R.J.

1999-01-01

A review is given about the research activities around the 250 kw TRIGA reactor Vienna, which are adequate to other neutron sources of comparable or bigger size. The topics selected for presentation range from neutron radiography, materials irradiation, neutron small-angle scattering, neutron activation analysis, neutron polarization to neutron interferometry. It is the aim of this presentation to stimulate programs for more efficient use around TRIGA research reactors with neutron flux densities of 1013 cm-2a-1 at the center of the reactor core. We briefly describe the experimental facilities installed at the 250 kw TRIGA reactor of the Austrian Universities in Vienna and present a great part of the current research activities performed with them. We believe that most of the techniques and experiments presented here are adequate for implementation to other reactors of similar or even higher power. Those technologies which require extremely specialized know-how not generally available at every research Inst.e will not be treated here or are just mentioned without any further details.(author)

Operation and reactivity measurements of an accelerator driven subcritical TRIGA reactor

Science.gov (United States)

O'Kelly, David Sean

Experiments were performed at the Nuclear Engineering Teaching Laboratory (NETL) in 2005 and 2006 in which a 20 MeV linear electron accelerator operating as a photoneutron source was coupled to the TRIGA (Training, Research, Isotope production, General Atomics) Mark II research reactor at the University of Texas at Austin (UT) to simulate the operation and characteristics of a full-scale accelerator driven subcritical system (ADSS). The experimental program provided a relatively low-cost substitute for the higher power and complexity of internationally proposed systems utilizing proton accelerators and spallation neutron sources for an advanced ADSS that may be used for the burning of high-level radioactive waste. Various instrumentation methods that permitted ADSS neutron flux monitoring in high gamma radiation fields were successfully explored and the data was used to evaluate the Stochastic Pulsed Feynman method for reactivity monitoring.

International Atomic Energy Agency use of facility calorimeters for safeguards purposes

International Nuclear Information System (INIS)

McRae, L.P.; Delegard, C.H.; Hamilton, R.A.; Westsik, G.A.; Moriarty, T.F.; Lemaire, R.J.

1996-01-01

The International Atomic Energy Agency is performing nuclear materials safeguards on an inventory of pure and scrap plutonium oxide powder materials held in Vault 3 of the Plutonium Finishing Plant, operated by the Westinghouse Hanford Company for the US Department of Energy at the Hanford Site in Washington State. The International Atomic Energy Agency uses qualitative and quantitative techniques to verify the presence and quantity of the nuclear materials under safeguards. The Agency uses weighing, sampling, and destructive analyses to obtain the most accurate verification measurements of containers of plutonium powders. In contrast, the plant operator generally uses non-destructive plutonium assay based on gamma spectrometry and calorimetry for its most accurate plutonium powder container measurements. Recent results have shown that the operator''s calorimeter system achieves measurement variabilities comparable with, or better than, the destructive analyses, particularly for scrap. The results are achieved more quickly and economically, with less waste and lower radiation exposure and contamination hazard, by calorimetry than by classical destructive analyses. Techniques, including authentication methods, are being jointly developed to permit use of the operator''s calorimeter system for international safeguards purposes. The authentication is to ensure the independence of, and to substantiate the validity of, calorimeter measurements for international safeguards. The authentication methods considered and being developed are discussed

Measured and calculated effective delayed neutron fraction of the IPR-R1 Triga reactor

Energy Technology Data Exchange (ETDEWEB)

Souza, Rose Mary G.P.; Dalle, Hugo M.; Campolina, Daniel A.M., E-mail: souzarm@cdtn.b, E-mail: dallehm@cdtn.b, E-mail: campolina@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

The effective delayed neutron fraction, {beta}{sub eff}, one of the most important parameter in reactor kinetics, was measured for the 100 kW IPR-R1 TRIGA Mark I research reactor, located at the Nuclear Technology Development Center - CDTN, Belo Horizonte, Brazil. The current reactor core has 63 fuel elements, containing about 8.5% and 8% by weight of uranium enriched to 20% in U{sup 235}. The core has cylindrical configuration with an annular graphite reflector. Since the first criticality of the reactor in November 1960, the core configuration and the number of fuel elements have been changed several times. At that time, the reactor power was 30 kW, there were 56 fuel elements in the core, and the {beta}{sub eff} value for the reactor recommended by General Atomic (manufacturer of TRIGA) was 790 pcm. The current {beta}{sub eff} parameter was determined from experimental methods based on inhour equation and on the control rod drops. The estimated values obtained were (774 {+-} 38) pcm and (744 {+-} 20) pcm, respectively. The {beta}{sub eff} was calculated by Monte Carlo transport code MCNP5 and it was obtained 747 pcm. The calculated and measured values are in good agreement, and the relative percentage error is -3.6% for the first case, and 0.4% for the second one. (author)

Fast atom diffraction for grazing scattering of Ne atoms from a LiF(0 0 1) surface

International Nuclear Information System (INIS)

Gravielle, M.S.; Schueller, A.; Winter, H.; Miraglia, J.E.

2011-01-01

Angular distributions of fast Ne atoms after grazing collisions with a LiF(0 0 1) surface under axial surface channeling conditions are experimentally and theoretically studied. We use the surface eikonal approximation to describe the quantum interference of scattered projectiles, while the atom-surface interaction is represented by means of a pairwise additive potential, including the polarization of the projectile atom. Experimental data serve as a benchmark to investigate the performance of the proposed potential model, analyzing the role played by the projectile polarization.

Fast atom diffraction for grazing scattering of Ne atoms from a LiF(0 0 1) surface

Energy Technology Data Exchange (ETDEWEB)

Gravielle, M.S., E-mail: msilvia@iafe.uba.ar [Instituto de Astronomia y Fisica del Espacio (CONICET-UBA), Casilla de correo 67, sucursal 28 C1428EGA, Buenos Aires (Argentina); Departamento de Fisica, Fac. de Ciencias Exactas y Naturales, Universidad de Buenos Aires (Argentina); Schueller, A.; Winter, H. [Institut fuer Physik, Humboldt Universitaet zu Berlin, Newtonstrasse 15, D-12489 Berlin-Adlershof (Germany); Miraglia, J.E. [Instituto de Astronomia y Fisica del Espacio (CONICET-UBA), Casilla de correo 67, sucursal 28 C1428EGA, Buenos Aires (Argentina); Departamento de Fisica, Fac. de Ciencias Exactas y Naturales, Universidad de Buenos Aires (Argentina)

2011-06-01

Angular distributions of fast Ne atoms after grazing collisions with a LiF(0 0 1) surface under axial surface channeling conditions are experimentally and theoretically studied. We use the surface eikonal approximation to describe the quantum interference of scattered projectiles, while the atom-surface interaction is represented by means of a pairwise additive potential, including the polarization of the projectile atom. Experimental data serve as a benchmark to investigate the performance of the proposed potential model, analyzing the role played by the projectile polarization.

Results from Accelerator Driven TRIGA Reactor Experiments at The University of Texas at Austin

International Nuclear Information System (INIS)

O'Kelly, S.; Braisted, J.; Krause, M.; Welch, L.

2008-01-01

Accelerator Driven Transmutation of High-Level Waste (ATW) is one possible solution to the fuel reprocessing back-end problem for the disposal of high level waste such as minor actinides (Am, Np or Cm) and long-lived fission products. International programs continue to support research towards the eventual construction and operation of a proton accelerator driven spallation neutron source coupled to a subcritical 'neutron amplifier' for more efficient HLW transmutation. This project was performed under DOE AFCI Reactor-Accelerator Coupling Experiments (RACE). A 20 MeV Electron Linac was installed in the BP no 5 cave placing neutron source adjacent to an offset reactor core to maximize neutron coupling with available systems. Asymmetric neutron injection 'wasted' neutrons due to high leakage but sufficient neutrons were available to raise reactor power to ∼100 watts. The Linac provided approximately 100 mA but only 50% reached target. The Linac cooling system could not prevent overheating at frequencies over 200 Hz. The Linac electron beam had harmonics of primary frequency and periodic low frequency pulse intensity changes. Neutron detection using fission chambers in current mode eliminated saturation dead time and produced better sensitivity. The Operation of 'dual shielded' fission chambers reduced electron noise from linac. Benchmark criticality calculation using start-up data showed that the MCNPX model overestimates reactivity. TRIGA core was loaded to just slightly supercritical by adding graphite elements and measuring reactivity of $0.037. MCNPX modeled TRIGA core with and without graphite to arrive at 'true' measured subcritical multiplication of 0.998733± 0.00069. Thus, Alpha for the UT-RACE TRIGA core was approximately 155.99 s -1 . The Stochastic Feynman-Alpha Method (SFM) accuracy was evaluated during transients and reactivity changes. SFM was shown to be a potential real-time method of reactivity determination in future ADSS but requires stable

Research projects at the TRIGA-reactor Vienna

International Nuclear Information System (INIS)

Boeck, H.; Buchberger, T.; Buchtela, K.; Hammer, J.; Miksovsky, A.; Veider, A.; Weber, H.W.; Zugarek, G.

1986-01-01

In 1985 the thermalizing column was modified to a beam tube with a conical collimator for neutron radiography. A highly sophisticated sample and cassette changer will be constructed in the next months. The central channel of the thermal column is also used for neutron radiography especially for small objects. The four beam tubes of the TRIGA-reactor are intensively used for neutron spectroscopy, small angle scattering, neutron interferometry and investigations of magnetic structures with polarized neutrons. The neutron activation installation in the piecing beam tube is permanently used for various sample analysis using a ultrafast pneumatic transfer system. In addition to these experiments directly related to the TRIGA-reactor other research projects are carried out, some of them under an IAEA research contract which are mostly focused towards nuclear safeguards such as the magnetic scanning of power reactor fuel assemblies or the laser surveillance system of spent fuel pools. (author)

Enrichment measurement in TRIGA type fuels

International Nuclear Information System (INIS)

Aguilar H, F.; Mazon R, R.

2001-05-01

The Department of Energy of the United States of North America, through the program 'Idaho Operations Nuclear Spent Fuel Program' of the Idaho National Engineering and Environmental Laboratory (INEEL), in Idaho Falls; Idaho USA, hires to Global Technologies Inc. (GTI) to develop a prototype device of detection enrichment uranium (DEU Detection of Enrichment of Uranium) to determine quantitatively the enrichment in remainder U-235 in a TRIGA fuel element at the end of it useful life. The characteristics of the prototype developed by GTI are the following ones: It allows to carry out no-destructive measurements of TRIGA type fuel. Easily transportable due to that reduced of it size. The determination of the enrichment (in grams of U-235) it is obtained with a precision of 5%. The National Institute of Nuclear Research (ININ), in its facilities of the Nuclear Center of Mexico, it has TRIGA type fuel of high and low enrichment (standard and FLIP) fresh and with burnt, it also has the infrastructure (hot cells, armor-plating of transport, etc) and qualified personnel to carry out the necessary maneuvers to prove the operation of the DEU prototype. For this its would be used standard type fuel elements and FLIP, so much fresh as with certain burnt one. In the case of the fresh fuels the measurement doesn't represent any risk, the fuels before and after the measurement its don't contain a quantity of fission products that its represent a radiological risk in its manipulation; but in the case of the fuels with burnt the handling of the same ones represents an important radiological risk reason why for its manipulation it was used the transport armor-plating and the hot cells. (Author)

Report of cooperative research programs in the field of ion-beam breeding between Japan Atomic Energy Agency and Malaysian Nuclear Agency (Bilateral cooperative research)

International Nuclear Information System (INIS)

Ahmad, Zaiton; Oono, Yutaka

2016-03-01

This report summarizes Bilateral Cooperative Research between Japan Atomic Energy Agency and Malaysian Nuclear Agency (a representative of the Government of Malaysia) implemented from 2002 to 2012 under 'THE IMPLEMENTING ARRANGEMENT BETWEEN THE GOVERNMENT OF MALAYSIA AND THE JAPAN ATOMIC ENERGY AGENCY ON THE RESEARCH COOPERATION IN THE FIELD OF RADIATION PROCESSING'. The research activities in two Cooperative Research Programs, 'Mutation Induction of Orchid Plants by Ion Beams' and 'Generating New Ornamental Plant Varieties Using Ion Beams' performed 2002-2007 and 2007-2012, respectively, are contained. The lists of steering committee meetings, irradiation experiments, and publications/presentations of each program are also attached in the Appendixes. (author)

Development of an on-line high-temperature ion source for neutron-rich fission products at TRIGA-SPEC

Energy Technology Data Exchange (ETDEWEB)

Renisch, Dennis [Institut fuer Kernchemie, Johannes Gutenberg-Universitaet Mainz (Germany); Collaboration: TRIGA-SPEC-Collaboration

2012-07-01

The TRIGA-SPEC experiment at the TRIGA Mainz research reactor aims to determine ground-state properties of exotic nuclides. It includes the Penning-trap mass spectrometer TRIGA-TRAP and the collinear laser spectroscopy setup TRIGA-LASER. Nuclides of interest are produced in the neutron-induced fission of suitable actinide isotopes, thermalized in a gas-filled volume and transported to an on-line ion source with a gas-jet. The ion source being constructed has two operation modes: a high-temperature surface ionization mode and a hollow cathode plasma mode. It is expected that the surface mode will yield a high ionization efficiency for certain elements, in the order of at least several percent, whereas the plasma mode has the advantage, that more elements can be ionized but with lower efficiency compared to the surface ionization mode. The current status of the TRIGA-SPEC experiments and the present performance of the on-line ion source are presented.

Operation and Support Costs for the Department of Defense

National Research Council Canada - National Science Library

Pierrot, Lane; Kornfeld, Robert; Mechanic, Robert E; Miller, Michael; Bryton, Eugene; Berger, Michael; Dombey, Bonita; Kostak, William; Lussier, Frances; Moore, David

1988-01-01

Operation and support (O&S) funds -- the portion of the Department of Defense (DoD) budget that pays to operate DoD's forces -- have grown an average of about 2 percent per year from 1980 to 1988 in real...

Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

International Nuclear Information System (INIS)

Khan, Jahirul Haque

2013-01-01

The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark

Transport of radioactive material. 1994-2002. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2002-10-01

This document lists all sales publications, IAEA-TECDOC Series, Training Course Series and National Competent Authorities Lists of the International Atomic Energy Agency dealing with the transport of radioactive materials during the period 1994-2002. It gives a short abstract and contents of these issues along with their costs in EURO

Support for Arts Education. State Arts Agency Fact Sheet

Science.gov (United States)

National Assembly of State Arts Agencies, 2011

2011-01-01

Supporting lifelong learning in the arts is a top priority for state arts agencies. By supporting arts education in the schools, state arts agencies foster young imaginations, address core academic standards, and promote the critical thinking and creativity skills essential to a 21st century work force. State arts agencies also support…

Seed irradiation facilities at TRIGA Mark II reactor

International Nuclear Information System (INIS)

Najzer, M.

1972-01-01

Fast neutrons and gamma-rays with their high and low LET respectively are excellent complementary tools for investigation of the effect of different types of mutations. TRIGA Irradiation Facility and Thermal Column Irradiation Facility were designed and installed for the first time in the TRIGA tank and thermal column respectively. The basic idea of design was the use of depleted uranium as gamma-ray and thermal neutron shield and simultaneously as thermal to fast neutron converter. Low LET radiation, due to direct and thermal neutron capture gamma-rays, is strongly attenuated while fast neutron flux is increased. GIF is made of a cadmium tube inserted in a graphite block. It is located in the central thermal column channel. The basic idea is to convert thermal neutrons to gamma-rays by capture in the cadmium

Design of a self-aligned, wide temperature range (300 mK-300 K) atomic force microscope/magnetic force microscope with 10 nm magnetic force microscope resolution

Energy Technology Data Exchange (ETDEWEB)

Karcı, Özgür [NanoMagnetics Instruments Ltd., Hacettepe - İvedik OSB Teknokent, 1368. Cad., No: 61/33, 06370, Yenimahalle, Ankara (Turkey); Department of Nanotechnology and Nanomedicine, Hacettepe University, Beytepe, 06800 Ankara (Turkey); Dede, Münir [NanoMagnetics Instruments Ltd., Hacettepe - İvedik OSB Teknokent, 1368. Cad., No: 61/33, 06370, Yenimahalle, Ankara (Turkey); Oral, Ahmet, E-mail: orahmet@metu.edu.tr [Department of Physics, Middle East Technical University, 06800 Ankara (Turkey)

2014-10-01

We describe the design of a wide temperature range (300 mK-300 K) atomic force microscope/magnetic force microscope with a self-aligned fibre-cantilever mechanism. An alignment chip with alignment groves and a special mechanical design are used to eliminate tedious and time consuming fibre-cantilever alignment procedure for the entire temperature range. A low noise, Michelson fibre interferometer was integrated into the system for measuring deflection of the cantilever. The spectral noise density of the system was measured to be ~12 fm/√Hz at 4.2 K at 3 mW incident optical power. Abrikosov vortices in BSCCO(2212) single crystal sample and a high density hard disk sample were imaged at 10 nm resolution to demonstrate the performance of the system.

Design of a self-aligned, wide temperature range (300 mK-300 K) atomic force microscope/magnetic force microscope with 10 nm magnetic force microscope resolution

International Nuclear Information System (INIS)

Karcı, Özgür; Dede, Münir; Oral, Ahmet

2014-01-01

We describe the design of a wide temperature range (300 mK-300 K) atomic force microscope/magnetic force microscope with a self-aligned fibre-cantilever mechanism. An alignment chip with alignment groves and a special mechanical design are used to eliminate tedious and time consuming fibre-cantilever alignment procedure for the entire temperature range. A low noise, Michelson fibre interferometer was integrated into the system for measuring deflection of the cantilever. The spectral noise density of the system was measured to be ∼12 fm/√Hz at 4.2 K at 3 mW incident optical power. Abrikosov vortices in BSCCO(2212) single crystal sample and a high density hard disk sample were imaged at 10 nm resolution to demonstrate the performance of the system

Protocol Additional to the agreement between France, the European Atomic Energy Community and the International Atomic Energy Agency for the application of safeguards in France

International Nuclear Information System (INIS)

2005-01-01

The text of the Protocol Additional to the Agreement between France, the European Atomic Energy Community and the International Atomic Energy Agency for the Application of Safeguards in France is reproduced in the Annex to this document for the information of all Members. The Additional Protocol was approved by the Board of Governors on 11 June 1998. It was signed in Vienna on 22 September 1998. Pursuant to Article 16 of the Additional Protocol, the Protocol entered into force on 30 April 2004, the date on which the Agency received written notification that the European Atomic Energy Community and France had met their respective internal requirements for entry into force

FY 1972-1976 Defense Program and the 1972 Defense Budget.

Science.gov (United States)

1971-03-01

Thai Government. This assessment was given me by Thai officials during my recent visit there. Insurgents along the Thai/ Malaysian border are under the...Development and Initial Procurement of Maverick Air-to-Ground Missile 31 87 Air Superiority and Air Defense Continued Procurement of F-4 Air Force Fighter... MAVERICK . The MAVERICK is another program that is of importance in providing increased capabilities for support of troops on the battlefield. MAVERICK is

Nuclear Power, Nuclear Fuel Cycle and Waste Management 1980-1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-05-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power and Nuclear Fuel Cycle and Waste Management issued during the period 1980-1994. Most publications are issued in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all of these papers have abstracts in English. If publications are also available in other languages than English, this is noted as C for Chinese, F for French, R for Russian and S for Spanish by the relevant ISBN number. It should be noted that prices of books are quoted in Austrian Schillings. The prices do not include local taxes and are subject to change without notice. All books in this catalogue are 16 x 24 cm, paper-bound, unless otherwise stated

A combined wet/dry sipping cell for investigating failed triga fuel elements

International Nuclear Information System (INIS)

Boeck, H.; Gallhammer, H.; Hammer, J.; Israr, M.

1987-08-01

A sipping cell to detect failed triga fuel has been designed and constructed at the Atominstitut. The cell allows both wet- and dry sipping of one single standard triga fuel element. In the dry sipping method the fuel element may be electrically heated up to a maximum temperature of about 300 0 C to allow the detection of temperature dependent fission product release from the fuel element. 20 figs., 1 tab. (Author)

Radiological control guide for decommissioning of the TRIGA mark-2, 3

International Nuclear Information System (INIS)

Lee, Bong Jae

2000-08-01

The purpose of radiological control for TRIGA mark-2, 3 research reactors and facilities at the KAERI Seoul site, which are to be decommissioned, is in minimizing the radiation exposure for workers and in preventing the release of the radioactive materials to the environment. In order to accomplish these goal, the radiological control guide will be prepared during the decommissioning activities. Therefore, it is expected that this technical report can be used in preparing radiological control guide for safety decommissioning of the TRIGA mark-2, 3

Radionuclide mass inventory, activity, decay heat, and dose rate parametric data for TRIGA spent nuclear fuels

International Nuclear Information System (INIS)

Sterbentz, J.W.

1997-03-01

Parametric burnup calculations are performed to estimate radionuclide isotopic mass and activity concentrations for four different Training, Research, and Isotope General Atomics (TRIGA) nuclear reactor fuel element types: (1) Aluminum-clad standard, (2) Stainless Steel-clad standard, (3) High-enrichment Fuel Life Improvement Program (FLIP), and (4) Low-enrichment Fuel Life Improvement Program (FLIP-LEU-1). Parametric activity data are tabulated for 145 important radionuclides that can be used to generate gamma-ray emission source terms or provide mass quantity estimates as a function of decay time. Fuel element decay heats and dose rates are also presented parametrically as a function of burnup and decay time. Dose rates are given at the fuel element midplane for contact, 3.0-feet, and 3.0-meter detector locations in air. The data herein are estimates based on specially derived Beginning-of-Life (BOL) neutron cross sections using geometrically-explicit TRIGA reactor core models. The calculated parametric data should represent good estimates relative to actual values, although no experimental data were available for direct comparison and validation. However, because the cross sections were not updated as a function of burnup, the actinide concentrations may deviate from the actual values at the higher burnups

The construction of TRIGA-TRAP and direct high-precision Penning trap mass measurements on rare-earth elements and americium

Energy Technology Data Exchange (ETDEWEB)

Ketelaer, Jens

2010-06-14

The construction of TRIGA-TRAP and direct high-precision Penning trap mass measurements on rare-earth elements and americium: Nuclear masses are an important quantity to study nuclear structure since they reflect the sum of all nucleonic interactions. Many experimental possibilities exist to precisely measure masses, out of which the Penning trap is the tool to reach the highest precision. Moreover, absolute mass measurements can be performed using carbon, the atomic-mass standard, as a reference. The new double-Penning trap mass spectrometer TRIGA-TRAP has been installed and commissioned within this thesis work, which is the very first experimental setup of this kind located at a nuclear reactor. New technical developments have been carried out such as a reliable non-resonant laser ablation ion source for the production of carbon cluster ions and are still continued, like a non-destructive ion detection technique for single-ion measurements. Neutron-rich fission products will be available by the reactor that are important for nuclear astrophysics, especially the r-process. Prior to the on-line coupling to the reactor, TRIGA-TRAP already performed off-line mass measurements on stable and long-lived isotopes and will continue this program. The main focus within this thesis was on certain rare-earth nuclides in the well-established region of deformation around N {proportional_to} 90. Another field of interest are mass measurements on actinoids to test mass models and to provide direct links to the mass standard. Within this thesis, the mass of {sup 241}Am could be measured directly for the first time. (orig.)

The construction of TRIGA-TRAP and direct high-precision Penning trap mass measurements on rare-earth elements and americium

International Nuclear Information System (INIS)

Ketelaer, Jens

2010-01-01

The construction of TRIGA-TRAP and direct high-precision Penning trap mass measurements on rare-earth elements and americium: Nuclear masses are an important quantity to study nuclear structure since they reflect the sum of all nucleonic interactions. Many experimental possibilities exist to precisely measure masses, out of which the Penning trap is the tool to reach the highest precision. Moreover, absolute mass measurements can be performed using carbon, the atomic-mass standard, as a reference. The new double-Penning trap mass spectrometer TRIGA-TRAP has been installed and commissioned within this thesis work, which is the very first experimental setup of this kind located at a nuclear reactor. New technical developments have been carried out such as a reliable non-resonant laser ablation ion source for the production of carbon cluster ions and are still continued, like a non-destructive ion detection technique for single-ion measurements. Neutron-rich fission products will be available by the reactor that are important for nuclear astrophysics, especially the r-process. Prior to the on-line coupling to the reactor, TRIGA-TRAP already performed off-line mass measurements on stable and long-lived isotopes and will continue this program. The main focus within this thesis was on certain rare-earth nuclides in the well-established region of deformation around N ∝ 90. Another field of interest are mass measurements on actinoids to test mass models and to provide direct links to the mass standard. Within this thesis, the mass of 241 Am could be measured directly for the first time. (orig.)

Computational analysis of Bangladesh 3 MW TRIGA research reactor using MCNP4C, JENDL-3.3 and ENDF/B-Vl data libraries

International Nuclear Information System (INIS)

Huda, M.Q.

2006-01-01

The three-dimensional continuous energy Monte Carlo code MCNP4C was used to develop a versatile and accurate full-core model of the 3 MW TRIGA MARK II research reactor at Atomic Energy Research Establishment, Savar, Dhaka, Bangladesh. The model represents in detail all components of the core with literally no physical approximation. All fresh fuel and control elements as well as the vicinity of the core were precisely described. Validation of the JENDL-3.3 and ENDF/BVI continuous energy cross-section data for MCNP4C was performed against some well-known benchmark lattices. For TRIGA analysis, data from JENDL-3.3 and ENDF/B-VI in combination with the JENDL-3.2 and ENDF/B-V data files (for nat Zr, nat Mo, nat Cr, nat Fe, nat Ni, nat Si, and nat Mg) at 300 K evaluations were used. Full S(α, β) scattering functions from ENDF/B-V for Zr in ZrH, H in ZrH and water molecule, and for graphite were used in both cases. The validation of the model was performed against the criticality and reactivity benchmark experiments of the TRIGA reactor. There is ∼20.0% decrease of thermal neutron flux occurs when the thermal library is removed during the calculation. Effect of erbium isotope that is present in the TRIGA fuel was also studied. In addition to the effective multiplication values, the well-known integral parameters: δ 28 , δ 25 , ρ 25 , and C * were calculated and compared for both JENDL3.3 and ENDF/B-VI libraries and were found to be in very good agreement. Results are also reported for most of the analyses performed by JENDL-3.2 and ENDF/B-V data libraries

Irradiation positions for fission-track dating in the University of Pavia TRIGA Mark II nuclear reactor

International Nuclear Information System (INIS)

Oddone, Massimo; Meloni, Sandro; Balestrieri, Maria Laura; Bigazzi, Giulio

2002-01-01

An irradiation position arranged is described in the present paper for fission-track dating in the Triga Mark II reactor of the University of Pavia. Fluence values determined using the NIST glass standard SRM 962a for fission-track dating and the traditional metal foils are compared. Relatively good neutron thermalization (φ th /φ f = 0.956) and lack of significant fluence spatial gradients are good factors for fission-track dating. Finally, international age standards (or putative age standards) irradiated in this new position yielded results consistent with independent reference ages. (author)

Implementation of the k{sub 0} technique using multi-detectors on diverse irradiation facilities of TRIGA Reactor; Implementacion de la tecnica k{sub 0} usando multidetectores en diferentes instalaciones de irradiacion del Reactor TRIGA

Energy Technology Data Exchange (ETDEWEB)

Caldera C, M. de G.

2013-07-01

The k{sub 0} method with the technique of neutron activation analysis allows obtaining important characteristics parameters that describe a nuclear reactor. Among these parameters are the form factor of epithermal neutron flux, α and the ratio of thermal neutron flux with respect to the epithermal neutron flux, f. These parameters were obtained by irradiation of two different monitors, one of Au-Zr and the other of Au-Mo-Cr, where the last one was made and implemented for the first time. Both monitors were irradiated in different positions in the TRIGA Mark III Reactor at the National Institute of Nuclear Research. (Author)

Control console conceptual design for sheet type fuels of Triga Mark-II reactor

International Nuclear Information System (INIS)

Eko Priyono; Kurnia Wibowo; Anang Susanto

2016-01-01

The control console conceptual design for sheet type fuel of TRIGA Mark-II reactor has been made. The control console conceptual design was made with refer study result of instrument and control system which is used in BATAN'S reactor i.e TRIGA-2000 Bandung, TRIGA Yogyakarta and MPR-30 Serpong. The control console conceptual design was made by using AutoCad software. The control console conceptual design reactor for sheet type fuel of TRIGA Mark-II reactor consist of 5 segments that is 3 segments for placing the computer monitors, 1 segment for placing bargraph displays and recorders and 1 segment for placing panel meters. There are the door on front and back position at each segment for enter and out devices in the console. The control console conceptual design is also equipped by the table along in front of console for placing reactor panel control and for writing, 3 drawers for 3 keyboards. The dimension of console will refer control room size and the components will be placed on console which will be detailed in detail design if this conceptual design has been approved. (author)

Fire Support Requirements Methodology Study, Phase 2 Proceedings of the Fire Support Methodology Workshop

Science.gov (United States)

1975-12-18

It was not immediatei- clear that the -approach- would- succeed in overcoming the deficiencies of present fire support methodologies which demand- an...support require analysis up to Level 6. They also felt that deficiencies in f technique were most serious at Levels 3, 4 and 5. It was accepted that...defined as: Tk2 = _Tkl ilk2 kl (2) Tkt = Tk,t-l - ’lMktMk,t-l + 𔃼kt ,t-2 I t > (3. where Mt refers to the-number of type k targets killed in time

Virtual Leadership: The Influence of Transformational Leadership Style on Employee Satisfaction at the Defense Contract Management Agency

Science.gov (United States)

Johnson, Kevin A.

2012-01-01

The purpose of this quantitative correlational study was to examine the possible relationship between transformational leadership style behaviors and the influence it had on employee satisfaction. The information presented in this study involved virtual team members at the Defense Contract Management Agency, Navy Special Emphasis Operations. The…

Optimization study of ultracold neutron sources at TRIGA reactors using MCNP

International Nuclear Information System (INIS)

Pokotilovskij, Yu.N.; Rogov, A.D.

1997-01-01

Monte Carlo simulation for the optimization of ultracold and very cold neutron sources for TRIGA reactors is performed. The calculations of thermal and cold neutron fluxes from the TRIGA reactor for different positions and configurations of a very cold solid methane moderator were performed with using the MCNP program. The production of neutrons in the ultracold and very cold energy range was calculated for the most promising final moderators (converters): very cold solid deuterium and heavy methane. The radiation energy deposition was calculated for the optimized solid methane-heavy methane cold neutron moderator

Followup Audit of Controls Over Operating System and Security Software and Other General Controls for Computer Systems Supporting the Defense Finance and Accounting Service

National Research Council Canada - National Science Library

1996-01-01

This is the third in a series of followup audits made to evaluate the corrective actions taken by the Defense Finance and Accounting Service, the Defense Information Systems Agency, and the Defense...

Physical decommissioning of the Shippingport Atomic Power Station

International Nuclear Information System (INIS)

Crimi, F.P.

1988-01-01

The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

Agitation within Mk-42 insert caused by air sparge

International Nuclear Information System (INIS)

Ramsey, C.J.

1991-01-01

Dissolution of Rocky Flats Pu alloys and Pu metal using a ''nested insert'' configuration (One Well Insert (S-3352) inside the Mk-42 Insert) will require a Nuclear Safety Study, a major assumption of which will be that the annular dissolver is well-mixed. The ''well-mixed'' assumption was theoretically and experimentally supported for alloy dissolution using the Three Well Insert, but the present situation differs significantly. In the former case, the insert was directly exposed to the agitation induced by air sparging; in the case under consideration, the One Well Insert would be shielded by the Mk-42 Insert. In an effort to determine if the ''nested insert'' approach should be pursued, the past studies and technical literature have been surveyed and an attempt made to predict the extent of mixing and bulk circulation for a ''nested insert'' configuration in the presence of air sparging

Operating experience with the Cornell University TRIGA reactor

International Nuclear Information System (INIS)

Aderhold, H.C.

1970-01-01

As a result of our investigations, we believed the damage to be mechanical in origin and not to cladding failure. A new handling tool of modified design was put into service in July 1963, and since that time one element S/N 3075 has been dropped. This we believe was caused by operator error. At the request of prospective users, a high intensity, high energy gamma-ray irradiation facility has been added to the TRIGA equipment. This apparatus is simple to construct and use, either temporarily or permanently, with the TRIGA. Adjustment of relative neutron and gamma ray fluxes is possible by either shielding or changing rate of water flow. No attempt was made to improve performance by guiding water flow through the core, and higher yields should be obtainable by this means and by increasing the size of the holdup tank

Analytical quality control services of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Suschny, O.

1986-01-01

The International Atomic Energy Agency provides quality control services to analytical laboratories. These services which include the provision of reference materials and the organisation of intercomparisons are rendered for the purpose of assisting laboratories in determining the accuracy of their analytical work. The following classes of materials are presently available: nuclear materials, environmental materials, animal and plant materials, materials for biomedical studies and materials of marine origin. (orig.) [de

Effects of Cooling Fluid Flow Rate on the Critical Heat Flux and Flow Stability in the Plate Fuel Type 2 MW TRIGA Reactor

OpenAIRE

H. P. Rahardjo; V. I. Sri Wardhani

2017-01-01

The conversion program of the 2 MW TRIGA reactor in Bandung consisted of the replacement of cylindrical fuel (produced by General Atomic) with plate fuel (produced by BATAN). The replacement led into the change of core cooling process from upward natural convection type to downward forced convection type, and resulted in different thermohydraulic safety criteria, such as critical heat flux (CHF) limit, boiling limit, and cooling fluid flow stability. In this paper, a thermohydraulic safety an...

Sympathetic cooling in a rubidium cesium mixture: Production of ultracold cesium atoms

International Nuclear Information System (INIS)

Haas, M.

2007-01-01

finally contains the experimental results as well as the analysis of which. In experiments, which involve only rubidium, rubidium is coolde by means of microwave cooling; thereby an unwanted population of the state vertical stroke f=2,m f =1 right angle is observed, which hinders the condensation. The population of the state vertical stroke f=2,m f =1 right angle is systematically studied. The continuous depopulation of the state vertical stroke 2,1 right angle by means of a second microwave frequency radiated upon allows the production of rubidium condensates of 10 5 atoms after 23 s evaporative cooling. By selective microwave cooling of the rubidium atoms the rubidium cesium mixtures are cooled until 700 mK. By means of a simple model the sympathetic cooling of cesium is analyzed, which allows a first characterization of the rubidium-cesium interaction

"Homeland Defense: At Risk as a Result of Civil Support?"

National Research Council Canada - National Science Library

Brickhouse, Tonja

2003-01-01

This research effort is an attempt by the author to examine the broad area of military support to civil authorities and the potential for a significant demand on Department of Defense (DoD) resources...

JOYO MK-II core characteristics database

International Nuclear Information System (INIS)

Tabuchi, Shiro; Aoyama, Takafumi; Nagasaki, Hideaki; Kato, Yuichi

1998-12-01

The experimental fast reactor JOYO served as the MK-II irradiation bed core for testing fuel and material for FBR development for 15 years from 1982 to 1997. During the MK-II operation, extensive data were accumulated from the core characteristics tests conducted in thirty-one duty operations and thirteen special test operations. These core management data and core characteristics data were compiled into a database. The code system MAGI has been developed and used for core management of JOYO MK-II, and the core characteristics and the irradiation test conditions were calculated using MAGI on the basis of three dimensional diffusion theory with seven neutron energy groups. The core management data include extensive data, which were recorded on CD-ROM for user convenience. The data are specifications and configurations of the core, and for about 300 driver fuel subassemblies and about 60 uninstrumented irradiation subassemblies are core composition before and after irradiation, neutron flux, neutron fluences, fuel and control rod burn-up, and temperature and power distributions. MK-II core characteristics and test conditions were stored in the database for post analysis. Core characteristics data include excess reactivities, control rod worths, and reactivity coefficients, e.g., temperature, power and burn-up. Test conditions include both measured and calculated data for irradiation conditions. (author)

Over Twenty Years Of Experience In ITU TRIGA MARK-II Reactor

International Nuclear Information System (INIS)

Yavuz, Hasbi

2008-01-01

I.T.U. TRIGA MARK-II Training and Research Reactor, rated at 250 kW steady-state and 1200 MW pulsing power is the only research and training reactor owned and operated by a university in Turkey. Reactor has been operating since March 11, 1979; therefore the reactor has been operating successfully for more than twenty years. Over the twenty years of operation: - The tangential beam tube was equipped with a neutron radiography facility, which consists of a divergent collimator and exposure room; - A computerized data acquisition system was designed and installed such that all parameters of the reactor, which are observed from the console, could be monitored both in normal and pulse operations; - An electrical power calibration system was built for the thermal power calibration of the reactor; - Publications related with I.T.U. TRIGA MARK-II Training and Research Reactor are listed in Appendix; - Two majors undesired shutdown occurred; - The I.T.U. TRIGA MARK-II Training and Research Reactor is still in operation at the moment. (authors)

Experience in operation and maintenance of the TRIGA Mark II reactor at the University of Pavia in the time period July 1974 - June 1976

International Nuclear Information System (INIS)

Cambieri, A.; Cingoli, F.; Genova, N.; Meloni, S.; Perlini, G.

1976-01-01

The operation of the 250 kW steady state/250 MW pulsed TRIGA Mark II Reactor of the University of Pavia over the past two years is presented and discussed. Reactor maintenance activity is presented as well. Data for reactor utilization and a summary of the health physics procedures are also given. Since the third European Conference of TRIGA Reactor Users in 1974, reactor operation took place smoothly without major troubles. Because of the core excess decrease due to reactor operation and consequent burn-up, ten new stainless steel clad fuel elements were bought from General Atomic. Reactor operation license expired at the end of 1975 and it is now under way the bureaucratic work to get its renewal. The aging of the electronic equipment raises minor problems and the predicted switching to a new solid state equipment started by changing the old electromechanical rod position indicators with new digital ones. The installation of the Euracos II facility (Enriched Uranium Converter Source), described at the last TRIGA Users Conference, began at the end of 1975 and it is still under way. The first operation of the facility will take place at reduced power so that the removal of the graphite blocks from thermal column was not accomplished. The installation of the facility is described and the procedures of its operation in connection with reactor operation are presented as well. (author)

Development of Reactor TRIGA PUSPATI Simulator for Education and Training

International Nuclear Information System (INIS)

Mohd Sabri Minhat; Zarina Masood; Muhammad Rawi Mohamed Zin

2016-01-01

The real-time simulator for Reactor TRIGA PUSPATI (RTP) which is under development. The main purpose of this simulator is operator training and a dynamic test bed (DTB) to test and validate the control logics in reactor regulating system (RRS) of RTP. The simulator configuration is divided into hardware and software. The simulator hardware consists of a host computer, operator station, a network switch, control rod drive mechanism and a large display panel. The RTP hardwired panel is replicated similar to real console. The software includes a mathematical model includes reactor kinetics and thermal-hydraulics that implements plant dynamics in real-time using LabVIEW, an instructor station module work as host computer that manages user instructions, and a human machine interface module as a graphical user interface which is used in the real RTP plant. The developed TRIGA reactor simulators are installed in the Malaysian Nuclear Agency nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by actual RRS cabinet which is consist of Programmable Logic Controller (PLC) S7-1500, and was interfaced using a hard-wired and network-based interface. RRS cabinet generates control signals for reactor power control based on the various feedback signals from DTB such as neutron detector signal and control rod positions, and the DTB runs plant dynamics based on the RRS control signals. Thus the Hardware-In-the-Loop Simulation between RRS and the emulated plant (DTB) has been implemented and tested in this configuration. Normal and abnormal case test have been emulated for this project. In conclusion, the functions and the control performance of the developed RTP dynamic test bed simulator have been tested showing reasonable and acceptable results. (author)

RELAP5 model for TRIGA 14 MWt

International Nuclear Information System (INIS)

Negut, Gheorghe; Prisecaru, Ilie)

2003-01-01

The ICN TRIGA facility was commissioned at the beginning of 1980. Since that time the 14 MW Material Test Reactor was used extensively for various tests, experiments and basic research. There were provided a 100 kW loop and natural convection capsules to test CANDU type fuel and structural materials as Zircaloy as well as medical and industrial radioisotopes production facilities. The first load of High Enriched Uranium (HEU) fuel, mostly was exhausted and in the '90 there was necessary a replacement with Low Enriched Uranium (LEU) fuel. The original configuration of 29 HEU fuel bundles is now replaced with a HEU - LEU mixed core of 35 fuel bundles. This process involved the revision of Safety Analysis Report.The paper presents the analysis of Loss of Fluid Accident (LOFA) and the comparison with the results obtained during commissioning phase. A simple model of the TRIGA core was developed with the aid of RELAP5MOD3.2 code. The RELAP5 documented the flow reversal and natural convection establishment, and the model proved a useful and accurate instrument for thermal hydraulic analysis. Presented are the RELAP5 model for the TRIGA reactor and a LOFA accident analysis. The following results and conclusions concerning the LOFA tests with emergency pump off after 15 minutes and at start of the test are presented. In the first test TRIGA reactor is operated at the nominal power of 14 MW and the main pumps flow rate is 700 kg/sec. The main pumps are stopped and in 10 seconds the flow rate reaches 22 kg/sec, the emergency pump flow rate. The emergency pump is stopped after 15 minutes from the LOFA test initiation. The reactor is tripped by the low flow rate signal at the level of 473 kg/sec. The core flow is reversed after the 5 seconds and the core is cooled by natural convection. After 425 seconds from the LOFA initiation the residual power level is sufficiently low, so, the flow is reversed once again and the residual heat is removed by the emergency pump flow in

Neutron activation analysis using TRIGA

International Nuclear Information System (INIS)

Byrne, A.R.

1972-01-01

Activation analysis with TRIGA MARK II is the main part of the work of the nuclear Chemistry Section at the Institute. A major part of the effort in this field is concerned with the determination of trace elements at the micro and nanogram level in a wide variety of materials, and with the development of new methods, (or the adaptation of known methods,) applicable to these determinations. In particular, specific and group radiochemical separations are studied

75 FR 77849 - Closed Meeting of the Missile Defense Advisory Committee

Science.gov (United States)

2010-12-14

... DEPARTMENT OF DEFENSE Office of the Secretary Closed Meeting of the Missile Defense Advisory Committee AGENCY: Department of Defense; Missile Defense Agency (MDA). ACTION: Notice. SUMMARY: Under the... Defense announces that the following Federal advisory committee meeting of the Missile Defense Advisory...

75 FR 77848 - Closed Meeting of the Missile Defense Advisory Committee

Science.gov (United States)

2010-12-14

... DEPARTMENT OF DEFENSE Office of the Secretary Closed Meeting of the Missile Defense Advisory Committee AGENCY: Department of Defense; Missile Defense Agency (MDA). ACTION: Notice. SUMMARY: Under the... Defense announces that the following Federal advisory committee meeting of the Missile Defense Advisory...

75 FR 43156 - Federal Advisory Committee; Missile Defense Advisory Committee

Science.gov (United States)

2010-07-23

... DEPARTMENT OF DEFENSE Office of the Secretary Federal Advisory Committee; Missile Defense Advisory Committee AGENCY: Missile Defense Agency (MDA), DoD. ACTION: Notice of closed meeting. SUMMARY: Under the... Defense announces that the Missile Defense Advisory Committee will meet on August 4 and 5, 2010, in...

Piping Flexibility Analysis of the Primary Cooling System of TRIGA 2000 Bandung Reactor due to Earthquake

International Nuclear Information System (INIS)

Rahardjo, H.P.

2011-01-01

Earthquakes in a nuclear installation can overload a piping system which is not flexible enough. These loads can be forces, moments and stresses working on the pipes or equipment. If the load is too large and exceed the allowable limits, the piping and equipment can be damaged and lead to overall system operation failure. The load received by piping systems can be reduced by making adequate piping flexibility, so all the loads can be transmitted homogeneously throughout the pipe without load concentration at certain point. In this research the analysis of piping stress has been conducted to determine the size of loads that occurred in the piping of primary cooling system of TRIGA 2000 Reactor, Bandung if an earthquake happened in the reactor site. The analysis was performed using Caesar II software-based finite element method. The ASME code B31.1 arranging the design of piping systems for power generating system (Power Piping Code) was used as reference analysis method. Modeling of piping systems was based on the cooling piping that has already been installed and the existing data reported in Safety Analysis Reports (SARs) of TRIGA 2000 reactor, Bandung. The quake considered in this analysis is the earthquake that occurred due to the Lembang fault, since it has the Peak Ground Acceleration (PGA) in the Bandung TRIGA 2000 reactor site. The analysis results showed that in the static condition for sustain and expansion loads, the stress fraction in all piping lines does not exceed the allowable limit. However, during operation moment, in dynamic condition, the primary cooling system is less flexible at sustain load, expansion load, and combination load and the stress fraction have reached 95,5%. Therefore a pipeline modification (re-routing) is needed to make pipe stress does not exceed the allowable stress. The pipeline modification was carried out by applied a gap of 3 mm in the X direction of the support at node 25 and eliminate the support at the node 30, also a

Modernization design of neutron radiography of ITU TRIGA Mark-II reactor

International Nuclear Information System (INIS)

Tugrul, B.; Bilge, A.N.

1988-01-01

ITU TRIGA MARK-II Research and Training Reactor has a power of 250 KW and has three beam tubes. One of them is tangential beam tube used for neutron radiography. In this study, the neutron radiography set in the tangential beam tube is described with its problems for ITU TRIGA Reactor. After that modernization of the system is designed and the applicability of the direct and indirect methods is evaluated. Improving the ratio of length to diameter for the beam tube, elimination the fogging on the film and constructive design for practice and secure application of the technique is developed. (author)

Department of Defense Agency Financial Report for FY 2011

Science.gov (United States)

2011-11-01

able to distribute resources across hospitals and clinics within a market to meet the needs of the entire population of eligible beneficiaries. In...WRAMC), Washington, DC. This entailed construction of a new community hospital and a dental clinic at Fort Belvoir and an expansion of the National...Department of Defense DSB Defense Science Board DSS Defense Security Service DTM Directive-type Memorandum DTS Defense Travel System EBF Education

Pulsed TRIGA reactor as substitute for long pulse spallation neutron source

International Nuclear Information System (INIS)

Whittemore, W.L.

1999-01-01

TRIGA reactor cores have been used to demonstrate various pulsing applications. The TRIGA reactor fuel (U-ZrH x ) is very robust especially in pulsing applications. The features required to produce 50 pulses per second have been successfully demonstrated individually, including pulse tests with small diameter fuel rods. A partially optimized core has been evaluated for pulses at 50 Hz with peak pulsed power up to 100 MW and an average power up to 10 MW. Depending on the design, the full width at half power of the individual pulses can range between 2000 μsec to 3000 μsec. Until recently, the relatively long pulses (2000 μsec to 3000 μsec) from a pulsed thermal reactor or a long pulse spallation source (LPSS) have been considered unsuitable for time-of-flight measurements of neutron scattering. More recently considerable attention has been devoted to evaluating the performance of long pulse (1000 to 4000 μs) spallation sources for the same type of neutron measurements originally performed only with short pulses from spallation sources (SPSS). Adequate information is available to permit meaningful comparisons between CW, SPSS, and LPSS neutron sources. Except where extremely high resolution is required (fraction of a percent), which does require short pulses, it is demonstrated that the LPSS source with a 1000 msec or longer pulse length and a repetition rate of 50 to 60 Hz gives results comparable to those from the 60 MW ILL (CW) source. For many of these applications the shorter pulse is not necessarily a disadvantage, but it is not an advantage over the long pulse system. In one study, the conclusion is that a 5 MW 2000 μsec LPSS source improves the capability for structural biology studies of macromolecules by at least a factor of 5 over that achievable with a high flux reactor. Recent studies have identified the advantages and usefulness of long pulse neutron sources. It is evident that the multiple pulse TRIGA reactor can produce pulses comparable to

Scattering of 20Ne atoms from the (001) face of LiF

International Nuclear Information System (INIS)

Semerad, E.; Hoerl, E.M.

1983-01-01

An apparatus for measurements of inelastic scattering processes of gas atoms from crystal surfaces is described. Scattering experiments with Neon atoms of thermal energy on the (001) LiF surface in the azimuth are discussed. Inelastic scattering shows large contributions of single phonon interactions as well as of modes originating from the bulk bands. (Author)

Defense Agencies Cash Management in the Defense Business Operations Fund

National Research Council Canada - National Science Library

Lane, F

1997-01-01

The primary audit objective was to determine whether the Fund Balance With Treasury Account on the Consolidated Financial Statements of the Defense Business Operations Fund for FY 1996 was presented...

Radioactivity of spent TRIGA fuel

International Nuclear Information System (INIS)

Usang, M. D.; Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P.

2015-01-01

Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive

Radioactivity of spent TRIGA fuel

Energy Technology Data Exchange (ETDEWEB)

Usang, M. D., E-mail: mark-dennis@nuclearmalaysia.gov.my; Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P. [Reactor Department, Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)

2015-04-29

Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive.

Nanosheet Supported Single-Metal Atom Bifunctional Catalyst for Overall Water Splitting.

Science.gov (United States)

Ling, Chongyi; Shi, Li; Ouyang, Yixin; Zeng, Xiao Cheng; Wang, Jinlan

2017-08-09

Nanosheet supported single-atom catalysts (SACs) can make full use of metal atoms and yet entail high selectivity and activity, and bifunctional catalysts can enable higher performance while lowering the cost than two separate unifunctional catalysts. Supported single-atom bifunctional catalysts are therefore of great economic interest and scientific importance. Here, on the basis of first-principles computations, we report a design of the first single-atom bifunctional eletrocatalyst, namely, isolated nickel atom supported on β 12 boron monolayer (Ni 1 /β 12 -BM), to achieve overall water splitting. This nanosheet supported SAC exhibits remarkable electrocatalytic performance with the computed overpotential for oxygen/hydrogen evolution reaction being just 0.40/0.06 V. The ab initio molecular dynamics simulation shows that the SAC can survive up to 800 K elevated temperature, while enacting a high energy barrier of 1.68 eV to prevent isolated Ni atoms from clustering. A viable experimental route for the synthesis of Ni 1 /β 12 -BM SAC is demonstrated from computer simulation. The desired nanosheet supported single-atom bifunctional catalysts not only show great potential for achieving overall water splitting but also offer cost-effective opportunities for advancing clean energy technology.

Characterization of gamma field in the JSI TRIGA reactor

Science.gov (United States)

Ambrožič, Klemen; Radulović, Vladimir; Snoj, Luka; Gruel, Adrien; Guillou, Mael Le; Blaise, Patrick; Destouches, Christophe; Barbot, Loïc

2018-01-01

Research reactors such as the "Jožzef Stefan" Institute TRIGA reactor have primarily been designed for experimentation and sample irradiation with neutrons. However recent developments in incorporating additional instrumentation for nuclear power plant support and with novel high flux material testing reactor designs, γ field characterization has become of great interest for the characterization of the changes in operational parameters of electronic devices and for the evaluation of γ heating of MTR's structural materials in a representative reactor Γ spectrum. In this paper, we present ongoing work on γ field characterization both experimentally, by performing γ field measurements, and by simulations, using Monte Carlo particle transport codes in conjunction with R2S methodology for delayed γ field characterization.

Implementation of the k0 technique using multi-detectors on diverse irradiation facilities of TRIGA Reactor

International Nuclear Information System (INIS)

Caldera C, M. de G.

2013-01-01

The k 0 method with the technique of neutron activation analysis allows obtaining important characteristics parameters that describe a nuclear reactor. Among these parameters are the form factor of epithermal neutron flux, α and the ratio of thermal neutron flux with respect to the epithermal neutron flux, f. These parameters were obtained by irradiation of two different monitors, one of Au-Zr and the other of Au-Mo-Cr, where the last one was made and implemented for the first time. Both monitors were irradiated in different positions in the TRIGA Mark III Reactor at the National Institute of Nuclear Research. (Author)

High Temperature Fuel Cladding Chemical Interactions Between TRIGA Fuels and 304 Stainless Steel

Energy Technology Data Exchange (ETDEWEB)

Perez, Emmanuel [Idaho National Lab. (INL), Idaho Falls, ID (United States); Keiser, Jr., Dennis D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Forsmann, Bryan [Boise State Univ., ID (United States); Janney, Dawn E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Henley, Jody [Idaho National Lab. (INL), Idaho Falls, ID (United States); Woolstenhulme, Eric C. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-02-01

High-temperature fuel-cladding chemical interactions (FCCI) between TRIGA (Training, Research, Isotopes, General Atomics) fuel elements and the 304 stainless steel (304SS) are of interest to develop an understanding of the fuel behavior during transient reactor scenarios. TRIGA fuels are composed of uranium (U) particles dispersed in a zirconium-hydride (Zr-H) matrix. In reactor, the fuel is encased in 304-stainless-steel (304SS) or Incoloy 800 clad tubes. At high temperatures, the fuel can readily interact with the cladding, resulting in FCCI. A number of FCCI can take place in this system. Interactions can be expected between the cladding and the Zr-H matrix, and/or between the cladding and the U-particles. Other interactions may be expected between the Zr-H matrix and the U-particles. Furthermore, the fuel contains erbium-oxide (Er-O) additions. Interactions can also be expected between the Er-O, the cladding, the Zr-H and the U-particles. The overall result is that very complex interactions may take place as a result of fuel and cladding exposures to high temperatures. This report discusses the characterization of the baseline fuel microstructure in the as-received state (prior to exposure to high temperature), characterization of the fuel after annealing at 950C for 24 hours and the results from diffusion couple experiments carries out at 1000C for 5 and 24 hours. Characterization was carried out via scanning electron microscopy (SEM) and transmission electron microscopy (TEM) with sample preparation via focused ion beam in situ-liftout-technique.

High Temperature Fuel Cladding Chemical Interactions Between TRIGA Fuels and 304 Stainless Steel

International Nuclear Information System (INIS)

Perez, Emmanuel; Keiser Jr, Dennis D.; Forsmann, Bryan; Janney, Dawn E.; Henley, Jody; Woolstenhulme, Eric C.

2016-01-01

High-temperature fuel-cladding chemical interactions (FCCI) between TRIGA (Training, Research, Isotopes, General Atomics) fuel elements and the 304 stainless steel (304SS) are of interest to develop an understanding of the fuel behavior during transient reactor scenarios. TRIGA fuels are composed of uranium (U) particles dispersed in a zirconium-hydride (Zr-H) matrix. In reactor, the fuel is encased in 304-stainless-steel (304SS) or Incoloy 800 clad tubes. At high temperatures, the fuel can readily interact with the cladding, resulting in FCCI. A number of FCCI can take place in this system. Interactions can be expected between the cladding and the Zr-H matrix, and/or between the cladding and the U-particles. Other interactions may be expected between the Zr-H matrix and the U-particles. Furthermore, the fuel contains erbium-oxide (Er-O) additions. Interactions can also be expected between the Er-O, the cladding, the Zr-H and the U-particles. The overall result is that very complex interactions may take place as a result of fuel and cladding exposures to high temperatures. This report discusses the characterization of the baseline fuel microstructure in the as-received state (prior to exposure to high temperature), characterization of the fuel after annealing at 950C for 24 hours and the results from diffusion couple experiments carries out at 1000C for 5 and 24 hours. Characterization was carried out via scanning electron microscopy (SEM) and transmission electron microscopy (TEM) with sample preparation via focused ion beam in situ-liftout-technique.

Design and safety considerations for the 10 MW(t) multipurpose TRIGA reactor in Thailand

International Nuclear Information System (INIS)

Razvi, J.; Bolin, J.M.; Saurwein, J.J.; Whittemore, W.L.; Proongmuang, S.

1999-01-01

General Atomics (GA) is constructing the Ongkharak Nuclear Research Center (ONRC) near Bangkok, Thailand for the Office of Atomic Energy for Peace. The ONRC complex includes the following: A multipurpose 10 MW(t) research reactor; An Isotope Production Facility; Centralized Radioactive Waste Processing and Storage Facilities. The Center is being built 60-km northeast of Bangkok, with a 10 MW(t) TRIGA type research reactor as the centerpiece. Facilities are included for neutron transmutation doping of silicon, neutron capture therapy neutron beam research and for production of a variety of radioisotopes. The facility will also be utilized for applied research and technology development as well as training in reactor operations, conduct of experiments and in reactor physics. The multipurpose, pool-type reactor will be fueled with high-density (45 wt%), low-enriched (19.7 wt%) uranium-erbium-zirconium-hydride (UErZrH) fuel rods, cooled and moderated by light water, and reflected by beryllium and heavy water. The general arrangement of the reactor and auxiliary pool structure allows irradiated targets to be transferred entirely under water from their irradiation locations to the hot cell, then pneumatically transferred to the adjacent Isotope Production Facility for processing. The core configuration includes 4 x 4 array standard TRIGA fuel clusters, modified clusters to serve as fast-neutron irradiation facilities, control rods and an in-core Ir-192 production facility. The active core is reflected on two sides by beryllium and on the other two sides by D 2 O. Additional irradiation facilities are also located in the beryllium reflector blocks and the D 2 O reflector blanket. The fuel provides the fundamental safety feature of the ONRC reactor, and as a result of all the well established accident-mitigating characteristics of the UErZrH fuel itself (large prompt negative temperature coefficient of reactivity, fission product retention and chemical stability), a

Component failure data base of TRIGA reactors

International Nuclear Information System (INIS)

Djuricic, M.

2004-10-01

This compilation provides failure data such as first criticality, component type description (reactor component, population, cumulative calendar time, cumulative operating time, demands, failure mode, failures, failure rate, failure probability) and specific information on each type of component of TRIGA Mark-II reactors in Austria, Bangladesh, Germany, Finland, Indonesia, Italy, Indonesia, Slovenia and Romania. (nevyjel)

The International Atomic Energy Agency Nuclear Security Education Strategies

International Nuclear Information System (INIS)

BRAUNEGGER-GUELICH, A.; RUKHLO, V.; GREGORIC, M.; COLGAN, P.

2011-01-01

The threat of nuclear terrorism has not diminished. In response to the concerns of States, an international nuclear security framework has emerged through the establishment of a number of legally binding and non-binding international instruments which obligates or commits States to carry out a number of actions to protect against nuclear terrorism. In this context, the need for human resource development programmes in nuclear security was underscored at several International Atomic Energy Agency (IAEA) General Conferences and Board of Governors' Meetings. In the pursuit of this need, the IAEA provides a comprehensive nuclear security training programme to States on a regular basis, and has developed a concept that seeks to effectively pass ownership of nuclear security knowledge and skills to States through the establishment of a Nuclear Security Support Centre. In addition, the IAEA has developed a technical guidance titled IAEA Nuclear Security Series No. 12 - Educational Programme in Nuclear Security that consists of a model of a Master of Science (M.Sc.) and assists educational institutions to provide nuclear security education. The article sets out IAEA efforts in the area of nuclear security training and education, including the assistance to States for establishing a Nuclear Security Support Centre. It underlines the objective and content of the IAEA Nuclear Security Series No. 12, discusses different concepts on how to establish nuclear security at universities and, emphasizes on the IAEA efforts to assist educational and research institutions, and other stake holders to enhance global nuclear security by developing, sharing and promoting excellence in nuclear security education. (author)

77 FR 34357 - Missile Defense Advisory Committee; Notice of Closed Meeting

Science.gov (United States)

2012-06-11

... DEPARTMENT OF DEFENSE Office of the Secretary Missile Defense Advisory Committee; Notice of Closed Meeting AGENCY: Missile Defense Agency (MDA), Department of Defense. ACTION: Notice of closed meeting... Missile Defense Advisory Committee will take place. DATES: Tuesday, June 12, 2012 through Wednesday, June...

76 FR 71556 - Missile Defense Advisory Committee; Notice of Closed Meeting

Science.gov (United States)

2011-11-18

... DEPARTMENT OF DEFENSE Office of the Secretary Missile Defense Advisory Committee; Notice of Closed Meeting AGENCY: Missile Defense Agency (MDA), Department of Defense. ACTION: Notice of closed meeting... Missile Defense Advisory Committee will take place. DATES: Tuesday, December 13, 2011 through Wednesday...

76 FR 45783 - Missile Defense Advisory Committee; Notice of Closed Meeting

Science.gov (United States)

2011-08-01

... DEPARTMENT OF DEFENSE Office of the Secretary Missile Defense Advisory Committee; Notice of Closed Meeting AGENCY: Department of Defense; Missile Defense Agency (MDA). ACTION: Notice of closed meeting... Missile Defense Advisory Committee will take place. DATES: Tuesday, August 16, 2011 through Thursday...

Training courses for the staff of the nuclear power station KRSKO conducted at the TRIGA reactor center in Ljubljana

International Nuclear Information System (INIS)

Pregl, G.; Najzer, M.

1976-01-01

The training program for the Nuclear Power Station Krsko was divided into two modules: fundamentals of nuclear engineering and specialized training according to duties that candidates are supposed to take at the power station. Basic training was organized at the TRIGA Reactor Center in Ljubljana in two different versions. The first version intended for plant operators and all engineers lasted for six months and included about 500 hours of classroom lessons and seminars and 31 laboratory experiments. The educational program was conventional. The following topics were covered: nuclear and atomic physics, reactor theory, reactor dynamics, reactor instrumentation and control, heat transfer in nuclear power plants, nuclear power plant systems, reactor materials, reactor safety, and radiation protection. Until now, two groups, consisting of 37 candidates altogether, have attended this basic course. Plans have been made to conduct two additional courses of about 20 students each for technicians other than operators. The program of this second version will be reduced, with the emphasis on reactor core physics and radiation protection. Classroom lessons will be strongly supported by laboratory experiments. (author)

Current radiation protection activities of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Webb, G.A.M.

1996-01-01

The International Atomic Energy Agency (IAEA) program of the Radiation Safety Section is described in this paper. The Section has two main components: (1) the development of consensus safety documentation and (2) the use of that documentation as the basis for assisting countries to deal safely with their applications of radiation and radioactivity. Main activities of the section are listed for each of these components. Activities include documentation, coordinated research programs, and assistance to developing countries. 14 tabs

Nuclear and radiological safety 1980-1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-06-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety issued during the period 1980-1994. The following aspects are covered: Uranium mining and milling, Fuel fabrication and storage, Nuclear power plants, Research reactors, Radiation sources and accelerators, Transport of radioactive materials, Waste repositories, Radiation protection, Accident response, Radioactive waste management, Safety analysis, Quality management, Legal and governmental aspects

Knockout of NMDA-receptors from parvalbumin interneurons sensitizes to schizophrenia-related deficits induced by MK-801

Science.gov (United States)

Bygrave, A M; Masiulis, S; Nicholson, E; Berkemann, M; Barkus, C; Sprengel, R; Harrison, P J; Kullmann, D M; Bannerman, D M; Kätzel, D

2016-01-01

It has been suggested that a functional deficit in NMDA-receptors (NMDARs) on parvalbumin (PV)-positive interneurons (PV-NMDARs) is central to the pathophysiology of schizophrenia. Supportive evidence come from examination of genetically modified mice where the obligatory NMDAR-subunit GluN1 (also known as NR1) has been deleted from PV interneurons by Cre-mediated knockout of the corresponding gene Grin1 (Grin1ΔPV mice). Notably, such PV-specific GluN1 ablation has been reported to blunt the induction of hyperlocomotion (a surrogate for psychosis) by pharmacological NMDAR blockade with the non-competitive antagonist MK-801. This suggests PV-NMDARs as the site of the psychosis-inducing action of MK-801. In contrast to this hypothesis, we show here that Grin1ΔPV mice are not protected against the effects of MK-801, but are in fact sensitized to many of them. Compared with control animals, Grin1ΔPVmice injected with MK-801 show increased stereotypy and pronounced catalepsy, which confound the locomotor readout. Furthermore, in Grin1ΔPVmice, MK-801 induced medial-prefrontal delta (4 Hz) oscillations, and impaired performance on tests of motor coordination, working memory and sucrose preference, even at lower doses than in wild-type controls. We also found that untreated Grin1ΔPVmice are largely normal across a wide range of cognitive functions, including attention, cognitive flexibility and various forms of short-term memory. Taken together these results argue against PV-specific NMDAR hypofunction as a key starting point of schizophrenia pathophysiology, but support a model where NMDAR hypofunction in multiple cell types contribute to the disease. PMID:27070406

Berkeley Nuclear Laboratories Reactor Physics Mk. III Experimental Programme. Description of facility and programme for 1971

Energy Technology Data Exchange (ETDEWEB)

Nunn, R M; Waterson, R H; Young, J D

1971-01-15

Reactor physics experiments have been carried out at Berkeley Nuclear Laboratories during the past few years in support of the Civil Advanced Gas-Cooled Reactors (Mk. II) the Generating Board is building. These experiments are part of an overall programme whose objective is to assess the accuracy of the calculational methods used in the design and operation of these reactors. This report provides a description of the facility for the Mk. III experimental programme and the planned programme for 1971.

Effect of MK-801 on the development of nicotine sensitization of nucleus accumbens dopamine release

Energy Technology Data Exchange (ETDEWEB)

Hong, Soo Kyung; Choung, In Soon; Kim, Sang Eun [Seoul National University College of Medicine, Seoul (Korea, Republic of)

2005-07-01

We have previously found that MK-801, a noncompetitive NMDA receptor antagonist, prevents behavioral sensitization to nicotine. This study aimed to investigate the effect of MK-801 on a neurochemical component of nicotine sensitization by evaluating the effect of the drug on nicotine sensitization of nucleus accumbens dopamine (DA) release. Sprague-Dawley rats were pretreated with MK-801 (0.3 mg/kg, i.p.) or saline 30 min before injection of nicotine (0.4 mg/kg, s.c., once daily) for 7 consecutive days. Twenty-four hours after the last drug injection, animals were challenged with local perfusion of 5 mM nicotine into the shell of nucleus accumbens and DA release was monitored using in vivo microdialysis. In rats pretreated with chronic nicotine, local nicotine challenge induced a greater increase of accumbal DA release than in saline-treated animals (maximal DA response 969 {+-} 235% (mean {+-} SEM) of basal level vs. 520 {+-} 93%, P < 0.05). Co-administration of MK-801 with nicotine attenuated an increase of DA release elicited by local nicotine challenge, compared with nicotine alone (maximal DA response 427 {+-} 83% of basal level vs. 969 {+-} 235%, P < 0.01). These results suggest that MK-801 blocks the development of nicotine sensitization of nucleus accumbens DA release, further supporting the involvement of NMDA receptors in the development of behavioral sensitization to nicotine.

Effect of MK-801 on the development of nicotine sensitization of nucleus accumbens dopamine release

International Nuclear Information System (INIS)

Hong, Soo Kyung; Choung, In Soon; Kim, Sang Eun

2005-01-01

We have previously found that MK-801, a noncompetitive NMDA receptor antagonist, prevents behavioral sensitization to nicotine. This study aimed to investigate the effect of MK-801 on a neurochemical component of nicotine sensitization by evaluating the effect of the drug on nicotine sensitization of nucleus accumbens dopamine (DA) release. Sprague-Dawley rats were pretreated with MK-801 (0.3 mg/kg, i.p.) or saline 30 min before injection of nicotine (0.4 mg/kg, s.c., once daily) for 7 consecutive days. Twenty-four hours after the last drug injection, animals were challenged with local perfusion of 5 mM nicotine into the shell of nucleus accumbens and DA release was monitored using in vivo microdialysis. In rats pretreated with chronic nicotine, local nicotine challenge induced a greater increase of accumbal DA release than in saline-treated animals (maximal DA response 969 ± 235% (mean ± SEM) of basal level vs. 520 ± 93%, P < 0.05). Co-administration of MK-801 with nicotine attenuated an increase of DA release elicited by local nicotine challenge, compared with nicotine alone (maximal DA response 427 ± 83% of basal level vs. 969 ± 235%, P < 0.01). These results suggest that MK-801 blocks the development of nicotine sensitization of nucleus accumbens DA release, further supporting the involvement of NMDA receptors in the development of behavioral sensitization to nicotine

Charges Assessed the Army by the Defense Logistics Agency for Deployable Medical Systems

National Research Council Canada - National Science Library

1995-01-01

.... Deployable medical systems are standardized modular field hospitals that can be prepositioned in the event of a contingency, national emergency, or war operations. In FY 1994, the Defense Personnel Support Center billed the Army $25 million for acquiring and assembling deployable medical systems.

International technology exchange in support of the Defense Waste Processing Facility wasteform production

International Nuclear Information System (INIS)

Kitchen, B.G.

1989-01-01

The nearly completed Defense Waste Processing Facility (DWPF) is a Department of Energy (DOE) facility at the Savannah River Site that is designed to immobilize defense high level radioactive waste (HLW) by vitrification in borosilicate glass and containment in stainless steel canisters suitable for storage in the future DOE HLW repository. The DWPF is expected to start cold operation later this year (1990), and will be the first full scale vitrification facility operating in the United States, and the largest in the world. The DOE has been coordinating technology transfer and exchange on issues relating to HLW treatment and disposal through bi-lateral agreements with several nations. For the nearly fifteen years of the vitrification program at Savannah River Laboratory, over two hundred exchanges have been conducted with a dozen international agencies involving about five-hundred foreign national specialists. These international exchanges have been beneficial to the DOE's waste management efforts through confirmation of the choice of the waste form, enhanced understanding of melter operating phenomena, support for paths forward in political/regulatory arenas, confirmation of costs for waste form compliance programs, and establishing the need for enhancements of melter facility designs. This paper will compare designs and schedules of the international vitrification programs, and will discuss technical areas where the exchanges have provided data that have confirmed and aided US research and development efforts, impacted the design of the DWPF and guided the planning for regulatory interaction and product acceptance

Other Defense Organizations and Defense Finance and Accounting Service Controls Over High-Risk Transactions Were Not Effective

Science.gov (United States)

2016-03-28

Defense Organizations and Defense Finance and Accounting Service Controls Over High-Risk Transactions Were Not Effective M A R C H 2 8 , 2 0 1 6...Defense Organizations and Defense Finance and Accounting Service Controls Over High-Risk Transactions Were Not Effective Visit us at www.dodig.mil... FINANCE AND ACCOUNTING SERVICE DIRECTOR, DEFENSE HEALTH AGENCY SUBJECT: Other Defense Organizations and Defense Finance and Accounting Service

International Atomic Energy Agency thirty-third general conference

International Nuclear Information System (INIS)

Anon.

1989-01-01

A brief account is given of the 33rd session of IAEA General Conference held in Vienna from 25 to 29 September 1989. The Minister for Primary Industry and Energy, Mr John Kerin, led the Australian delegation. His statement to the General Conference highlighted Australia's role as a major uranium exporter, its committment to the Non-Proliferation of Nuclear Weapon Treaty and support for the role which the Agency plays in it. The major Australian policy initiatives in environmental areas were also outlined. Australia continues to make a substantial extra-budgetary contribution to the Regional Cooperation Agreement for Asia and Pacific (RCA), and it has recently expanded its committment by agreeing to support a series of new RCA projects. In this context, the role played by the Australian Nuclear Science and Technology Organization for the provision of technical assistance and cooperation in many areas of the Agency's activities is discussed. ills

Social Support and Personal Agency in At-Risk Mothers

Directory of Open Access Journals (Sweden)

María José Rodrigo

2011-04-01

Full Text Available This study investigated: a mothers´ use and satisfaction with informal and formal supports in at-risk psychosocial contexts, and b the relationships between satisfaction with help and the mothers´ perception of their role (personal agency. Self-report data about the use and satisfaction with sources of help, and levels of internal control, self-efficacy, couple agreement, role difficulty and motivation for change were obtained from 519 mothers referred by Social Services and 519 non-referred mothers. Results indicated that at-risk mothers relied less upon close informal support and more on formal support than non atrisk mothers. They were also more satisfied with the formal sources of support and had lower levels of personal agency. There were beneficial effects of satisfaction with informal help and school support on several aspects of personal agency for both groups. However, satisfaction with school and social services support had a detrimental effect on couple agreement in the at-risk group. Implications of the results for providing social support to at-risk families are discussed.

78 FR 30233 - Defense Federal Acquisition Regulation Supplement; Government Support Contractor Access to...

Science.gov (United States)

2013-05-22

... Number 0750-AG38 Defense Federal Acquisition Regulation Supplement; Government Support Contractor Access... Government support contractors to have access to proprietary technical data belonging to prime contractors and other third parties, provided that the technical data owner may require the support contractor to...

Atomic structure of CaF2/MnF2-Si(1 1 1) superlattices from X-ray diffraction

International Nuclear Information System (INIS)

Alcock, Simon G.; Nicklin, C.L.; Howes, P.B.; Norris, C.A.; Kyutt, R.N.; Sokolov, N.S.; Yakovlev, N.L.

2007-01-01

X-ray reflectivity and non-specular crystal truncation rod scans have been used to determine the three-dimensional atomic structure of the buried CaF 2 -Si(1 1 1) interface and ultrathin films of MnF 2 and CaF 2 within a superlattice. We show that ultrathin films of MnF 2 , below a critical thickness of approximately four monolayers, are crystalline, pseudomorphic, and adopt the fluorite structure of CaF 2 . High temperature deposition of the CaF 2 buffer layer produces a fully reacted, CaF 2 -Si(1 1 1) type-B interface. The mature, 'long' interface is shown to consist of a partially occupied layer of CaF bonded to the Si substrate, followed by a distorted CaF layer. Our atomistic, semi-kinematical scattering method extends the slab reflectivity method by providing in-plane structural information

Earth sciences 1980-1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-04-01

This catalogue lists sales publications of the International Atomic Energy Agency dealing with Earth Sciences issued during the period 1969-1994. Most publications are published in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all these papers have abstracts in English. It should be noted that prices of books are quoted in Austrian Schillings. The prices do not include local taxes and are subject to change without notice. All books in this catalogue are 16 x 24 cm, paper-bound, unless otherwise stated

A Summary of the Rendezvous, Proximity Operations, Docking, and Undocking (RPODU) Lessons Learned from the Defense Advanced Research Project Agency (DARPA) Orbital Express (OE) Demonstration System Mission

Science.gov (United States)

Dennehy, Cornelius J.; Carpenter, James R.

2011-01-01

The Guidance, Navigation, and Control (GN&C) Technical Discipline Team (TDT) sponsored Dr. J. Russell Carpenter, a Navigation and Rendezvous Subject Matter Expert (SME) from NASA's Goddard Space Flight Center (GSFC), to provide support to the Defense Advanced Research Project Agency (DARPA) Orbital Express (OE) rendezvous and docking flight test that was conducted in 2007. When that DARPA OE mission was completed, Mr. Neil Dennehy, NASA Technical Fellow for GN&C, requested Dr. Carpenter document his findings (lessons learned) and recommendations for future rendezvous missions resulting from his OE support experience. This report captures lessons specifically from anomalies that occurred during one of OE's unmated operations.

Abnormal General Ledger Account Balances for Other Defense Organizations Reported by DFAS Cleveland

National Research Council Canada - National Science Library

2001-01-01

... and other Government agencies to prepare annual audited financial statements. This report is the second in a series of reports supporting our audit of the FY 2000 financial statements for "Other Defense Organizations-General Funds...

Nuclear techniques in food and agriculture. 1980-1994. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1995-04-01

The catalogue lists all publications of the International Atomic Energy Agency dealing with Food And Agriculture during the period 1980-1994. The major subjects covered include: food irradiation, insect and pest control, mutation plant breeding, plant biotechnology, soil fertility and irrigation, agrochemicals animal production and health

NFR TRIGA package design review report

International Nuclear Information System (INIS)

Clements, M.D.

1994-01-01

The purpose of this document is to compile, present and document the formal design review of the NRF TRIGA packaging. The contents of this document include: the briefing meeting presentations, package description, design calculations, package review drawings, meeting minutes, action item lists, review comment records, final resolutions, and released drawings. This design review required more than two meeting to resolve comments. Therefore, there are three meeting minutes and two action item lists

Defense radioactive waste management

International Nuclear Information System (INIS)

Hindman, T.B. Jr.

1988-01-01

The Office of Defense Programs (DP), U.S. Department of Energy, is responsible for the production of nuclear weapons and materials for national defense. Pursuant to this mission, DP operates a large industrial complex that employs over 60,000 people at various installations across the country. As a byproduct of their activities, these installations generate radioactive, hazardous, or mixed wastes that must be managed in a safe and cost-effective manner in compliance with all applicable Federal and STate environmental requirements. At the Federal level such requirements derive primarily from the Atomic Energy Act, the Resource Conservation and Recovery Act (RCRA), the comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Superfund Amendments and Reauthorization Act (SARA). Responsibility for DP activities in connection with the disposal of defense wastes is consolidated within the Office of Defense Waste and Transportation Management (DWTM). This paper discusses these activities which consist of five principal elements: the environmental restoration of inactive DP facilities and sites, the processing storage and disposal of wastes associated with ongoing operations at active DP facilities, research and development directed toward the long-term disposal of radioactive, hazardous, mixed wastes, technology development directly supporting regulatory compliance, and the development of policies, procedures, and technologies for assuring the safe transportation of radioactive and hazardous materials

TRIGA reactor operating experience

International Nuclear Information System (INIS)

Anderson, T.V.

1970-01-01

The Oregon State TRIGA Reactor (OSTR) has been in operation 3 years. Last August it was upgraded from 250 kW to 1000 kW. This was accomplished with little difficulty. During the 3 years of operation no major problems have been experienced. Most of the problems have been minor in nature and easily corrected. They came from lazy susan (dry bearing), Westronics Recorder (dead spots in the range), The Reg Rod Magnet Lead-in Circuit (a new type lead-in wire that does not require the lead-in cord to coil during rod withdrawal hss been delivered, much better than the original) and other small corrections

Defense Base Realignment and Closure Budget Data for the Closure of Gentile Air Force Station, Dayton, Ohio, and Realignment of Defense Logistics Agency Components to Wright-Patterson Air Force Base, Ohio

National Research Council Canada - National Science Library

1996-01-01

.... This report provides the results of the audit of two projects, valued at $5.5 million, for the closure of Gentile Air Force Station, Dayton, Ohio, and realignment to Wright-Patterson Air Force Base, Ohio, of two Defense Logistics Agency components...

Twenty years of Triga Mark I reactor use

International Nuclear Information System (INIS)

Stasiulevicius, R.; Maretti Junior, F.

1981-01-01

This work is a report on the 20 years of activities of the Triga Mark I, research reactor located in Belo Horizonte, Brazil. It contains also a list of publications, details of operation and improvements introduced in the reactor as well as some perspectives for its future. (A.C.A.S.)

Prenatal choline supplementation attenuates MK-801-induced deficits in memory, motor function, and hippocampal plasticity in adult male rats.

Science.gov (United States)

Nickerson, Chelsea A; Brown, Alexandra L; Yu, Waylin; Chun, Yoona; Glenn, Melissa J

2017-10-11

Choline is essential to the development and function of the central nervous system and supplemental choline during development is neuroprotective against a variety of insults, including neurotoxins like dizocilpine (MK-801). MK-801 is an NMDA receptor antagonist that is frequently used in rodent models of psychological disorders, particularly schizophrenia. At low doses, it causes cognitive impairments, and at higher doses it induces motor deficits, anhedonia, and neuronal degeneration. The primary goals of the present study were to investigate whether prenatal choline supplementation protects against the cognitive impairments, motor deficits, and neuropathologies that are precipitated by MK-801 administration in adulthood. Adult male Sprague-Dawley rats were fed a standard or supplemented choline diet prenatally. Using the novelty preference test of object recognition, we found that only prenatal standard-fed rats displayed memory consolidation deficits induced by low-dose MK-801 administered immediately following study of sample objects; all other groups, including prenatal choline supplemented rats given MK-801, showed intact memory. Following high-dose MK-801, prenatal choline supplementation significantly alleviated rats' motor response to MK-801, particularly ataxia. Using doublecortin and Ki67 to mark neurogenesis and cell division, respectively, in the hippocampus, we found that prenatal choline supplementation, in the face of MK-801 toxicity, protected against reduced hippocampal plasticity. Taken together, the current findings suggest that prenatal choline supplementation protects against a variety of behavioral and neural pathologies induced by the neurotoxin, MK-801. This research contributes to the growing body of evidence supporting the robust neuroprotective capacity of choline. Copyright © 2017 IBRO. Published by Elsevier Ltd. All rights reserved.

Australia and the International Atomic Energy Agency

International Nuclear Information System (INIS)

1987-01-01

Australia's support for the IAEA's safeguards program is described. Through a program of bilateral assistance to the Agency, Austrlia has developed and sponsored special programs of assistance to the IAEA's Safeguards over the period 1980 to 1986. The speech by the Minister for Foreign Affairs and Trade, Mr Bill Hayden, to the IAEA Thirtieth Anniversary Conference in Vienna on 21 September 1987 is included

Seven years of operation of the U. S. geological survey TRIGA reactor

International Nuclear Information System (INIS)

Kraker, Pat

1976-01-01

February 1976 marks 7 years of operation of the U. S. Geological Survey TRIGA Reactor (GSTR) facility. In these 7 years we have generated more than 5800 MWH's of thermal energy and irradiated more than 47,000 samples for experimenters from the Survey, universities, and other Governmental agencies. Several mechanical and electrical components have required attention. Changes to the technical specifications have included one minor wording change involving the evacuation alarm, a reevaluation of the measurement of argon-41 concentrations, a revision concerning transient-rod maintenance, and a reduction in the frequency of fuel-element measurements. To improve physical security we have increased building security, installed an intrusion alarm, and, most recently, expanded the boundaries of the facility within the building to provide better control access. There also have been major changes to our operating procedures and the initiation of a reactor-operator requalification program. (author)

Assessment of the role of the International Atomic Energy Agency in relevant human resources development in Sudan during the period 1999-2004

International Nuclear Information System (INIS)

Awadalla, S.A.

2006-02-01

The objective of the study is to evaluate the role of International Atomic Energy Agency in human resources development. The Agency is believed to be one of the specialized U N organizations aiming at peaceful applications of atomic energy in areas such as human health, animal health, agriculture, industry. Sudan joined the Agency in 1958 to make use of assistance provided to establish human development projects in the country through technical cooperation. Through this study, the role of research projects has been highlighted and the impact on human resources development and service enhancement is discussed. The annual reports from the Agency and the competent authority were the secondary sources. The primary source was personal interviews with national coordinators and director general of Sudan Atomic Energy Commission. The study concluded that the technical assistance from the Agency played a significant role in development through technology transfer especially in waste management, non-destructive testing, and human health. The role of Sudan Atomic Energy Commission in management of such projects is acknowledged.(Author)

Assessment of the role of the International Atomic Energy Agency in relevant human resources development in Sudan during the period 1999-2004

Energy Technology Data Exchange (ETDEWEB)

Awadalla, S A [Development Studies and Research Institute, University of Khartoum, Khartoum (Sudan)

2006-02-15

The objective of the study is to evaluate the role of International Atomic Energy Agency in human resources development. The Agency is believed to be one of the specialized U N organizations aiming at peaceful applications of atomic energy in areas such as human health, animal health, agriculture, industry. Sudan joined the Agency in 1958 to make use of assistance provided to establish human development projects in the country through technical cooperation. Through this study, the role of research projects has been highlighted and the impact on human resources development and service enhancement is discussed. The annual reports from the Agency and the competent authority were the secondary sources. The primary source was personal interviews with national coordinators and director general of Sudan Atomic Energy Commission. The study concluded that the technical assistance from the Agency played a significant role in development through technology transfer especially in waste management, non-destructive testing, and human health. The role of Sudan Atomic Energy Commission in management of such projects is acknowledged.(Author)

The role of the International Atomic Energy Agency in radiation and waste safety

International Nuclear Information System (INIS)

Wrixon, A.D.; Ortiz-Lopez, P.

1999-01-01

The International Atomic Energy Agency is specifically required by its Statute 'to establish or adopt ... standards of safety for protection of health and minimization of danger to life and property ... and to provide for the application of these standards ...'. Standards encompass three main elements: legally binding international undertakings among States; globally agreed international safety standards; and the provision for facilitating the application of those standards. Radiation safety standards are national responsibilities, but there is considerable value in formulating harmonized approaches throughout the world. The Agency has attempted to do this by establishing internationally agreed safety standards and by prompting their application. Of prime importance are the Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. These deal with the basic requirements that must be met in order to ensure an adequate standard of safety. More detailed guidance on the application of these requirements is given in Safety Guides established under them. Fuller technical support is given in a series of Safety Reports. A number of Safety Guides are relevant to this meeting. An existing Safety Guide on exemption is being revised to cover related topics such as exclusion and clearance, and this is the subject of a separate presentation. As part of the programme to combat illicit trafficking in radioactive materials, a new Safety Guide on the topic is being developed. Both are near completion. Another Safety Guide is being produced to elaborate the requirements in the Basic Safety Standards on the safety of radioactive sources. The topics of illicit trafficking in radioactive materials and the safety of radioactive sources were given added impetus by resolutions of the last General Conference of the Agency. This paper provides an overview of these activities of the Agency. (author)

Planning and implementation of Istanbul Technical University TRIGA research reactor program

International Nuclear Information System (INIS)

Aybers, N.; Yavuz, H.; Bayulken, A.

1982-01-01

The Istanbul Technical University TRIGA Research Reactor at the Institute for Nuclear Energy, which went critical on March 11, 1979 is basically a pulsing type TRIGA Mark - II reactor. Completion of the ITU-TRR contributed to broaden the role of the Institute for Nuclear Energy of the Technical University in Istanbul in the nuclear field by providing for the first time adequate on-campus experimental facilities for nuclear engineering studies to ITU students. The research program which is currently under planning at ITU-NEE encompasses: a) Neutron activation analysis studies by techniques and applications to chemistry, mining, materials research, archaeological and biomedical studies; b) applications of Radioisotopes; c) Radiography with reactor neutron beams; d) Radiation Pulsing

MK classification of evolved blue stars in the halo

International Nuclear Information System (INIS)

Garrison, R.F.

1987-01-01

The problem of the masses and origin of the evolved blue stars is very complex. No single approach can give all the answers unambiguously; it would be naive to suppose otherwise. The MK process and the MK system give a perspective which complements photometric, kinematic, high dispersion and other quantitative data. It is useful to know which stars are similar (or not) in spectral morphology, so that interesting candidates can be selected for further study. In many cases, the gross physical characteristics can be fairly well determined by use of the MK System. 8 references

The effect of high curing temperature on the reaction kinetics in MK/lime and MK-blended cement matrices at 60 deg. C

International Nuclear Information System (INIS)

Rojas, Moises Frias; Sanchez de Rojas, M.I.

2003-01-01

It is well known that the pozzolanic reaction between metakaolin (MK) and calcium hydroxide produces CSH, C 2 ASH 8 (stratlingite), C 4 AH 13 and C 3 ASH 6 (hydrogarnet). However, the presence or absence of these hydrated phases depends on different parameters, such as curing temperature, matrix used, etc. This paper shows the results of a study in order to know the effect of high curing temperature (60 deg. C) on the kinetics of the pozzolanic reaction in different matrices. MK/lime (calcium hydroxide) and MK-blended cement matrices were studied in samples stored and cured at 60 deg. C and up to 123 days of hydration. The nature, sequence and crystallinity of the hydrated phases were analysed using differential thermal analysis (DTA) and X-ray diffraction (XRD) techniques. Results showed that the sequence and formation of the hydrated phases was different in both matrices cured at 60 deg. C. In an MK/lime matrix, C 2 ASH 8 , C 4 AH 13 and C 3 ASH 6 were the main hydrated phases; while in an MK-blended cement, stratlingite was the sole hydrated phase issued from pozzolanic reaction. The DTA and XRD data also reveal an important fact: there is no evidence of the presence of hydrogarnet in blended cements

The influence of Triga 2000 reactor operation on the surface contamination at reactor room using smear test method

International Nuclear Information System (INIS)

Bintu Khoiriyyah; Budi Purnama; Tri Cahyo Laksono

2016-01-01

The monitoring of surface contamination should be conducted to determine the safety of work areas. Surface contamination at the TRIGA 2000 reactor room which is on PSTNT-BATAN Bandung remain to be implemented although reactor not operating. In this research monitoring of surface contamination when TRIGA 2000 in operation of the first time after several years not operating aims to determine the influence on the results of monitoring. The monitoring of surface contamination has been done using smear test method at some predetermined in TRIGA 2000 reactor room. The highest surface contamination activities is obtained 0.32 Bq/cm 2 and there are some points that are not detected. Based on keputusan kepala BAPETEN No.1/Ka BAPETEN/ V/99 the work showed that the TRIGA 2000 reactor in the category of low area contamination, that is <3.7 Bq/cm 2 to gross beta. (author)

The role of international atomic energy agency in maintaining nuclear safety competence

International Nuclear Information System (INIS)

Aro, I.; Mazour, T.

2000-01-01

This paper provides information how International Atomic Energy Agency can assist Member States in maintaining and developing nuclear safety competence. The topics covered include the development of safety standards, organisation of nuclear safety related conferences, provision of safety reviews, organisation of training courses and topical workshops and publication of training related documents. Usefulness of these activities for competence development is discussed. (author)

Application of Code Of Conduct on the Safety of Research Reactor (RTP)

International Nuclear Information System (INIS)

Ligam, A.S.; Ahmad Nabil Abd Rahim; Zarina Masood

2014-01-01

The implementation and the practices of the effective safety system at research reactors are important to ensure that the worker, public and environment do not receive any abnormal causes. Many international safety related support agencies for research reactor such as International Atomic Energy Agency (IAEA) providing guidelines that can be applied to enhance and strengthen the enforcement of safety namely Code of Conduct on the Safety of Research Reactor (IAEA/CODEOC/RR/2006). The excellent safety management, reliability, and maintainability of RTP reactor structures, coupled with personnel numerous lessons and experiences learned, Reactor TRIGA PUSPATI research reactor providing Nuclear Malaysia personnel and visitor the very safe working and visiting environment. This paper will discuss the status, practices and improvement strategies over the past few years. (author)

IAEA technical documents (TECDOCs) 1992-2002. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2003-02-01

This catalogue lists all technical documents (TECDOCs) of the International Atomic Energy Agency issued between 1 January 1992 and 31 December 2002. It is divided into two parts. The first part lists all documents in numerical order, starting with the most recent publication. The second part lists all documents by subject category, in alphabetical order within each category. Most publications are issued in English, although some are also available in other languages

Nine years of operation of ITU-TRR TRIGA Mark-II reactor

International Nuclear Information System (INIS)

Yavuz, H.; Bayuelken, A.R.; Yavuz, M.A.

1988-01-01

ITU-TRR TRIGA Mark-II reactor in Istanbul with a steady state power of 250 kW and a pulsing capability up to 1200 MW has been operating since March 11,1979 with an energy release of 107.5 MWh and a total of 72 pulses. During this nearly nine years, the reactor was in operation without any major undesired shut down. One of the major problems was faced when the instrumented fuel element in position 9 of the F ring went totally out of order. Secondly, the cooling tower of the secondary cooling system could not be operated properly during the hot summer days, and also we had a tar leakage problem with the radial beam port connection to the tank. During the regular maintenance work in this summer, the measurements of changes in nuclear and physical parameters of the reactor fuel and dummy elements have also proceeded. (author)

Protocol between the Russian Federation and the International Atomic Energy Agency Additional to the Agreement between the Union of Soviet Socialist Republics and the International Atomic Energy Agency for the Application of Safeguards in the Union of Soviet Socialist Republics

International Nuclear Information System (INIS)

2008-01-01

The text of the Protocol between the Russian Federation and the International Atomic Energy Agency Additional to the Agreement between the Union of Soviet Socialist Republics and the International Atomic Energy Agency for the Application of Safeguards in the Union of Soviet Socialist Republics is reproduced in this document for the information of all Members. The Board of Governors approved the Protocol on 21 March 2000. It was signed on 22 March 2000 in Vienna. Pursuant to Article 11 of the Additional Protocol, the Protocol entered into force on 16 October 2007, the date on which the Agency received from the Russian Federation written notification that the procedures of the Russian Federation required for entry into force had been met

Protocol between the Russian Federation and the International Atomic Energy Agency Additional to the Agreement between the Union of Soviet Socialist Republics and the International Atomic Energy Agency for the Application of Safeguards in the Union of Soviet Socialist Republics

International Nuclear Information System (INIS)

2008-01-01

The text of the Protocol between the Russian Federation and the International Atomic Energy Agency Additional to the Agreement between the Union of Soviet Socialist Republics and the International Atomic Energy Agency for the Application of Safeguards in the Union of Soviet Socialist Republics is reproduced in this document for the information of all Members. The Board of Governors approved the Protocol on 21 March 2000. It was signed on 22 March 2000 in Vienna. Pursuant to Article 11 of the Additional Protocol, the Protocol entered into force on 16 October 2007, the date on which the Agency received from the Russian Federation written notification that the procedures of the Russian Federation required for entry into force had been met [es

The effects of the CXCR2 antagonist, MK-7123, on bone marrow functions in healthy subjects.

Science.gov (United States)

Hastrup, Nina; Khalilieh, Sauzanne; Dale, David C; Hanson, Lars G; Magnusson, Peter; Tzontcheva, Anjela; Tseng, Jack; Huyck, Susan; Rosenberg, Elizabeth; Krogsgaard, Kim

2015-04-01

The CXCR2 antagonist MK-7123 causes dose-dependent reductions in absolute neutrophil counts (ANC) and decreases neutrophil tissue responses, but its effects on bone marrow functions are not yet known. We conducted a double-blind, randomized study in 18 healthy subjects comparing the effects of either MK-7123 (30mg, po, daily for 28days) or placebo on peripheral blood counts and bone marrow myeloid cell populations. MK-7123 caused a reversible decrease (approximately 50%) in the ANC as demonstrated on days 1 and 28, the first and last days of the treatment period. Bone marrow aspirate smears and biopsy imprints did not differ in the proportion of mature neutrophils in pretreatment, day 28, day 56 or placebo samples. There were no treatment effects on biopsy or aspirate clot cellularity, myeloid to erythroid or myeloid post-mitotic to mitotic ratios; flow-cytometric analyses of aspirate cells; or bone marrow fat to cell balance as assessed by MRI. MK-7123 was generally well tolerated with neutropenia being the most common adverse event; however, there were no clinical symptoms associated with decreased ANCs. These findings indicate that the CXCR2 antagonist MK-7123 causes rapidly reversible decrease in the ANC without measurable myelosuppressive effects. The results support the development of CXCR2 antagonists as potentially useful anti-inflammatory agents, primarily interrupting neutrophil trafficking. Copyright © 2015. Published by Elsevier Ltd.

Neutronics analysis of TRIGA Mark II research reactor

Directory of Open Access Journals (Sweden)

Haseebur Rehman

2018-02-01

Full Text Available This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4 and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE codes. Cores 133 and 134 were analyzed in 2-D (r, θ and 3-D (r, θ, z, using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied using various libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0, Joint Evaluated Fission and Fusion File (JEFF-3.1, Japanese Evaluated Nuclear Data Library (JENDL-3.2, and Joint Evaluated File (JEF-2.2 nuclear data. The simulation results showed that the multiplication factor calculated for all these data libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134 was also calculated with different homogenization approaches. A comparison was made with experimental and reported Monte Carlo results, and it was found that, using proper homogenization of absorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantly improved.

Specimen rotation system of the WSU TRIGA-fueled reactor

International Nuclear Information System (INIS)

Lovas, Thomas A.

1976-01-01

The specimen rotation system presently in use at the WSU reactor has been designed to provide maximum utilization of the irradiation capabilities achieved through use of TRIGA-type fuel. This paper describes the system with particular emphasis on characteristics which are advantageous to experimenters. (author)

SAFARI engineering model 50 mK cooler

Science.gov (United States)

Duband, L.; Duval, J. M.; Luchier, N.

2014-11-01

SAFARI is an infrared instrument developed by a European based consortium to be flown in SPICA, a Japanese led mission. The SAFARI detectors are transition edge sensors (TES) and require temperatures down to 50 mK for their operation. For that purpose we have developed a hybrid architecture based on the combination of a 300 mK sorption stage and a small adiabatic demagnetization stage. An engineering model has been designed to provide net heat lifts of 0.4 and 14 μW respectively at 50 and 300 mK, with an overall cycle duration of 48 h and a duty cycle objective of over 75%. The cooler is self-contained, fits in a volume of 156 × 312 × 182 mm and is expected to weigh 5.1 kg. It has been designed to withstand static loads of 120 g and a random vibration level of 21 g RMS.

Studies on decommissioning of TRIGA reactors and site restoration technologies in the Republic of Korea

International Nuclear Information System (INIS)

Oh, Won-Zin; Kim, Gye-Nam; Won, Hui-Jun

2002-01-01

Research and development on research reactor decommissioning and environmental restoration has been carried out at KAERI since 1997 to prepare for the decommissioning of KAERI's two TRIGA-type research reactors, which had been shut down since 1995. A 3-D graphic model of the TRIGA research reactor was built using IGRIP. The dismantling process was simulated in the graphic environment to verify the feasibility of individual operations before the execution of the remote dismantling process. An under-water wall-climbing robot, moving by propeller injection, and identifying its coordinates by using a laser sensor, was developed and tested in the TRIGA reactor pool by measuring a radioactive contamination map of the reactor surface. Using MODFLOW and TRIGA site geological data, a computer simulation of the underground migration of residual radionuclides, after the TRIGA reactor decommissioning, was carried out. It was found that the underground migration rate was very slow such that, when radionuclide decay and dilution are considered, the residual radionuclides will not have a significant environmental impact. The soil decontamination R and D, using soil washing, solvent flushing and electro-decontamination technologies, was carried out to determine the best method for decontaminating the soil waste accumulated in KAERI. The decontamination results indicated that, using the soil washing method, more than 80% of the soil wastes could be decontaminated well enough to discharge them to the environment. It was also determined that the control of solution pH and temperature in the soil washing process is important for the reduction of decontamination waste. Further decontamination, using an electro-kinetic decontamination method, was considered necessary for the residual soil waste, which consisted mainly of fine soil particles. (author)

Installation and operation of a radio-frequency quadrupole cooler and buncher and offline commissioning of the TRIGA-SPEC ion beam preparation transfer line

International Nuclear Information System (INIS)

Beyer, Thomas

2014-01-01

The dominant fraction of elements heavier than iron was created in stellar nucleosynthesis by neutron-capture reactions. The isotopic compositions of these elements are the fingerprints of the involved processes, and a huge amount of experimental data on these isotopes is required to support corresponding astrophysical calculations and models. The TRIGA-SPEC experiment aims to contribute to these data by the measurement of ground-state properties of neutron-rich heavy nuclides. It consists of the Penning-trap mass spectrometer TRIGA-TRAP for the determination of masses, Q-values and binding energies, and the collinear laser spectroscopy setup TRIGALASER for the determination of charge radii, nuclear spins, and moments. The nuclides of interest are produced by neutron-induced fission of an actinide target inside the research reactor TRIGA Mainz and ionized in an online ion source. In the context of this thesis, the two experiments were coupled to the reactor, completing the ion beam preparation transfer line. This included the implementation and commissioning of a radio-frequency quadrupole for the emittance reduction and accumulation of the ions. The functionality of the ion beam preparation was verified by successful test measurements of stable nuclides produced in the online ion source.

76 FR 16736 - Closed Meeting of the Missile Defense Advisory Committee

Science.gov (United States)

2011-03-25

... DEPARTMENT OF DEFENSE Office of the Secretary Closed Meeting of the Missile Defense Advisory Committee AGENCY: Missile Defense Agency (MDA), DoD. ACTION: Notice of closed meeting. SUMMARY: Under the...: Missile Defense Advisory Committee. Dates of Meeting: Thursday, March 24, 2011. Times: 8 a.m. to 5:30 p.m...

The neutron and gamma-ray dose characterization using the Monte Carlo method to study the feasibility of the Prompt Gamma Activation Analysis technique at IPR-R1 TRIGA reactor in Brazil

Energy Technology Data Exchange (ETDEWEB)

Guerra, Bruno T.; Soares, Alexandre L.; Grynberg, Suely E.; Menezes, Maria Angela B.C., E-mail: brunoteixeiraguerra@yahoo.com.br, E-mail: menezes@cdtn.br, E-mail: asleal@cdtn.br, E-mail: seg@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2013-07-01

The IPR-R1 is a reactor type TRIGA, Mark-I model, manufactured by the General Atomic Company and installed at Nuclear Technology Development Centre (CDTN) of Brazilian Nuclear Energy Commission (CNEN), in Belo Horizonte, Brazil. It is a light water moderated and cooled, graphite-reflected, open-pool type research reactor. IPR-R1 works at 100 kW but it will be briefly licensed to operate at 250 kW. It presents low power, low pressure, for application in research, training and radioisotopes production. The fuel is an alloy of zirconium hydride and uranium enriched at 20% in {sup 235}U. The Implementation of the PGNAA (Prompt Gamma Neutron Activation Analysis) Technical at the TRIGA IPR-R1 research reactor of the CDTN will significantly increase in the types of matrices analyzable. A project is underway in order to implement this technique in CDTN. In order of verified the feasibility of the PGNAA at the TRIGA reactor, the MCNP (Monte Carlo N-Particle) method is used to theoretical calculations. This paper presents the results of a preliminary study of the neutron and gamma-ray dose in the room where the reactor is located, in case of implementation of this technique in the IPR-R1. (author)

The neutron and gamma-ray dose characterization using the Monte Carlo method to study the feasibility of the Prompt Gamma Activation Analysis technique at IPR-R1 TRIGA reactor in Brazil

International Nuclear Information System (INIS)

Guerra, Bruno T.; Soares, Alexandre L.; Grynberg, Suely E.; Menezes, Maria Angela B.C.

2013-01-01

The IPR-R1 is a reactor type TRIGA, Mark-I model, manufactured by the General Atomic Company and installed at Nuclear Technology Development Centre (CDTN) of Brazilian Nuclear Energy Commission (CNEN), in Belo Horizonte, Brazil. It is a light water moderated and cooled, graphite-reflected, open-pool type research reactor. IPR-R1 works at 100 kW but it will be briefly licensed to operate at 250 kW. It presents low power, low pressure, for application in research, training and radioisotopes production. The fuel is an alloy of zirconium hydride and uranium enriched at 20% in 235 U. The Implementation of the PGNAA (Prompt Gamma Neutron Activation Analysis) Technical at the TRIGA IPR-R1 research reactor of the CDTN will significantly increase in the types of matrices analyzable. A project is underway in order to implement this technique in CDTN. In order of verified the feasibility of the PGNAA at the TRIGA reactor, the MCNP (Monte Carlo N-Particle) method is used to theoretical calculations. This paper presents the results of a preliminary study of the neutron and gamma-ray dose in the room where the reactor is located, in case of implementation of this technique in the IPR-R1. (author)

Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests

International Nuclear Information System (INIS)

Liu, Y.Y.; Tsai, H.; Billone, M.C.; Kramer, J.M.

1992-01-01

The next step in the development of metal fuels for the integral fast reactor (IFR) is the conversion of the Experimental Breeder Reactor II (EBR-II) core to one containing the ternary U-20 Pu-10 Zr alloy clad with HT-9 cladding, i.e., the Mk-V core. This paper presents results of three hot-cell furnace simulation tests on irradiated Mk-V-type fuel elements (U-19 Pu-10 Zr/HT-9), which were performed to support the safety case for the Mk-V core. These tests were designed to envelop an umbrella (bounding) unlikely loss-of-flow (LOF) event in EBR-II during which the calculated peak cladding temperature would reach 776 degree C for < 2 min. The principal objectives of these tests were (a) demonstration of the safety margin of the fuel element, (b) investigation of cladding breaching behavior, and (c) provision of data for validation of the FPIN2 and LIFE-METAL codes

77 FR 76938 - Defense Federal Acquisition Regulation Supplement: Contracting Activity Updates (DFARS Case 2012...

Science.gov (United States)

2012-12-31

... Security Cooperation Agency, the Defense Security Service, the Defense Threat Reduction Agency, the Missile... DEPARTMENT OF DEFENSE Defense Acquisition Regulations System 48 CFR Part 202 RIN 0750-AH81 Defense...: Defense Acquisition Regulations System, Department of Defense (DoD). ACTION: Final rule. SUMMARY: DoD is...

Experience in the recruitment, organization and training of operations and maintenance personnel for the Malaysian research reactor

International Nuclear Information System (INIS)

Jamal Khair Ibrahim.

1983-01-01

The TRIGA Reactor located at the Tun Ismail Atomic Research Centre (PUSPATI) Complex is owned and operated by the Nuclear Energy Unit of the Prime Minster's Department. The operations and maintenance personnel are part and parcel of the national civil service organization. As such, the requirement and remuneration of these personnel are handled by a central federal government personnel management agency in common with personnel from other federal government agencies. In addition, the reactor is the first and only one in Malaysia, a developing country, which is the process of committing herself towards a nuclear power programme. These factors coupled with the absence of an independent reactor operator licensing agency posed unique problems in the recruitment, organization, training and licensing of operations personnel for the facility. The paper discusses these factors and their bearing on the recruitment, training, licensing and career development prospects of the PUSPATI TRIGA Reactor operators. (author)

Thinking, doing and support. Background report

International Nuclear Information System (INIS)

Verhue, D.; Binnema, H.; Mulder, S.

2007-09-01

By request of the Netherlands Environmental Assessment Agency, Veldkamp and TNS NIPO conducted research on the societal support for the acceptance of measures for the solution of a number of sustainability issues in February and March 2007. The objective of this study was to determine which characteristics of measures determine societal support and how this coheres with the issue that is solved with the measures. Measures that were examined entailed the sustainability issues biodiversity and climate change. In the case of biodiversity measures were examines that deal with the limitation of space utilization, whereas in climate change measures were examined that focus on energy saving and electricity generation. Moreover, for development cooperation, the type of aid with the greatest support has been identified. [mk] [nl

Specifications of the International Atomic Energy Agency's international project on safety assessment driven radioactive waste management solutions

International Nuclear Information System (INIS)

Ghannadi, M.; Asgharizadeh, F.; Assadi, M. R.

2008-01-01

Radioactive waste is produced in the generation of nuclear power and the production and use of radioactive materials in the industry, research, and medicine. The nuclear waste management facilities need to perform a safety assessment in order to ensure the safety of a facility. Nuclear safety assessment is a structured and systematic way of examining a proposed facility, process, operation and activity. In nuclear waste management point of view, safety assessment is a process which is used to evaluate the safety of radioactive waste management and disposal facilities. In this regard the International Atomic Energy Agency is planed to implement an international project with cooperation of some member states. The Safety Assessment Driving Radioactive Waste Management Solutions Project is an international programme of work to examine international approaches to safety assessment in aspects of p redisposal r adioactive waste management, including waste conditioning and storage. This study is described the rationale, common aspects, scope, objectives, work plan and anticipated outcomes of the project with refer to International Atomic Energy Agency's documents, such as International Atomic Energy Agency's Safety Standards, as well as the Safety Assessment Driving Radioactive Waste Management Solutions project reports

Performances on nuclear activation analysis by TRIGA Mark II reactor

International Nuclear Information System (INIS)

Capannesi, G.; Rosada, A.

1986-01-01

Progresses in methodological research and connected applications in the field of activation analysis are introduced. Some peculiar characteristics on the TRIGA MARK II reactor have enabled the possibility of obtaining interesting results. The particular, the rotating radiation device Lazy Susan, with a capability of 40 positionings, permits homogeneity in neutron flux and energy spectrum stability within 15%. High level of precision and accuracy are obtained in analytic. Applications of major interest have been: - reference material certification; - forensic applications; - electrolytic cell productivity evaluation. The TRIGA MARK II reactor is equipped with a thermal column throughout a D 2 O diaphragm with a thickness of 70 cm. The available neutron flux has no fast and epithermal components. Via this facility a method has been tested for the instrumental determination of Al in Si metal of solar and electronic degree. (author)

Development of the Fuel Element Database of PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Nurhayati Ramli; Naim Syauqi Hamzah; Nurfazila Husain; Yahya Ismail; Mat Zin Mat Husin; Mohd Fairus Abd Farid

2015-01-01

Since June 28th, 1982, the PUSPATI TRIGA Reactor (RTP) operates safely with an accumulated energy release of about 17,200 MWhr, which corresponds to about 882 g of uranium burn-up. The reactor core has been reconfigured 15th times. Presently, there are 111 TRIGA fuel elements in the core, which 66 of the fuel elements are from the initial criticality while the rest of the fuel elements have been added to compensate the uranium consumption. As 59 % of the fuel elements are older than 30 years old, it is necessary to put the history of every fuel element in a database for easy access of the fuel element movement, inspection results history and integrity status. This paper intends to describe how the fuel element database is developed and related formulae used in determining the RTP fuel element elongation. (author)

A Planetary Defense Gateway for Smart Discovery of relevant Information for Decision Support

Science.gov (United States)

Bambacus, Myra; Yang, Chaowei Phil; Leung, Ronald Y.; Barbee, Brent; Nuth, Joseph A.; Seery, Bernard; Jiang, Yongyao; Qin, Han; Li, Yun; Yu, Manzhu;

Defensive Federal Litigation

Science.gov (United States)

1998-08-20

requires that all affirmative defenses be pleaded in the answer. The rule lists 19 specific affirmative defenses, such as estoppel , laches, res judicata...Brown, 22 F.3d 516 (2d Cir. 1994); Poole v. Rourke, 779 F. Supp. 1546 (E.D. Cal. 1991). 3-40 potential collateral estoppel .4. effect of the district...the back pay claim, which was over $10,000, to the Court of Claims. The court of appeals found that ൸Collateral estoppel prohibits relitigation of

Tunable reactivity of supported single metal atoms by impurity engineering of the MgO(001) support.