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1

EIS-0271: Construction and Operation of a Tritium Extraction Facility at  

Broader source: Energy.gov (indexed) [DOE]

EIS-0271: Construction and Operation of a Tritium Extraction EIS-0271: Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site EIS-0271: Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site SUMMARY DOE proposes to construct and operate a Tritium Extraction Facility (TEF) at H Area on the Savannah River Site (SRS) to provide the capability to extract tritium from commercial light water reactor (CLWR) targets and from targets of similar design. The proposed action is also DOE's preferred alternative. An action alternative is to construct and operate TEF at the Allied General Nuclear Services facility, which is adjacent to the eastern side of the SRS. Under the no-action alternative DOE could incorporate tritium extraction capabilities in the accelerator for production of

2

Commercial Light Water Reactor -Tritium Extraction Facility Process Waste Assessment (Project S-6091)  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has been tasked by the Department of Energy (DOE) to design and construct a Tritium Extraction Facility (TEF) to process irradiated tritium producing burnable absorber rods (TPBARs) from a Commercial Light Water Reactor (CLWR). The plan is for the CLWR-TEF to provide tritium to the SRS Replacement Tritium Facility (RTF) in Building 233-H in support of DOE requirements. The CLWR-TEF is being designed to provide 3 kg of new tritium per year, from TPBARS and other sources of tritium (Ref. 1-4).The CLWR TPBAR concept is being developed by Pacific Northwest National Laboratory (PNNL). The TPBAR assemblies will be irradiated in a Commercial Utility light water nuclear reactor and transported to the SRS for tritium extraction and processing at the CLWR-TEF. A Conceptual Design Report for the CLWR-TEF Project was issued in July 1997 (Ref. 4).The scope of this Process Waste Assessment (PWA) will be limited to CLWR-TEF processing of CLWR irradiated TPBARs. Although the CLWR- TEF will also be designed to extract APT tritium-containing materials, they will be excluded at this time to facilitate timely development of this PWA. As with any process, CLWR-TEF waste stream characteristics will depend on process feedstock and contaminant sources. If irradiated APT tritium-containing materials are to be processed in the CLWR-TEF, this PWA should be revised to reflect the introduction of this contaminant source term.

Hsu, R.H.; Delley, A.O.; Alexander, G.J.; Clark, E.A.; Holder, J.S.; Lutz, R.N.; Malstrom, R.A.; Nobles, B.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Carson, S.D. [Sandia National Laboratories, New Mexico, NM (United States); Peterson, P.K. [Sandia National Laboratories, New Mexico, NM (United States)

1997-11-30T23:59:59.000Z

3

Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site  

Broader source: Energy.gov (indexed) [DOE]

T T E D S T A T E S O F A M E R I C A D E P A R T M E NT O F E N E R G Y DOE/EIS-0271 Construction & Operation of a Tritium Extraction Facility at the Savannah River Site Department of Energy Savannah River Operations Office Aiken, South Carolina Final Environmental Impact Statement March 1999 DOE/EIS-0271 March 1999 Preface iii COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement: Construction and Operation of a Tritium Extraction Facility at the Savannah River Site (DOE/EIS-0271) LOCATION: Aiken and Barnwell Counties, South Carolina CONTACT: For additional information on this environmental impact statement (EIS), write or call: Andrew R. Grainger, NEPA Compliance Officer U.S. Department of Energy

4

Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site  

Broader source: Energy.gov (indexed) [DOE]

1 1 March 1999 Summary S-1 SUMMARY S.1 Introduction and Background The U.S. Department of Energy (DOE) is re- sponsible for ensuring that the nation has a sup- ply of materials sufficient to maintain its nuclear weapons stockpile at levels directed by the President of the United States. One of these materials is tritium - a gaseous isotope of hy- drogen that increases the yield of nuclear weap- ons. None of the weapons in the nuclear arsenal would be capable of functioning as designed without tritium. As long as the United States chooses to maintain a nuclear deterrent - of any size - it will need tritium. There are two factors that dictate the timing re- garding the nation's need for tritium. The first is that the U.S. no longer has the operating facili- ties needed to produce tritium. DOE has shut

5

Weapons engineering tritium facility overview  

SciTech Connect (OSTI)

Materials provide an overview of the Weapons Engineering Tritium Facility (WETF) as introductory material for January 2011 visit to SRS. Purpose of the visit is to discuss Safety Basis, Conduct of Engineering, and Conduct of Operations. WETF general description and general GTS program capabilities are presented in an unclassified format.

Najera, Larry [Los Alamos National Laboratory

2011-01-20T23:59:59.000Z

6

Type B Investigation Board Report on the April 2, 2002, Worker Fall from Shoring/Scaffolding Structure at the Savannah River Site Tritium Extraction Facility Construction Site  

Broader source: Energy.gov [DOE]

On April 2, 2002, a carpenter helping to erect shoring/scaffolding fell about 52” and struck his head. He sustained head injuries requiring hospitalization that exceeded the threshold for a Type B investigation in accordance with Department of Energy (DOE) Order 225.1A, Accident Investigation. The accident occurred at the DOE’s Savannah River Site (SRS) at the Tritium Extraction Facility (TEF) construction site.

7

Radiological Training for Tritium Facilities  

Broader source: Energy.gov (indexed) [DOE]

Change Notice No. 2 Change Notice No. 2 May 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 2. Radiological Safety Training for Tritium Facilities DOE-HDBK-1105-2002 Page/Section Change Part 1, page 14 Change: U.S. Department of Energy, Radiological Control

8

Radiological Training for Tritium Facilities  

Broader source: Energy.gov (indexed) [DOE]

DOE HANDBOOK DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 1. Radiological Safety Training for Tritium Facilities DOE-HDBK-1105-2002 Page/Section Change Cover sheets parts 1, 2, 3, and 4 Change: Office of Environment, Safety & Health

9

The Safety and Tritium Applied Research Facility  

Science Journals Connector (OSTI)

Device, Facility, and Operation / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

R. A. Anderl; D. A. Petti; K. A. McCarthy; G. R. Longhurst

10

Tritium Recycling (Processing) Facility Design  

Science Journals Connector (OSTI)

Design, Operation, and Maintenance of Tritium System / Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

Jack Metzler; Thuy Le

11

Tritium emission reduction at Darlington tritium removal facility using a Bubbler System  

SciTech Connect (OSTI)

Ontario Power Generation Nuclear (OPGN) has a 4 x 880 MWe CANDU nuclear station at its Darlington Nuclear Div. located in Bowmanville. The station operates a Tritium Removal Facility (TRF) to reduce and maintain low tritium levels in the Moderator and Heat Transport heavy water systems of Ontario's CANDU fleet by extracting, concentrating, immobilizing and storing as a metal tritide. Minimizing tritium releases to the environment is of paramount importance to ensure that dose to the public is as low as reasonably achievable (ALARA) and to maintain credibility with the Public. Tritium is removed from the Cryogenic Distillation System to the Tritium Immobilization System (TIS) glove box via a transfer line that is protected by a rupture disc and relief valve. An overpressure event in 2003 had caused the rupture disc to blow, resulting in the release of a significant quantity of elemental tritium into the relief valve discharge line, which ties into the contaminated exhaust system. As a result of a few similar events occurring over a number of years of TRF operation, the released elemental tritium would have been converted to tritium oxide in the presence of a stagnant moist air environment in the stainless steel discharge line. A significant amount of tritium oxide hold-up in the discharge line was anticipated. To minimize any further releases to the environment, a Bubbler System was designed to remove and recover the tritium from the discharge line. This paper summarizes the results of several Bubbler recovery runs that were made over a period of a month. Approximately 3500 Ci of tritium oxide and 230 Ci of elemental tritium were removed and collected. The tritium contained in the water produced from the Bubbler system was later safely recovered in the station's downgraded D{sub 2}O clean-up and recovery system. (authors)

Kalyanam, K.; Leilabadi, A.; El-Behairy, O.; Williams, G. I. D.; Vogt, H. K. [Ontario Power Generation, Darlington Nuclear, PO Box 4000, Bowmanville, ON L1C 3Z8 (Canada)

2008-07-15T23:59:59.000Z

12

An introduction to the National Tritium Labeling Facility  

SciTech Connect (OSTI)

The facilities and projects of the National Tritium Labeling Facility are described. 5 refs., 1 fig., 1 tab.

Dorsky, A.M.; Morimoto, H.; Saljoughian, M.; Williams, P.G.; Rapoport, H.

1988-06-01T23:59:59.000Z

13

Radiological training for tritium facilities  

SciTech Connect (OSTI)

This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835.

NONE

1996-12-01T23:59:59.000Z

14

Independent Oversight Review, Savannah River Site Tritium Facilities -  

Broader source: Energy.gov (indexed) [DOE]

Tritium Tritium Facilities - December 2012 Independent Oversight Review, Savannah River Site Tritium Facilities - December 2012 December 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Savannah River Site Tritium Facilities The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent review of preparedness for severe natural phenomena events (NPEs) at the National Nuclear Security Administration (NNSA) Savannah River Site's (SRS's) Tritium Facilities (TF). The HSS Office of Safety and Emergency Management Evaluations performed this review to evaluate the processes for identifying emergency response capabilities and maintaining them in a state of readiness in case of a severe NPE.

15

Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)  

SciTech Connect (OSTI)

Under the Tritium Facility Modernization {ampersand} Consolidation (TFM{ampersand}C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM{ampersand}C Project also provides for a new replacement R&D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H.

Hsu, R.H. [Westinghouse Savannah River Company, AIKEN, SC (United States); Oji, L.N.

1997-11-14T23:59:59.000Z

16

Operational Readiness Review: Savannah River Replacement Tritium Facility  

SciTech Connect (OSTI)

The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members.

Not Available

1993-02-01T23:59:59.000Z

17

Linear plasma-based tritium production facility  

SciTech Connect (OSTI)

The concept presented here is an adaptation of a recently completed conceptual design of a compact high-fluence D-T neutron source for accelerated end-of-life testing of fusion reactor materials. Although this preliminary assessment serves to illustrate the main features of a linear plasma-based tritium breeder, it is not necessarily an optimized design. We believe that proper design choices for the breeder application will certainly reduce costs, perhaps as much as a factor of two. We also point out that Q (the ratio of fusion power produced to power input to the plasma) increases with system length and that the cost per kg of tritium decreases for longer systems with higher output. In earlier studies of linear two-component plasma systems, Q values as high as three were predicted. At this level of performance and with energy recovery, operating power requirements of the breeder could approach zero. 5 refs., 1 fig., 1 tab.

Coensgen, F.H.; Futch, A.H.; Molvik, A.W.

1989-02-15T23:59:59.000Z

18

Determination of tritiated formaldehyde in effluents from tritium facilities  

SciTech Connect (OSTI)

Recent observations suggested that formal-dehyde can be incorporated in vegetation at a very high rate. In this paper, the authors develop a methodology for determining tritiated formaldehyde (CHTO) in gaseous effluent containing HTO and HT as dominant species. CHTO being very soluble in water is collected in a solution of carrier formaldehyde. This carrier is necessary for precipitating for formaldehyde derivative of dimedone and collecting it by filtration. The precipitate, which contains the formaldehyde hydrogens, is freed from exchangeable tritium, dried in oven, and combusted to water for tritium determination. CHTO can thus be separated from HTO with a high efficiency, leading to the possibility of determining accurately 1 Bq of CHTO in as much as 5 {times} 10{sup 4} Bq of HTO. The methodology has been applied in preliminary experiments to determine the ratio of CHTO to HTO in effluent from a tritium-handling facility and effluent released from solid miscellaneous wastes.

Belot, Y.; Camus, H.; Marini, T. (Commissariat a l'Energie Atomique, DPEI/SERGD, BP 6, F-92265 Fontenay aux Roses Cedex (FR))

1992-03-01T23:59:59.000Z

19

Health physics manual of good practices for tritium facilities  

SciTech Connect (OSTI)

The purpose of this document is to provide written guidance defining the generally accepted good practices in use at Department of Energy (DOE) tritium facilities. A {open_quotes}good practice{close_quotes} is an action, policy, or procedure that enhances the radiation protection program at a DOE site. The information selected for inclusion in this document should help readers achieve an understanding of the key radiation protection issues at tritium facilities and provide guidance as to what characterizes excellence from a radiation protection point of view. The ALARA (As Low as Reasonable Achievable) program at DOE sites should be based, in part, on following the good practices that apply to their operations.

Blauvelt, R.K.; Deaton, M.R.; Gill, J.T. [and others

1991-12-01T23:59:59.000Z

20

Radiochemical characteristics of tritium to be considered in fusion reactor facility design  

Science Journals Connector (OSTI)

The results of research and development related to radiochemical characteristics of tritium to be considered in a fusion reactor facility design are summarized. Reactions induced by...

S. O’hira; T. Hayashi; W. Shu; T. Yamanishi

2007-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Safety System Oversight Assessment of the Los Alamos National Laboratory Weapons Engineering Tritium Facility Tritium Gas Handling System  

Broader source: Energy.gov (indexed) [DOE]

Site Visit Report Site Visit Report Safety System Oversight Assessment of the Los Alamos National Laboratory Weapons Engineering Tritium Facility Tritium Gas Handling System INTRODUCTION AND OVERVIEW This report documents the results of the Office of Health, Safety and Security's (HSS) review of a safety system oversight (SSO) assessment of the Los Alamos National Laboratory (LANL) Weapons Engineering Tritium Facility (WETF) tritium gas handling system (TGHS). The assessment evaluated the TGHS's ability to perform as required by safety bases and other applicable requirements. The assessment was sponsored by the U.S. Department of Energy (DOE) Los Alamos Site Office (LASO) and was conducted October 25 - November 5, 2010. LASO was the overall lead organization for the evaluation, which included independent

22

Review of the Los Alamos National Laboratory Weapons Engineering Tritium Facility Tritium Gas Containment Vital Safety System, January 2013  

Broader source: Energy.gov (indexed) [DOE]

Independent Oversight Review of the Independent Oversight Review of the Los Alamos National Laboratory Weapons Engineering Tritium Facility Tritium Gas Containment Vital Safety System January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose............................................................................................................................................. 1 2.0 Background...................................................................................................................................... 1 3.0 Scope................................................................................................................................................ 1

23

Review of the Savannah River Site Tritium Facilities Implementation Verification Review Processes  

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

Savannah River Site Tritium Facilities Savannah River Site Tritium Facilities Implementation Verification Review Processes June 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background ........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 1

24

Review of the Savannah River Site Tritium Facilities Implementation Verification Review Processes  

Broader source: Energy.gov (indexed) [DOE]

Savannah River Site Tritium Facilities Savannah River Site Tritium Facilities Implementation Verification Review Processes June 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background ........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 1

25

Tritium Extraction from Pb-17Li by Bubble Columns  

Science Journals Connector (OSTI)

Tritium Processing / Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

Carlo Malara

26

The Operation of the Tokamak Fusion Test Reactor Tritium Facility  

Science Journals Connector (OSTI)

Design, Operation, and Maintenance of Tritium System / Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

Charles A. Gentile; James L. Anderson; Paul H. LaMarche

27

Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility |  

Broader source: Energy.gov (indexed) [DOE]

the Los Alamos Tritium Systems Test Assembly the Los Alamos Tritium Systems Test Assembly Facility Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility The purpose of this document is to report the results of a survey conducted at the Los Alamos Tritium Systems Test Assembly (TSTA Facility). The survey was conducted during the week of 3/20/00. The primary purpose of the survey is to identify facility conditions and issues that need to be addressed to transfer responsibility for the facility from the Office of Science (SC) to the Office of Environmental Management (EM). The second purpose is to provide EM with insight regarding the facility's risks and liabilities, which may influence the management of eventual downstream life-cycle activities. The survey and this report are part of a process for implementing the

28

Performance and improvements of the tritium handling facility at the Los Alamos Scientific Laboratory  

SciTech Connect (OSTI)

A major problem facing todays nuclear energy industry is the release of radioactive waste products to the atmosphere. The DP-East Tritium Handling Facility at the Los Alamos Scientific Laboratory (LASL), activated December 5, 1974 has processed 3.8 x 10/sup 6/ curies of tritium with a total stack release of 704.5 curies as of December 12, 1979. This averages only 11.7 Ci/month which to our knowledge is the lowest stack release any major tritium facility has achieved. The facility includes an 11.5 m/sup 3/ dry box with associated gas purification system (GPS) and an effluent treatment system (FTS). The system performance, problems, and improvements are discussed with special emphasis given to the ETS, the new dry box waste disposal system, and the new automated logic control system, all of which contribute significantly to the low level tritium release at this facility.

Nasise, J.E.

1980-01-01T23:59:59.000Z

29

Determination of a tritium bioassay technique for nuclear facilities  

E-Print Network [OSTI]

. Gaseous tritium is retained only to a small degree after inhalation, with over 905 released by exhaling; however, tritiated (') water (HTO) is almost completely retained. This degree of retention of tritiated water has been shown to occur... for ingestion, inhalation and transfer through the skin. Other comoounds of tritium will be re- tained to a greater or lesser extent dependent on the physiological use of the compound. Under normal condi- tions of fluid intake, the concentration of HTO...

Sensintaffar, Edwin Lee

2012-06-07T23:59:59.000Z

30

REPORT OF SURVEY OF THE LOS ALAMOS TRITIUM SYSTEMS TEST ASSEMBLY FACILITY  

Broader source: Energy.gov (indexed) [DOE]

THE LOS ALAMOS TRITIUM THE LOS ALAMOS TRITIUM SYSTEMS TEST ASSEMBLY FACILITY U.S. Department of Energy Office of Environmental Management & Office of Science Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility Rev. E (Final) October 3, 2000 Contents 1. Introduction 1.1 Purpose 1.2 Facility Description 1.3 Organization Representatives 1.4 Survey Participants 2. Summary, Conclusions & Recommendations 2.1 Comparison With LCAM Requirements 2.2 Transfer Considerations 2.3 Post-Transfer EM Path Forward & Management Risk 2.4 Post-Transfer S&M Reduction via Administrative Contamination Limit Revision 2.5 Stable Metal Tritides Consideration During D&D 3. Survey Results

31

Medical Isotope Production With The Accelerator Production of Tritium (APT) Facility  

SciTech Connect (OSTI)

In order to meet US tritium needs to maintain the nuclear weapons deterrent, the Department of Energy (DOE) is pursuing a dual track program to provide a new tritium source. A record of decision is planned for late in 1998 to select either the Accelerator Production of Tritium (APT) or the Commercial Light Water Reactor (CLWR) as the technology for new tritium production in the next century. To support this decision, an APT Project was undertaken to develop an accelerator design capable of producing 3 kg of tritium per year by 2007 (START I requirements). The Los Alamos National Laboratory (LANL) was selected to lead this effort with Burns and Roe Enterprises, Inc. (BREI) / General Atomics (GA) as the prime contractor for design, construction, and commissioning of the facility. If chosen in the downselect, the facility will be built at the Savannah River Site (SRS) and operated by the SRS Maintenance and Operations (M{ampersand}O) contractor, the Westinghouse Savannah River Company (WSRC), with long-term technology support from LANL. These three organizations (LANL, BREI/GA, and WSRC) are working together under the direction of the APT National Project Office which reports directly to the DOE Office of Accelerator Production which has program authority and responsibility for the APT Project.

Buckner, M.; Cappiello, M. [Westinghouse Savannah River Co., Aiken, SC (United States); Pitcher, E. [Los Alamos National Laboratory, Los Alamos, NM (United States); O`Brien, H. [O`Brien and Associates, Los Alamos, NM (United States)

1998-08-01T23:59:59.000Z

32

Radiological Training for Tritium Facilities DOE-HDBK-1105-2002  

Broader source: Energy.gov (indexed) [DOE]

Superseding Superseding DOE-HDBK-1105-96 December 1996 DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. (PART 1 OF 4) Radiological Training for Tritium Facilities Program Management Guide

33

Construction and Operation of a Tritium Extraction Facility at...  

National Nuclear Security Administration (NNSA)

table are in place and protected (fuel storage pools are doubled-walled stainless steel tanks with leak-detection systems). No effects greater than 5 percent above APT's baseline....

34

Tritium monitor  

DOE Patents [OSTI]

A system is described for continuously monitoring the concentration of tritium in an aqueous stream. The system pumps a sample of the stream to magnesium-filled combustion tube which reduces the sample to extract hydrogen gas. The hydrogen gas is then sent to an isotope separation device where it is separated into two groups of isotopes: a first group of isotopes containing concentrations of deuterium and tritium, and a second group of isotopes having substantially no deuterium and tritium. The first group of isotopes containing concentrations of deuterium and tritium is then passed through a tritium detector that produces an output proportional to the concentration of tritium detected. Preferably, the detection system also includes the necessary automation and data collection equipment and instrumentation for continuously monitoring an aqueous stream. 1 fig.

Chastagner, P.

1994-06-14T23:59:59.000Z

35

Tritium monitor  

DOE Patents [OSTI]

A system for continuously monitoring the concentration of tritium in an aqueous stream. The system pumps a sample of the stream to magnesium-filled combustion tube which reduces the sample to extract hydrogen gas. The hydrogen gas is then sent to an isotope separation device where it is separated into two groups of isotopes: a first group of isotopes containing concentrations of deuterium and tritium, and a second group of isotopes having substantially no deuterium and tritium. The first group of isotopes containing concentrations of deuterium and tritium is then passed through a tritium detector that produces an output proportional to the concentration of tritium detected. Preferably, the detection system also includes the necessary automation and data collection equipment and instrumentation for continuously monitoring an aqueous stream.

Chastagner, Philippe (Augusta, GA)

1994-01-01T23:59:59.000Z

36

Independent Oversight Review of the Savannah River Field Office Tritium Facilities Radiological Controls Activity-Level Implementation, November 2013  

Broader source: Energy.gov (indexed) [DOE]

of the of the Savannah River Field Office Tritium Facilities Radiological Controls Activity-Level Implementation May 2011 November 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................ 1 2.0 Scope................................................................................................................................................... 1 3.0 Background ......................................................................................................................................... 1

37

Design of a deuterium and tritium-ablator shock ignition target for the National Ignition Facility  

SciTech Connect (OSTI)

Shock ignition presents a viable path to ignition and high gain on the National Ignition Facility (NIF). In this paper, we describe the development of the 1D design of 0.5 MJ class, all-deuterium and tritium (fuel and ablator) shock ignition target that should be reasonably robust to Rayleigh-Taylor fluid instabilities, mistiming, and hot electron preheat. The target assumes 'day one' NIF hardware and produces a yield of 31 MJ with reasonable allowances for laser backscatter, absorption efficiency, and polar drive power variation. The energetics of polar drive laser absorption require a beam configuration with half of the NIF quads dedicated to launching the ignitor shock, while the remaining quads drive the target compression. Hydrodynamic scaling of the target suggests that gains of 75 and yields 70 MJ may be possible.

Terry, Matthew R.; Perkins, L. John; Sepke, Scott M. [Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, California 94550 (United States)

2012-11-15T23:59:59.000Z

38

Darlington tritium removal facility and station upgrading plant dynamic process simulation  

SciTech Connect (OSTI)

Ontario Power Generation Nuclear (OPGN) has a 4 x 880 MWe CANDU nuclear station at its Darlington Nuclear Div. located in Bowmanville. The station has been operating a Tritium Removal Facility (TRF) and a D{sub 2}O station Upgrading Plant (SUP) since 1989. Both facilities were designed with a Distributed Control System (DCS) and programmable logic controllers (PLC) for process control. This control system was replaced with a DCS only, in 1998. A dynamic plant simulator was developed for the Darlington TRF (DTRF) and the SUP, as part of the computer control system replacement. The simulator was used to test the new software, required to eliminate the PLCs. The simulator is now used for operator training and testing of process control software changes prior to field installation. Dynamic simulation will be essential for the ITER isotope separation system, where the process is more dynamic than the relatively steady-state DTRF process. This paper describes the development and application of the DTRF and SUP dynamic simulator, its benefits, architecture, and the operational experience with the simulator. (authors)

Busigin, A. [NITEK USA, Inc., 6405 NW 77 PL, Parkland, FL 33067 (United States); Williams, G. I. D.; Wong, T. C. W.; Kulczynski, D.; Reid, A. [Ontario Power Generation Nuclear, Box 4000, Bowmanville, ON L1C 3Z8 (Canada)

2008-07-15T23:59:59.000Z

39

Evaluation of replacement tritium facility (RTF) compliance with DOE safety goals using probabilistic consequence assessment methodology. Revision 1  

SciTech Connect (OSTI)

The Savannah River Site (SRS), operated by the Westinghouse Savannah River Company (WSRC) for the US Department of Energy (DOE), is a major center for the processing of nuclear materials for national defense, deep-space exploration, and medical treatment applications in the United States. As an integral part of the DOE`s effort to modernize facilities, implement improved handling and processing technology, and reduce operational risk to the general public and onsite workers, transition of tritium processing at SRS from the Consolidated Tritium Facility to the Replacement Tritium Facility (RTF) began in 1993. To ensure that operation of new DOE facilities such as RTF present minimum involuntary and voluntary risks to the neighboring public and workers, indices of risk have been established to serve as target levels or safety goals of performance for assessing nuclear safety. These goals are discussed from a historical perspective in the initial part of this paper. Secondly, methodologies to quantify risk indices are briefly described. Lastly, accident, abnormal event, and normal operation source terms from RTF are evaluated for consequence assessment purposes relative to the safety targets.

O`Kula, K.R.; East, J.M.; Moore, M.L.

1993-12-31T23:59:59.000Z

40

Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years.

Greager, E.M.

1997-12-11T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Copper activation deuterium-tritium neutron yield measurements at the National Ignition Facility  

E-Print Network [OSTI]

, New Mexico 87131, USA 2 Sandia National Laboratories, Albuquerque, New Mexico 87185, USA 3 Lawrence Livermore National Laboratories, Livermore, California 94550, USA 4 Plasma Science and Fusion Center, MIT(+ ) and 65 Cu(n,2n) 64 Cu(+ ), has been fielded at the National Ignition Facility (NIF). The induced copper

42

TFTR tritium operations lessons learned  

SciTech Connect (OSTI)

The Tokamak Fusion Test Reactor which is the progenitor for full D-T operating tokamaks has successfully processed > 81 grams of tritium in a safe and efficient fashion. Many of the fundamental operational techniques associated with the safe movement of tritium through the TFTR facility were developed over the course of many years of DOE tritium facilities (LANL, LLNL, SRS, Mound). In the mid 1980`s The Tritium Systems Test Assembly (TSTA) at LANL began reporting operational techniques for the safe handling of tritium, and became a major conduit for the transfer of safe tritium handling technology from DOE weapons laboratories to non-weapon facilities. TFTR has built on many of the TSTA operational techniques and has had the opportunity of performing and enhancing these techniques at America`s first operational D-T fusion reactor. This paper will discuss negative pressure employing `elephant trunks` in the control and mitigation of tritium contamination at the TFTR facility, and the interaction between contaminated line operations and {Delta} pressure control. In addition the strategy employed in managing the movement of tritium through TFTR while maintaining an active tritium inventory of < 50,000 Ci will be discussed. 5 refs.

Gentile, C.A.; Raftopoulos, S.; LaMarche, P. [Princeton Plasma Physics Lab., NJ (United States)] [and others

1996-12-31T23:59:59.000Z

43

Subwog 12-D tritium technology meeting  

SciTech Connect (OSTI)

The first Subwog 12-D Tritium Technology Meeting was held at the Westinghouse Savannah River Site during the week of May 21, 1990. Subwog 12-D was created as a subwog of JOWOG 12 to address the need to understand tritium applications throughout the entire weapons complex. This includes weapons related concerns, but is primarily intended to cover tritium production and handling, environmental, safety and health issues, compatibility with materials in general; and facility design, commissioning and decommissioning activities. Tritium technology issues discussed included the physical and chemical properties, kinetics, storage, reservoir loading techniques, isotope exchange, radiolysis/aging, process and handling technology, compatibility, purification and filtering, analysis, monitoring methods, function testing, packaging and shipping, environmental and operational safety, facility design and safety, glovebox atmosphere clean-up systems, glovebox/facility decommissioning, tritium production target materials, and tritium recovery. This document provides a collection of most of the unclassified extended abstracts and abstracts presented at Subwog 12-D.

Parker, M.J.; Addis, R.P.

1991-01-01T23:59:59.000Z

44

Subwog 12-D tritium technology meeting. Abstracts  

SciTech Connect (OSTI)

The first Subwog 12-D Tritium Technology Meeting was held at the Westinghouse Savannah River Site during the week of May 21, 1990. Subwog 12-D was created as a subwog of JOWOG 12 to address the need to understand tritium applications throughout the entire weapons complex. This includes weapons related concerns, but is primarily intended to cover tritium production and handling, environmental, safety and health issues, compatibility with materials in general; and facility design, commissioning and decommissioning activities. Tritium technology issues discussed included the physical and chemical properties, kinetics, storage, reservoir loading techniques, isotope exchange, radiolysis/aging, process and handling technology, compatibility, purification and filtering, analysis, monitoring methods, function testing, packaging and shipping, environmental and operational safety, facility design and safety, glovebox atmosphere clean-up systems, glovebox/facility decommissioning, tritium production target materials, and tritium recovery. This document provides a collection of most of the unclassified extended abstracts and abstracts presented at Subwog 12-D.

Parker, M.J.; Addis, R.P.

1991-12-31T23:59:59.000Z

45

Independent Oversight Review, Savannah River Field Office Tritium  

Broader source: Energy.gov (indexed) [DOE]

Field Office Tritium Field Office Tritium Facilities - November 2013 Independent Oversight Review, Savannah River Field Office Tritium Facilities - November 2013 November 13, 2013 Review of Savannah River Field Office Tritium Facilities Radiological Controls Activity-Level Implementation This report documents the results of an independent oversight review of the radiological protection program at the Savannah River Site (SRS) tritium facilities implemented at the activity-level by Savannah River Nuclear Solutions, LLC and its subcontractors. The review was performed by the Office of Health, Safety and Security's Office of Safety and Emergency Management Evaluations within the broader context of an ongoing program of targeted assessments of radiological control programs, with an emphasis on

46

tritium1120  

Broader source: Energy.gov (indexed) [DOE]

SUMMARY REPORT ON SUMMARY REPORT ON INSPECTION OF ISSUES ASSOCIATED WITH THE DEPARTMENT OF ENERGY' S TRITIUM SOURCE SELECTION PROCESS NOVEMBER 1998 DOE/IG-0431 U.S. DEPARTMENT OF ENERGY OFFICE OF INSPECTOR GENERAL OFFICE OF INSPECTIONS INSPECTION REPORT November 23, 1999 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman /s/ Inspector General SUBJECT: INFORMATION: Summary Report on "Inspection of Issues Associated With the Department of Energy' s Tritium Source Selection Process" BACKGROUND The Office of Inspector General received a letter dated August 31, 1998 from Senator Strom Thurmond concerning the selection of the tritium production source. The let-

47

Atmospheric tritium  

SciTech Connect (OSTI)

Research progress for the year 1979 to 1980 are reported. Concentrations of tritiated water vapor, tritium gas and tritiated hydrocarbons in the atmosphere at selected sampling points are presented. (ACR)

Oestlund, H.G.; Mason, A.S.

1980-01-01T23:59:59.000Z

48

Plutonium-Uranium Extraction (PUREX) facility preclosure work plan  

SciTech Connect (OSTI)

The dangerous waste permit identification number (WA7890008967)was issued by the U.S. Environmental Protection Agency and the Washington State Department of Ecology. This identification number encompasses a number of treatment, storage, and/or disposal units within the Hanford Facility. One of these treatment, storage, and/or disposal units is the PUREX Facility,currently undergoing a phased closure. The PUREX Facility Preclosure Work Plan submittal differs from closure plans previously submitted by the U.S. Department of Energy, Richland Operations Office to the Washington State Department of Ecology,in that the closure process occurs in three distinct phases as part of the decommissioning process (i.e., transition,surveillance and maintenance, and disposition). Final closure will occur during the disposition phase. This phased decommissioning process is implemented because development of a complete closure plan during the transition phase is impractical and future land use determinations have not been identified. The objective of the transition phase is to place the PUREX Facility in a safe configuration with respect to human health and the environment. Following the transition phase activities, the PUREX Facility will begin the surveillance and maintenance phase of 10 or more years until disposition phase activities commence. The closure plan for the PUREX facility will be prepared during the disposition phase. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels. The PUREX Storage Tunnels are an operating storage unit(DOE/RL-94-24).

Bhatia, R.K., Westinghouse Hanford

1996-07-09T23:59:59.000Z

49

Use of system code to estimate equilibrium tritium inventory in fusion DT machines, such as ARIES-AT and components testing facilities  

SciTech Connect (OSTI)

ITER is under construction and will begin operation in 2020. This is the first 500 MWfusion class DT device, and since it is not going to breed tritium, it will consume most of the limited supply of tritium resources in the world. Yet, in parallel, DT fusion nuclear component testing machines will be needed to provide technical data for the design of DEMO. It becomes necessary to estimate the tritium burn-up fraction and corresponding initial tritium inventory and the doubling time of these machines for the planning of future supply and utilization of tritium. With the use of a system code, tritium burn-up fraction and initial tritium inventory for steady state DT machines can be estimated. Estimated tritium burn-up fractions of FNSF-AT, CFETR-R and ARIES-AT are in the range of 1–2.8%. Corresponding total equilibrium tritium inventories of the plasma flow and tritium processing system, and with the DCLL blanket option are 7.6 kg, 6.1 kg, and 5.2 kg for ARIES-AT, CFETR-R and FNSF-AT, respectively.

C.P.C. Wong; B. Merrill

2014-10-01T23:59:59.000Z

50

Behavior of tritium in the Purex process  

SciTech Connect (OSTI)

The tri-n-butyl phosphate(TBP) extraction behavior of tritium was studied to support the evaluation of tritium confinement in the Purex process. The tritium distribution ratio in the system of U - 30% TBP/n-dodecane(nDD) - HNO[sub 3] [minus]H[sub 2]O was measured in batch-wise experiments. The tritium decontamination factor in a tritium scrubbing step was measured in chemical flow sheet experiments using a 6 stage mixer-settler having an internal recycle system of aqueous solution in each stage. Tritium was mainly extracted in the forms of water and nitric acid in the system. Less than 1% of the amount of tritium in the organic phase was fixed in the degradation products of the solvent. A tritium decontamination factor of about 500 in the tritium scrubbing step was obtained under the conditions of about 85 g-U/dm[sup 3] of uranium concentration in the irradiated solvent(30% TBP/nDD), 3 M nitric acid in the tritium scrubbing solution and an organic: aqueous phase ratio of 25. 17 refs., 14 figs., 1 tab.

Uchiyama, Gunzo; Fujine, Sachio; Maeda, Mitsuru; Sugikawa, Susumu; Tsujino, Takeshi (Japan Atomic Eenrgy Inst., Ibaraki (Japan))

1995-01-01T23:59:59.000Z

51

Estimation of tritium and helium inventory in the tritium handling system in Korea  

SciTech Connect (OSTI)

In Korea, the Wolsong Tritium Removal Facility (WTRF) is under construction to reduce the amount of tritium present in the moderator and coolant of the CANDU type Wolsong nuclear power plants. Recently, a study on the tritium handling system for recovery of the tritium collected from the WTRF was started. Some tritium would enter the steel of the container walls and subsequently decay to helium. This helium can deteriorate the mechanical properties of the material of the tritium handling system. To evaluate the tritium and helium inventory in the stainless steel wall of this system, the time-dependent diffusion equation was developed, solved and the results are presented in this paper. These results were compared to previous work that evaluated the tritium inventory in the stainless steel wall of 50-L tritium containers. Tritium and helium concentration profiles and the corresponding inventories were evaluated with respect to the various parameters such as exposure time, temperature, and partial pressure. After 24 years, the helium inventory in the wall of the tritium handling system exceeds the tritium inventory. (authors)

Yook, D.; Lee, S.; Lee, K. [Dept. of Nuclear Eng., KAIST, 373-1, Kusong-dong, Yusong-gu, Daejon 305-701 (Korea, Republic of); Song, K. M.; Shon, S. H. [KEPRI, 103-16 Munji-Dong, Yuseong-Gu, Daejeon, 305-380 (Korea, Republic of)

2008-07-15T23:59:59.000Z

52

Universal tritium transmitter  

SciTech Connect (OSTI)

At the Savannah River Site and throughout the National Nuclear Security Agency (NNSA) tritium is measured using Ion or Kanne Chambers. Tritium flowing through an Ion Chamber emits beta particles generating current flow proportional to tritium radioactivity. Currents in the 1 x 10{sup -15} A to 1 x 10{sup -6} A are measured. The distance between the Ion Chamber and the electrometer in NNSA facilities can be over 100 feet. Currents greater than a few micro-amperes can be measured with a simple modification. Typical operating voltages of 500 to 1000 Volts and piping designs require that the Ion Chamber be connected to earth ground. This grounding combined with long cable lengths and low currents requires a very specialized preamplifier circuit. In addition, the electrometer must be able to supply 'fail safe' alarm signals which are used to alert personnel of a tritium leak, trigger divert systems preventing tritium releases to the environment and monitor stack emissions as required by the United States federal Government and state governments. Ideally the electrometer would be 'self monitoring'. Self monitoring would reduce the need for constant checks by maintenance personnel. For example at some DOE facilities monthly calibration and alarm checks must be performed to ensure operation. NNSA presently uses commercially available electrometers designed specifically for this critical application. The problems with these commercial units include: ground loops, high background currents, inflexibility and susceptibility to Electromagnetic Interference (EMI) which includes RF and Magnetic fields. Existing commercial electrometers lack the flexibility to accommodate different Ion Chamber designs required by the gas pressure, type of gas and range. Ideally the electrometer could be programmed for any expected gas, range and high voltage output. Commercially available units do not have 'fail safe' self monitoring capability. Electronics used to measure extremely low current must have sufficient time to thermally equilibrate. Amplifiers, transistors, resistors all need time to stabilize before the electrometer circuit will measure accurately in the 10{sup -15} and 10{sup -14} ampere range. Existing electrometers give the user no indication when the unit has stabilized and is acceptable for low level measurements. Savannah River National Laboratory (SRNL) funded through the NNSA Plant Directed Research and Development (PDRD) program, has developed a truly Universal Tritium Transmitter (UTT) capable of solving many known problems with existing commercial electrometers. This UTT pushes the state-of-the-art in electrometer design and incorporates solutions to deficiencies found in commercial electrometers. (authors)

Cordaro, J. V.; Wood, M. [Westinghouse Savannah River Company, Savannah River National Laboratory, Aiken, SC 29808 (United States)

2008-07-15T23:59:59.000Z

53

1997 evaluation of tritium removal and mitigation technologies for Hanford Site wastewaters  

SciTech Connect (OSTI)

This report contains results of a biennial assessment of tritium separation technology and tritium nitration techniques for control of tritium bearing wastewaters at the Hanford Site. Tritium in wastewaters at Hanford have resulted from plutonium production, fuel reprocessing, and waste handling operations since 1944. this assessment was conducted in response to the Hanford Federal Facility Agreement and Consent Order.

Jeppson, D.W.; Biyani, R.K.; Duncan, J.B.; Flyckt, D.L.; Mohondro, P.C.; Sinton, G.L.

1997-07-24T23:59:59.000Z

54

Fermilab | Tritium at Fermilab | Tritium released into the air...  

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

Tritium released into the air and disposed of as solid waste Fermilab produces tritium as an expected byproduct of accelerator operations. The lab actively manages tritium, using...

55

Record of Decision, Tritium Supply and Recycling Programmatic Environmental Impact Statement  

Broader source: Energy.gov (indexed) [DOE]

63877 63877 Tuesday December 12, 1995 Part VII Department of Energy Record of Decision; Tritium Supply and Recycling Programmatic Environmental Impact Statement; Notice 63878 Federal Register / Vol. 60, No. 238 / Tuesday, December 12, 1995 / Notices DEPARTMENT OF ENERGY Record of Decision: Tritium Supply and Recycling Programmatic Environmental Impact Statement AGENCY: Department of Energy. ACTION: Record of Decision: Selection of Tritium Supply Technology and Siting of Tritium Supply and Recycling Facilities. SUMMARY: The Department of Energy (DOE) is issuing this Record of Decision regarding DOE's proposal for Tritium Supply and Recycling Facilities. The Department is making three simultaneous decisions. First, the Department will pursue a dual track on the two most promising tritium supply

56

Tritium waste disposal technology in the US  

SciTech Connect (OSTI)

Tritium waste disposal methods in the US range from disposal of low specific activity waste along with other low-level waste in shallow land burial facilities, to disposal of kilocurie amounts in specially designed triple containers in 65' deep augered holes located in an aird region of the US. Total estimated curies disposed of are 500,000 in commercial burial sites and 10 million curies in defense related sites. At three disposal sites in humid areas, tritium has migrated into the ground water, and at one arid site tritium vapor has been detected emerging from the soil above the disposal area. Leaching tests on tritium containing waste show that tritium in the form of HTO leaches readily from most waste forms, but that leaching rates of tritiated water into polymer impregnated concrete are reduced by as much as a factor of ten. Tests on improved tritium containment are ongoing. Disposal costs for tritium waste are 7 to 10 dollars per cubic foot for shallow land burial of low specific activity tritium waste, and 10 to 20 dollars per cubic foot for disposal of high specific activity waste. The cost of packaging the high specific activity waste is 150 to 300 dollars per cubic foot. 18 references.

Albenesius, E.L.; Towler, O.A.

1983-01-01T23:59:59.000Z

57

Development of tritium technology for the United States magnetic fusion energy program  

SciTech Connect (OSTI)

Tritium technology development for the DOE fusion program is taking place principally at three laboratories, Mound Facility, Argonne National Laboratory and the Los Alamos Scientific Laboratory. This paper will review the major aspects of each of the three programs and look at aspects of the tritium technology being developed at other laboratories within the United States. Facilities and experiments to be discussed include the Tritium Effluent Control Laboratory and the Tritium Storage and Delivery System for the Tokamak Fusion Test Reactor at Mound Facility; the Lithium Processing Test Loop and the solid breeder blanket studies at Argonne; and the Tritium Systems Test Assembly at Los Alamos.

Anderson, J.L.; Wilkes, W.R.

1980-01-01T23:59:59.000Z

58

Oxidative Tritium Decontamination System  

SciTech Connect (OSTI)

The Princeton Plasma Physics Laboratory, Tritium Systems Group has developed and fabricated an Oxidative Tritium Decontamination System (OTDS), which is designed to reduce tritium surface contamination on various components and items. The system is configured to introduce gaseous ozone into a reaction chamber containing tritiated items that require a reduction in tritium surface contamination. Tritium surface contamination (on components and items in the reaction chamber) is removed by chemically reacting elemental tritium to tritium oxide via oxidation, while purging the reaction chamber effluent to a gas holding tank or negative pressure HVAC system. Implementing specific concentrations of ozone along with catalytic parameters, the system is able to significantly reduce surface tritium contamination on an assortment of expendable and non-expendable items. This paper will present the results of various experimentation involving employment of this system.

Charles A. Gentile; John J. Parker; Gregory L. Guttadora; Lloyd P. Ciebiera

2002-02-11T23:59:59.000Z

59

Tritium in amorphous silicon  

SciTech Connect (OSTI)

Preliminary results on infrared and luminescence measurements of tritium incorporated amorphous silicon are reported. Tritium is an unstable isotope that readily substitutes hydrogen in the amorphous silicon network. Due to its greater mass, bonded tritium is found to introduce new stretching modes in the infrared spectrum. Inelastic collisions between the beta particles, produced as a result of tritium decay, and the amorphous silicon network, results in the generation of excess electron-hole pairs. Radiative recombination of these carriers is observed.

Sidhu, L.S.; Kosteski, T.; O`Leary, S.K.; Gaspari, F.; Zukotynski, S. [Univ. of Toronto, Ontario (Canada). Dept. of Electrical and Computer Engineering; Kherani, N.P.; Shmadya, W. [Ontario Hydro Technologies, Toronto, Ontario (Canada)

1996-12-31T23:59:59.000Z

60

Tritium Activities in Russia  

Science Journals Connector (OSTI)

Plenary / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

Arkadiy A.Yukhimchuk

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Continuous aqueous tritium monitor  

DOE Patents [OSTI]

An apparatus for a selective on-line determination of aqueous tritium concentration is disclosed. A moist air stream of the liquid solution being analyzed is passed through a permeation dryer where the tritium and moisture are selectively removed to a purge air stream. The purge air stream is then analyzed for tritium concentration, humidity, and temperature, which allows computation of liquid tritium concentration. 2 figs.

McManus, G.J.; Weesner, F.J.

1987-10-19T23:59:59.000Z

62

Extracting core shape from x-ray images at the National Ignition Facility  

SciTech Connect (OSTI)

Measuring the shape of implosions is critical to inertial confinement fusion experiments at the National Ignition Facility. We have developed techniques that have proven successful for extracting shape information from images of x-ray self-emission recorded by a variety of diagnostic instruments for both DT-filled targets and low-yield surrogates. These key results help determine optimal laser and target parameters leading to ignition. We have compensated for instrumental response and have employed a variety of image processing methods to remove artifacts from the images while retaining salient features. The implosion shape has been characterized by decomposing intensity contours into Fourier and Legendre modes for different lines of sight. We also describe procedures we have developed for estimating uncertainties in these measurements.

Glenn, S. M.; Benedetti, L. R.; Bradley, D. K.; Hammel, B. A.; Izumi, N.; Khan, S. F.; Ma, T.; Milovich, J. L.; Pak, A. E.; Smalyuk, V. A.; Tommasini, R.; Town, R. P. [Lawrence Livermore National Laboratory, Livermore, California 94555 (United States); Kyrala, G. A. [Los Alamos National Laboratory, Los Alamos, New Mexico 87544 (United States)

2012-10-15T23:59:59.000Z

63

Type A Accident Investigation Board report on the January 17, 1996, electrical accident with injury in Technical Area 21 Tritium Science and Fabrication Facility Los Alamos National Laboratory. Final report  

SciTech Connect (OSTI)

An electrical accident was investigated in which a crafts person received serious injuries as a result of coming into contact with a 13.2 kilovolt (kV) electrical cable in the basement of Building 209 in Technical Area 21 (TA-21-209) in the Tritium Science and Fabrication Facility (TSFF) at Los Alamos National Laboratory (LANL). In conducting its investigation, the Accident Investigation Board used various analytical techniques, including events and causal factor analysis, barrier analysis, change analysis, fault tree analysis, materials analysis, and root cause analysis. The board inspected the accident site, reviewed events surrounding the accident, conducted extensive interviews and document reviews, and performed causation analyses to determine the factors that contributed to the accident, including any management system deficiencies. Relevant management systems and factors that could have contributed to the accident were evaluated in accordance with the guiding principles of safety management identified by the Secretary of Energy in an October 1994 letter to the Defense Nuclear Facilities Safety Board and subsequently to Congress.

NONE

1996-04-01T23:59:59.000Z

64

Fermilab | Tritium at Fermilab | Frequently asked questions about tritium  

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

Frequently asked questions about tritium Frequently asked questions about tritium Answers to Frequently Asked Questions about Tritium at Fermilab. If you have any questions about tritium at Fermilab, please call the Office of Communication at 630-840-3351, or submit a question online. Q: What is tritium? A: Tritium is a form of hydrogen. It's a weakly radioactive isotope with a half-life of 12.3 years. When tritium decays into ordinary helium, it emits low-energy particles called beta particles. Although tritium can be found as a gas, its most common form is water. The Earth's atmosphere contains low levels of tritium produced naturally when cosmic rays strike air particles. At Fermilab, small amounts of tritium are produced as a byproduct of accelerator operations. Q: Does the tritium at Fermilab constitute a health risk to employees or

65

Tritium transport in the NuMI decay pipe region - modeling and comparison with experimental data  

SciTech Connect (OSTI)

The NuMI (Neutrinos at Main Injector) beam facility at Fermilab is designed to produce an intense beam of muon neutrinos to be sent to the MINOS underground experiment in Soudan, Minnesota. Neutrinos are created by the decay of heavier particles. In the case of NuMI, the decaying particles are created by interaction of high-energy protons in a target, creating mostly positive pions. These particles can also interact with their environment, resulting in production of a variety of short-lived radionuclides and tritium. In the NuMI beam, neutrinos are produced by 120 GeV protons from the Fermilab Main Injector accelerator which are injected into the NuMI beam line using single turn extraction. The beam line has been designed for 400 kW beam power, roughly a factor of 2 above the initial (2005-06) running conditions. Extracted protons are bent downwards at a 57mr angle towards the Soudan Laboratory. The meson production target is a 94 cm segmented graphite rod, cooled by water in stainless tubes on the top and bottom of the target. The target is followed by two magnetic horns which are pulsed to 200 kA in synchronization with the passage of the beam, producing focusing of the secondary hadron beam and its daughter neutrinos. Downstream of the second horn the meson beam is transported for 675 m in an evacuated 2 m diameter beam (''decay'') pipe. Subsequently, the residual mesons and protons are absorbed in a water cooled aluminum/steel absorber immediately downstream of the decay pipe. Some 200 m of rock further downstream ranges out all of the residual muons. During beam operations, after installation of the chiller condensate system in December 2005, the concentration of tritiated water in the MINOS sump flow of 177 gpm was around 12 pCi/ml, for a total of 0.010 pCi/day. A simple model of tritium transport and deposition via humidity has been constructed to aid in understanding how tritium reaches the sump water. The model deals with tritium transported as HTO, water in which one hydrogen atom has been replaced with tritium. Based on concepts supported by the modeling, a dehumidification system was installed during May 2006 that reduced the tritium level in the sump by a factor of two. This note is primarily concerned with tritium that was produced in the NuMI target pile, carried by air flow into the target hall and down the decay pipe passageway (where most of it was deposited). The air is exhausted through the existing air vent shaft EAV2 (Figure 1).

Hylen, J.; Plunkett, R.; /Fermilab

2007-03-01T23:59:59.000Z

66

Tritium Attenuation by Distillation  

SciTech Connect (OSTI)

The objective of this study was to determine how a 100 Area distillation system could be used to reduce to a satisfactory low value the tritium content of the dilute moderator produced in the 100 Area stills, and whether such a tritium attenuator would have sufficient capacity to process all this material before it is sent to the 400 Area for reprocessing.

Wittman, N.E.

2001-07-31T23:59:59.000Z

67

Facilities  

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

Facilities Facilities Facilities LANL's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 Some LANL facilities are available to researchers at other laboratories, universities, and industry. Unique facilities foster experimental science, support LANL's security mission DARHT accelerator DARHT's electron accelerators use large, circular aluminum structures to create magnetic fields that focus and steer a stream of electrons down the length of the accelerator. Tremendous electrical energy is added along the way. When the stream of high-speed electrons exits the accelerator it is

68

Tritium in the Savannah River Site environment  

SciTech Connect (OSTI)

Tritium is released to the environment from many of the operations at the Savannah River Site. The releases from each facility to the atmosphere and to the soil and streams, both from normal operations and inadvertent releases, over the period of operation from the early 1950s through 1988 are presented. The fate of the tritium released is evaluated through environmental monitoring, special studies, and modeling. It is concluded that approximately 91% of the tritium remaining after decay is now in the oceans. A dose and risk assessment to the population around the site is presented. It is concluded that about 0.6 fatal cancers may be associated with the tritium released during all the years of operation to the population of about 625,000. This same population (based on the overall US cancer statistics) is expected to experience about 105,000 cancer fatalities from all types of cancer. Therefore, it is considered unlikely that a relationship between any of the cancer deaths occurring in this population and releases of tritium from the SRS will be found.

Murphy, C.E. Jr.; Bauer, L.R.; Hayes, D.W.; Marter, W.L.; Zeigler, C.C.; Stephenson, D.E.; Hoel, D.D.; Hamby, D.M.

1991-05-01T23:59:59.000Z

69

PLUTONIUM-URANIUM EXTRACTION (PUREX) FACILITY ALARACT DEMONSTRATION FOR FILTER HOUSING  

SciTech Connect (OSTI)

This document presents an As Low As Reasonably Achievable Control Technology (ALARACT) demonstration for evaluating corrosion on the I-beam supporting filter housing No.9 for the 291-A-l emission unit of the Plutonium-Uranium Extraction (PUREX) Facility, located in the 200 East Area of the Hanford Site. The PUREX facility is currently in surveillance and maintenance mode. During a State of Washington, Department of Health (WDOH) 291-A-l emission unit inspection, a small amount of corrosion was observed at the base of a high-efficiency particulate air (HEPA) filter housing. A series of internal and external inspections identified the source of the corrosion material as oxidation of a small section of one of the carbon steel I-beams that provides support to the stainless steel filter housing. The inspections confirmed the corrosion is isolated to one I-beam support location and does not represent any compromise of the structural support or filter housing integrity. Further testing and inspections of the support beam corrosion and its cause were conducted but did not determine the cause. No definitive evidence was found to support any degradation of the housing. Although no degradation of the housing was found, a conservative approach will be implemented. The following actions will be taken: (1) The current operating filter housing No.9 will be removed from service. (2) The only remaining available filter housings (No.1, No.2, and No.3) will be placed in service. These filter housings have new HEPA filters fitted with stainless steel frames and faceguards which were installed in the spring of 2007. (3) Filter housings No.5 and No.10 will be put on standby as backups. To document the assessment of the unit, a draft ALARACT filter housing demonstration for the PUREX filter housing was prepared, and informally provided to WDOH on August 7, 2008. A follow up WDOH response to the draft ALARACT filter housing demonstration for the PUREX filter housing questioned whether deteriorated galvanized filter faceguards discovered during an internal filter housing inspection met American Society of Mechanical Engineers (ASME) AG-l or Military Specification (MIL) 51068 standards. The filter system was designed and installed prior to the issuance of AG-l, February 1986; however, MIL 51068 did require galvanized faceguards. The faceguards are not necessary for filtration or structural purposes; it is concluded that the system is in compliance with the intent of the applicable standard. Appendix B provides supporting information to address this issue.

LEBARON GJ

2008-11-25T23:59:59.000Z

70

Tritium catalyzed deuterium tokamaks  

SciTech Connect (OSTI)

A preliminary assessment of the promise of the Tritium Catalyzed Deuterium (TCD) tokamak power reactors relative to that of deuterium-tritium (D-T) and catalyzed deuterium (Cat-D) tokamaks is undertaken. The TCD mode of operation is arrived at by converting the /sup 3/He from the D(D,n)/sup 3/He reaction into tritium, by neutron capture in the blanket; the tritium thus produced is fed into the plasma. There are three main parts to the assessment: blanket study, reactor design and economic analysis and an assessment of the prospects for improvements in the performance of TCD reactors (and in the promise of the TCD mode of operation, in general).

Greenspan, E.; Miley, G.H.; Jung, J.; Gilligan, J.

1984-04-01T23:59:59.000Z

71

Tritium waste package  

DOE Patents [OSTI]

A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

1995-01-01T23:59:59.000Z

72

Tritium waste package  

DOE Patents [OSTI]

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1995-11-07T23:59:59.000Z

73

Fermilab | Tritium at Fermilab | Home  

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

Feature photo Feature photo Tritium at Fermilab Tritium is a weakly radioactive form of hydrogen. In nature, it's formed when cosmic particles hit Earth's atmosphere. Here at Fermilab, tritium is an expected byproduct of the operation of our particle accelerators. This website provides information on the monitoring and management of tritium at Fermilab. Small but detectable levels of tritium –well below regulatory limits--are found in some ponds on the Fermilab site, in Indian Creek as it leaves the laboratory, and in some of Fermilab's sanitary sewer water. No tritium has been detected in wells on the Fermilab site. We are committed to go beyond merely satisfying regulatory limits, and work to keep the levels of tritium as low as possible. Though the levels of tritium discharged by Fermilab pose no health risk to

74

MODELING ATMOSPHERIC RELEASES OF TRITIUM FROM NUCLEAR INSTALLATIONS  

SciTech Connect (OSTI)

Tritium source term analysis and the subsequent dispersion and consequence analyses supporting the safety documentation of Department of Energy nuclear facilities are especially sensitive to the applied software analysis methodology, input data and user assumptions. Three sequential areas in tritium accident analysis are examined in this study to illustrate where the analyst should exercise caution. Included are: (1) the development of a tritium oxide source term; (2) use of a full tritium dispersion model based on site-specific information to determine an appropriate deposition scaling factor for use in more simplified, broader modeling, and (3) derivation of a special tritium compound (STC) dose conversion factor for consequence analysis, consistent with the nature of the originating source material. It is recommended that unless supporting, defensible evidence is available to the contrary, the tritium release analyses should assume tritium oxide as the species released (or chemically transformed under accident's environment). Important exceptions include STC situations and laboratory-scale releases of hydrogen gas. In the modeling of the environmental transport, a full phenomenology model suggests that a deposition velocity of 0.5 cm/s is an appropriate value for environmental features of the Savannah River Site. This value is bounding for certain situations but non-conservative compared to the full model in others. Care should be exercised in choosing other factors such as the exposure time and the resuspension factor.

Okula, K

2007-01-17T23:59:59.000Z

75

Drum bubbler tritium processing system  

DOE Patents [OSTI]

A method of separating tritium oxide from a gas stream containing tritium oxide. The gas stream containing tritium oxide is fed into a container of water having a head space above the water. Bubbling the gas stream containing tritium oxide through the container of water and removing gas from the container head space above the water. Thereafter, the gas from the head space is dried to remove water vapor from the gas, and the water vapor is recycled to the container of water.

Rule, Keith (Hopewell, NJ); Gettelfinger, Geoff (Lexington, MA); Kivler, Paul (Hamilton Square, NJ)

1999-01-01T23:59:59.000Z

76

Monitoring of tritium  

DOE Patents [OSTI]

The fluid from a breeder nuclear reactor, which may be the sodium cooling fluid or the helium reactor-cover-gas, or the helium coolant of a gas-cooled reactor passes over the portion of the enclosure of a gaseous discharge device which is permeable to hydrogen and its isotopes. The tritium diffused into the discharge device is radioactive producing beta rays which ionize the gas (argon) in the discharge device. The tritium is monitored by measuring the ionization current produced when the sodium phase and the gas phase of the hydrogen isotopes within the enclosure are in equilibrium.

Corbett, James A. (Turtle Creek, PA); Meacham, Sterling A. (Greensburg, PA)

1981-01-01T23:59:59.000Z

77

RESULTS OF THE EXTRACTION-SCRUB-STRIP TESTING USING AN IMPROVED SOLVENT FORMULATION AND SALT WASTE PROCESSING FACILITY SIMULATED WASTE  

SciTech Connect (OSTI)

The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent - also known as the next generation solvent (NGS) - for deployment at the Savannah River Site to remove cesium from High Level Waste. The technical effort is a collaborative effort between Oak Ridge National Laboratory (ORNL) and Savannah River National Laboratory (SRNL). As part of the program, the Savannah River National Laboratory (SRNL) has performed a number of Extraction-Scrub-Strip (ESS) tests. These batch contact tests serve as first indicators of the cesium mass transfer solvent performance with actual or simulated waste. The test detailed in this report used simulated Tank 49H material, with the addition of extra potassium. The potassium was added at 1677 mg/L, the maximum projected (i.e., a worst case feed scenario) value for the Salt Waste Processing Facility (SWPF). The results of the test gave favorable results given that the potassium concentration was elevated (1677 mg/L compared to the current 513 mg/L). The cesium distribution value, DCs, for extraction was 57.1. As a comparison, a typical D{sub Cs} in an ESS test, using the baseline solvent formulation and the typical waste feed, is {approx}15. The Modular Caustic Side Solvent Extraction Unit (MCU) uses the Caustic-Side Solvent Extraction (CSSX) process to remove cesium (Cs) from alkaline waste. This process involves the use of an organic extractant, BoBCalixC6, in an organic matrix to selectively remove cesium from the caustic waste. The organic solvent mixture flows counter-current to the caustic aqueous waste stream within centrifugal contactors. After extracting the cesium, the loaded solvent is stripped of cesium by contact with dilute nitric acid and the cesium concentrate is transferred to the Defense Waste Processing Facility (DWPF), while the organic solvent is cleaned and recycled for further use. The Salt Waste Processing Facility (SWPF), under construction, will use the same process chemistry. The Office of Waste Processing (EM-31) expressed an interest in investigating the further optimization of the organic solvent by replacing the BoBCalixC6 extractant with a more efficient extractant. This replacement should yield dividends in improving cesium removal from the caustic waste stream, and in the rate at which the caustic waste can be processed. To that end, EM-31 provided funding for both the Savannah River National Laboratory (SRNL) and the Oak Ridge National Laboratory (ORNL). SRNL wrote a Task Technical Quality and Assurance Plan for this work. As part of the envisioned testing regime, it was decided to perform an ESS test using a simulated waste that simulated a typical envisioned SWPF feed, but with added potassium to make the waste more challenging. Potassium interferes in the cesium removal, and its concentration is limited in the feed to <1950 mg/L. The feed to MCU has typically contained <500 mg/L of potassium.

Peters, T.; Washington, A.; Fink, S.

2012-01-09T23:59:59.000Z

78

Fermilab | Tritium at Fermilab | Tritium in Surface Water  

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

Surface Water Surface Water Fermilab map Fermilab has conducted an environmental monitoring program on site for roughly 40 years. In November of 2005, for the first time, we detected low levels of tritium in Indian Creek, one of three creeks that travel through the Fermilab site. Low but measurable levels of tritium continue to be detected in Indian Creek. All tritium levels found on site are well below any federal health and environmental standards. The Department of Energy standard for surface water is 1,900 picocuries per milliliter, and our readings to date have remained in the single digits. The levels of tritium detected in Indian Creek are extremely low compared to what is safe for a lifetime of continuous exposure to tritium in surface water. The low levels of tritium in Indian Creek stem from particle beams produced

79

The certification process for tritium operators at TFTR  

SciTech Connect (OSTI)

The TFTR project, in concert with the PPPL Office of Certification and Training (OC and T), has established a program by which Tritium Operations Personnel are certified for their respective positions in accordance with DOE Order 5480.20A Personnel Selection, Qualification, and Training at DOE Nuclear Facilities and DOE Order 5480.19 conduct of Operations Requirements for DOE Facilities. The certification process commences during the candidate`s interview for the position of TFTR Tritium Operator. Prior to accepting a candidate into the tritium operation program, a detailed educational and work experience record is constructed for the candidate, including an interview by OC and T personnel to assess the candidates credentials and ability to successfully complete the program. The typical successful candidate for the position of TFTR Tritium Operator has worked in the nuclear or chemical industry for several years, and in many cases possess a college degree. A US Nuclear Navy background is quite common for many of the applicants. Candidates complete the program in 4 to 6 months, and typically move into supervisory positions (Tritium Shift Supervisors) within 2 to 3 years.

Gentile, C.A.; Murphy, S.E.; LaMarche, P.H.; Contino, A.M.; Gordon, S. [Princeton Plasma Physics Lab., NJ (United States)

1995-12-31T23:59:59.000Z

80

Tritium inventory tracking and management  

SciTech Connect (OSTI)

This investigation has identified a number of useful applications of the analysis of the tracking and management of the tritium inventory in the various subsystems and components in a DT fusion reactor system. Due to the large amounts of tritium that will need to be circulated within such a plant, and the hazards of dealing with the tritium an electricity generating utility may not wish to also be in the tritium production and supply business on a full time basis. Possible scenarios for system operation have been presented, including options with zero net increase in tritium inventory, annual maintenance and blanket replacement, rapid increases in tritium creation for the production of additional tritium supplies for new plant startup, and failures in certain system components. It has been found that the value of the tritium breeding ratio required to stabilize the storage inventory depends strongly on the value and nature of other system characteristics. The real operation of a DT fusion reactor power plant will include maintenance and blanket replacement shutdowns which will affect the operation of the tritium handling system. It was also found that only modest increases in the tritium breeding ratio are needed in order to produce sufficient extra tritium for the startup of new reactors in less than two years. Thus, the continuous operation of a reactor system with a high tritium breeding ratio in order to have sufficient supplies for other plants is not necessary. Lastly, the overall operation and reliability of the power plant is greatly affected by failures in the fuel cleanup and plasma exhaust systems.

Eichenberg, T.W.; Klein, A.C.

1990-09-10T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Tritium Release from Silica Glass  

Science Journals Connector (OSTI)

Material Interaction and Permeation / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

T.Tanifuji; S. Jitsukawa; S.Nasu; A.Moon; K.Mori; S.Nishikawa; M.Yamanaka; Y.Izawa

82

Fusion Tritium Program in the United States  

Science Journals Connector (OSTI)

National Fusion Tritium Program / Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988)

James L. Anderson; John R. Bartlit

83

Dosimetry and Standardization of Tritium in Russia  

Science Journals Connector (OSTI)

Tritium Safety / Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

M.I. Balonov; G. Ya. Bruk; T.V. Zhesko

84

Tritium Transport Vessel Using Depleted Uranium  

Science Journals Connector (OSTI)

Tritium Storage, Distribution, and Transportation / Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

L. K. Heung

85

International control of tritium to prevent horizontal proliferation and to foster nuclear disarmament  

SciTech Connect (OSTI)

In this paper, an approach to control tritium systematically on the international level is proposed. The first goal is to prevent the military use of tritium in states other than the five recognized nuclear weapons states. An {open_quotes}International Tritium Control System{close_quotes} (ITCS) would control all civilian facilities producing or handling tritium. The second goal is to restrict the availability of fresh tritium supplies for nuclear weapons programs as a means to avoid vertical proliferation in states that possess nuclear weapons, and as a step towards complete nuclear disarmament. This can be achieved by including tritium in a future weapons-usable materials production cutoff agreement and the approach proposed here is called an {open_quotes}Integrated Cutoff{close_quotes} (ICO). The simultaneous implementation of the ITCS and ICO aims at avoiding any new discrimination against non-nuclear weapon states. This paper will discuss the possible political and technical modalities to achieve both goals. The rules and decision making procedures are outlined for both control approaches and the implications for the nuclear non-proliferation regime are shown. Various control tasks are derived from a comprehensive analysis covering all diversion paths which can yield more than one gram of tritium within one year. In the appendix to this paper, the impact of a tritium shortage on the U.S. nuclear arsenal is illuminated. The extreme case of complete elimination of all tritium would result in a large yield reductions of the arsenal.

Kalinowski, M.B.; Colschen, L.C. [Institut fuer Kernphysik, Darmstadt (Germany)

1995-11-01T23:59:59.000Z

86

Chapter 4. Uranium Mine and Extraction Facility Reclamation This chapter is not intended to serve as guidance, or to supplement EPA or other agency environmental  

E-Print Network [OSTI]

4-1 Chapter 4. Uranium Mine and Extraction Facility Reclamation This chapter is not intended, it is an outline of practices which may or have been used for uranium site restoration. Mining reclamation for uranium mining sites. The existence of bonding requirements and/or financial guarantees in the cases where

87

Tritium diagnostics in a fusion reactor  

Science Journals Connector (OSTI)

Methods for controlling tritium in a fusion reactor are reviewed. The characteristic features of the...

A. I. Markin; N. I. Syromyatnikov; A. M. Belov

2010-05-01T23:59:59.000Z

88

Tritium in the Savannah River Site environment. Revision 1  

SciTech Connect (OSTI)

Tritium is released to the environment from many of the operations at the Savannah River Site. The releases from each facility to the atmosphere and to the soil and streams, both from normal operations and inadvertent releases, over the period of operation from the early 1950s through 1988 are presented. The fate of the tritium released is evaluated through environmental monitoring, special studies, and modeling. It is concluded that approximately 91% of the tritium remaining after decay is now in the oceans. A dose and risk assessment to the population around the site is presented. It is concluded that about 0.6 fatal cancers may be associated with the tritium released during all the years of operation to the population of about 625,000. This same population (based on the overall US cancer statistics) is expected to experience about 105,000 cancer fatalities from all types of cancer. Therefore, it is considered unlikely that a relationship between any of the cancer deaths occurring in this population and releases of tritium from the SRS will be found.

Murphy, C.E. Jr.; Bauer, L.R.; Hayes, D.W.; Marter, W.L.; Zeigler, C.C.; Stephenson, D.E.; Hoel, D.D.; Hamby, D.M.

1991-05-01T23:59:59.000Z

89

Normalized Tritium Quantification Approach (NoTQA) a Method for Quantifying Tritium Contaminated Trash and Debris at LLNL  

SciTech Connect (OSTI)

Several facilities and many projects at LLNL work exclusively with tritium. These operations have the potential to generate large quantities of Low-Level Radioactive Waste (LLW) with the same or similar radiological characteristics. A standardized documented approach to characterizing these waste materials for disposal as radioactive waste will enhance the ability of the Laboratory to manage them in an efficient and timely manner while ensuring compliance with all applicable regulatory requirements. This standardized characterization approach couples documented process knowledge with analytical verification and is very conservative, overestimating the radioactivity concentration of the waste. The characterization approach documented here is the Normalized Tritium Quantification Approach (NoTQA). This document will serve as a Technical Basis Document which can be referenced in radioactive waste characterization documentation packages such as the Information Gathering Document. In general, radiological characterization of waste consists of both developing an isotopic breakdown (distribution) of radionuclides contaminating the waste and using an appropriate method to quantify the radionuclides in the waste. Characterization approaches require varying degrees of rigor depending upon the radionuclides contaminating the waste and the concentration of the radionuclide contaminants as related to regulatory thresholds. Generally, as activity levels in the waste approach a regulatory or disposal facility threshold the degree of required precision and accuracy, and therefore the level of rigor, increases. In the case of tritium, thresholds of concern for control, contamination, transportation, and waste acceptance are relatively high. Due to the benign nature of tritium and the resulting higher regulatory thresholds, this less rigorous yet conservative characterization approach is appropriate. The scope of this document is to define an appropriate and acceptable characterization method for quantification of tritium contaminated trash and debris. The characterization technique is applicable to surface and subsurface tritium contaminated materials with surfaces amenable to swiping. Some limitations of this characterization technique are identified.

Dominick, J L; Rasmussen, C L

2008-07-23T23:59:59.000Z

90

Differential atmospheric tritium sampler  

DOE Patents [OSTI]

An atmospheric tritium sampler is provided which uses a carrier gas comprised of hydrogen gas and a diluting gas, mixed in a nonexplosive concentration. Sample air and carrier gas are drawn into and mixed in a manifold. A regulator meters the carrier gas flow to the manifold. The air sample/carrier gas mixture is pulled through a first moisture trap which adsorbs water from the air sample. The moisture then passes through a combustion chamber where hydrogen gas in the form of H/sub 2/ or HT is combusted into water. The manufactured water is transported by the air stream to a second moisture trap where it is adsorbed. The air is then discharged back into the atmosphere by means of a pump.

Griesbach, O.A.; Stencel, J.R.

1987-10-02T23:59:59.000Z

91

Differential atmospheric tritium sampler  

DOE Patents [OSTI]

An atmospheric tritium sampler is provided which uses a carrier gas comprised of hydrogen gas and a diluting gas, mixed in a nonexplosive concentration. Sample air and carrier gas are drawn into and mixed in a manifold. A regulator meters the carrier gas flow to the manifold. The air sample/carrier gas mixture is pulled through a first moisture trap which adsorbs water from the air sample. The mixture then passes through a combustion chamber where hydrogen gas in the form of H.sub.2 or HT is combusted into water. The manufactured water is transported by the air stream to a second moisture trap where it is adsorbed. The air is then discharged back into the atmosphere by means of a pump.

Griesbach, Otto A. (Langhorne, PA); Stencel, Joseph R. (Skillman, NJ)

1990-01-01T23:59:59.000Z

92

Mercury and tritium removal from DOE waste oils  

SciTech Connect (OSTI)

This work covers the investigation of vacuum extraction as a means to remove tritiated contamination as well as the removal via sorption of dissolved mercury from contaminated oils. The radiation damage in oils from tritium causes production of hydrogen, methane, and low-molecular-weight hydrocarbons. When tritium gas is present in the oil, the tritium atom is incorporated into the formed hydrocarbons. The transformer industry measures gas content/composition of transformer oils as a diagnostic tool for the transformers` condition. The analytical approach (ASTM D3612-90) used for these measurements is vacuum extraction of all gases (H{sub 2}, N{sub 2}, O{sub 2}, CO, CO{sub 2}, etc.) followed by analysis of the evolved gas mixture. This extraction method will be adapted to remove dissolved gases (including tritium) from the SRS vacuum pump oil. It may be necessary to heat (60{degrees}C to 70{degrees}C) the oil during vacuum extraction to remove tritiated water. A method described in the procedures is a stripper column extraction, in which a carrier gas (argon) is used to remove dissolved gases from oil that is dispersed on high surface area beads. This method appears promising for scale-up as a treatment process, and a modified process is also being used as a dewatering technique by SD Myers, Inc. (a transformer consulting company) for transformers in the field by a mobile unit. Although some mercury may be removed during the vacuum extraction, the most common technique for removing mercury from oil is by using sulfur-impregnated activated carbon (SIAC). SIAC is currently being used by the petroleum industry to remove mercury from hydrocarbon mixtures, but the sorbent has not been previously tested on DOE vacuum oil waste. It is anticipated that a final process will be similar to technologies used by the petroleum industry and is comparable to ion exchange operations in large column-type reactors.

Klasson, E.T. [Oak Ridge National Lab., TN (United States)

1997-10-01T23:59:59.000Z

93

Individual and population dose to users of the Savannah River following K-Reactor tritium release  

SciTech Connect (OSTI)

Approximately 5700 curies of tritium were released to Pen Branch between December 22, 1991 and December 25, 1991. As expected, the tritiated water traveled through the Savannah River swamp to Steel Creek and the Savannah River. Elevated tritium concentrations in the river at Becks Ferry (Beaufort-Jasper) and Abercorn Creek (Port Wentworth) has caused some concern among downstream water users as to the amount of tritium available for uptake through the domestic drinking water supplies at the Beaufort-Jasper and Port Wentworth water treatment facilities. Radiation dose to the downstream drinking water population is estimated in this report.

Carlton, W.H.; Hamby, D.M.

1992-12-31T23:59:59.000Z

94

Separation of Tritium from Wastewater  

SciTech Connect (OSTI)

A proprietary tritium loading bed developed by Molecular Separations, Inc (MSI) has been shown to selectively load tritiated water as waters of hydration at near ambient temperatures. Tests conducted with a 126 {micro}C{sub 1} tritium/liter water standard mixture showed reductions to 25 {micro}C{sub 1}/L utilizing two, 2-meter long columns in series. Demonstration tests with Hanford Site wastewater samples indicate an approximate tritium concentration reduction from 0.3 {micro}C{sub 1}/L to 0.07 {micro}C{sub 1}/L for a series of two, 2-meter long stationary column beds Further reduction to less than 0.02 {micro}C{sub 1}/L, the current drinking water maximum contaminant level (MCL), is projected with additional bed media in series. Tritium can be removed from the loaded beds with a modest temperature increase and the beds can be reused Results of initial tests are presented and a moving bed process for treating large quantities of wastewaters is proposed. The moving bed separation process appears promising to treat existing large quantities of wastewater at various US Department of Energy (DOE) sites. The enriched tritium stream can be grouted for waste disposition. The separations system has also been shown to reduce tritium concentrations in nuclear reactor cooling water to levels that allow reuse. Energy requirements to reconstitute the loading beds and waste disposal costs for this process appear modest.

JEPPSON, D.W.

2000-01-25T23:59:59.000Z

95

Primer on tritium safe handling practices  

SciTech Connect (OSTI)

This Primer is designed for use by operations and maintenance personnel to improve their knowledge of tritium safe handling practices. It is applicable to many job classifications and can be used as a reference for classroom work or for self-study. It is presented in general terms for use throughout the DOE Complex. After reading it, one should be able to: describe methods of measuring airborne tritium concentration; list types of protective clothing effective against tritium uptake from surface and airborne contamination; name two methods of reducing the body dose after a tritium uptake; describe the most common method for determining amount of tritium uptake in the body; describe steps to take following an accidental release of airborne tritium; describe the damage to metals that results from absorption of tritium; explain how washing hands or showering in cold water helps reduce tritium uptake; and describe how tritium exchanges with normal hydrogen in water and hydrocarbons.

Not Available

1994-12-01T23:59:59.000Z

96

Fermilab | Tritium at Fermilab | Ferry Creek Results  

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

(click chart for larger version) shows the levels of tritium in Ferry Creek on the Fermilab site since April 2006. To date, Fermilab has not detected tritium in Ferry Creek. The...

97

Circulation of Tritium in the Pacific Ocean  

Science Journals Connector (OSTI)

The input of bomb tritium into the high-latitude Northern Hemisphere waters has demonstrated the spread of a tracer in three dimensions in the North Pacific Ocean. Subsurface tritium maxima in middle and low latitudes clearly show the importance ...

Rana A. Fine; Joseph L. Reid; H. Göte Östlund

1981-01-01T23:59:59.000Z

98

EVALUATION OF ALTERNATE STAINLESS STEEL SURFACE TREATMENTS FOR MASS SPECTROSCOPY AND OTHER TRITIUM SYSTEMS  

SciTech Connect (OSTI)

There are specific components in the SRS Tritium Facilities that are required to introduce as few chemical impurities (such as protium and methane) as possible into the process gas. Two such components are the inlet systems for the mass spectroscopy facilities and hydrogen isotope mix standard containers. Two vendors now passivate stainless steel components for these systems, and both are relatively small businesses whose future viability can be questioned, which creates the need for new sources. Stainless steel containers were designed to evaluate alternate surface treatment vendors for tritium storage and handling for these high purity tritium systems. Five vendors applied their own 'best' surface treatments to two containers each - one was a current vendor, another was a chemical vapor deposited silicon coating, and the other three were electropolishing and chemical cleaning vendors. Pure tritium gas was introduced into all ten containers and the composition was monitored over time. The only observed impurities in the gas were some HT, less CT{sub 4}, and very small amounts of T{sub 2}O in all cases. The currently used vendor treated containers contained the least impurities. The chemical vapor deposited silicon treatment resulted in the highest impurity levels. Sampling one set of containers after about one month of tritium exposure revealed the impurity level to be nearly the same as that after more than a year of exposure - this result suggests that cleaning new stainless steel components by tritium gas contact for about a month may be a worthy operation.

Clark, E.; Mauldin, C.; Neikirk, K.

2012-02-29T23:59:59.000Z

99

Tritium diagnostics in a fusion reactor  

SciTech Connect (OSTI)

Methods for controlling tritium in a fusion reactor are reviewed. The characteristic features of the interaction of tritium with surfaces are considered, as well as its diffusive properties and its levels and saturation depths for a number of radioactive materials. New properties of boundary layers and new diffusive properties in the polycrystalline structure of metals are revealed. Unique measurements of the diffusive properties of tritium in stainless steel at room temperature are carried out. It is found that the main contribution to the diffusion process comes from the intergranular tritium flux. The capture of tritium by metals in the ITER device is calculated.

Markin, A. I.; Syromyatnikov, N. I.; Belov, A. M. [Troitsk Institute for Innovation and Fusion Research (Russian Federation)

2010-05-15T23:59:59.000Z

100

Tritium Handling and Safe Storage  

Broader source: Energy.gov (indexed) [DOE]

SENSITIVE DOE-HDBK-1129-2007 March 2007 ____________________ DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1129-2007

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Generation of gaseous tritium standards  

SciTech Connect (OSTI)

The determination of aqueous and non-aqueous tritium in gaseous samples is one type of determination often requested of radioanalytical laboratories. This determination can be made by introducing the sample as a gas into a sampling train containing two silica gel beds separated by.a catalytic oxidizer bed. The first bed traps tritiated water. The sample then passes into and through the oxidizer bed where non-aqueous tritium containing species are oxidized to water and other products of combustion. The second silica gel bed then traps the newly formed tritiated water. Subsequently, silica gel is removed to plastic bottles, deionized water is added, and the mixture is permitted to equilibrate. The tritium content of the equilibrium mixture is then determined by conventional liquid scintillation counting (LSC). For many years, the moisture content of inert, gaseous samples has been determined using monitors which quantitatively electrolyze the moisture present after that moisture has been absorbed by phosphorous pentoxide or other absorbents. The electrochemical reaction is quantitative and definitive, and the energy consumed during electrolysis forms the basis of the continuous display of the moisture present. This report discusses the experimental evaluation of such a monitor as the basis for a technique for conversion of small quantities of SRMs of tritiated water ({sup 3}HOH) into gaseous tritium standards ({sup 3}HH).

Hohorst, F.A.

1994-09-01T23:59:59.000Z

102

Tritium production potential of beam research and magnetic fusion program technologies  

SciTech Connect (OSTI)

Regular replenishment of tritium in the nuclear weapons stockpile is essential to maintain our nuclear deterrent. Nuclear reactor facilities presently used for the production of tritium are aging, and their operation is being curtailed awaiting the repairs and upgrades needed to meet modern standards of safety and environment. To provide improved capability in the future, DOE plans to construct a new production reactor. Alternatives to nuclear reactor methods for the production of tritium, mainly electrically-driven accelerator or fusion systems, have been proposed many times in the past. Given the critical national security implications of maintaining adequate tritium production facilities, it is clearly worthwhile for political decision-makers to have a clear and accurate picture of the technical options that could be made available at various points in the future. The goal of this white paper is to summarize available technical information on a set of non-nuclear-reactor options for tritium production with a minimum of advocacy for any one system of implicit assumptions about politically desirable attributes. Indeed, these various options differ considerably in aspects such as the maturity of the technology, the development cost and timescales required, and the capital and operating costs of a typical ''optimized'' facility.

Lee, J.D. (comp.)

1989-03-01T23:59:59.000Z

103

Real-time aqueous tritium monitor using liquid scintillation counting  

SciTech Connect (OSTI)

An ability to continuously monitor low-level tritium releases in aqueous effluents is of particular interest to heavy water facilities such as those at the Savannah River Site (SRS) and Canadian CANDU reactors. SRS developed a real-time monitoring system based on flow-through liquid scintillation (LS) counting. Sensitivities of 16 pCi/mL and 1 pCi/mL result from five minute and daily averages of counting data respectively. This sensitivity is about 200 times better than similar methods using solid scintillants. The LS system features uncomplicated sample pretreatment, precise of the cocktail and sample water, system features uncomplicated sample pretreatment, precise proportioning of the cocktail and sample water, on-line quench corrections, cocktail consumption as low as 0.15 mL/min, and response to changes in environmental tritium is less than 30 minutes. Field tests demonstrate that conditions necessary for stable analytical results are achieved.

Sigg, R.A.; McCarty, J.E.; Livingston, R.R.; Sanders, M.A.

1994-07-01T23:59:59.000Z

104

EFFECTS OF TRITIUM EXPOSURE ON UHMW-PE, PTFE, AND VESPEL  

SciTech Connect (OSTI)

Samples of three polymers, Ultra-High Molecular Weight Polyethylene (UHMW-PE), polytetrafluoroethylene (PTFE, also known as Teflon{reg_sign}), and Vespel{reg_sign} polyimide were exposed to 1 atmosphere of tritium gas at ambient temperature for varying times up to 2.3 years in closed containers. Sample mass and size measurements (to calculate density), spectra-colorimetry, dynamic mechanical analysis (DMA), and Fourier-transform infrared spectroscopy (FT-IR) were employed to characterize the effects of tritium exposure on these samples. Changes of the tritium exposure gas itself were characterized at the end of exposure by measuring total pressure and by mass spectroscopic analysis of the gas composition. None of the polymers exhibited significant changes of density. The color of initially white UHMW-PE and PTFE dramatically darkened to the eye and the color also significantly changed as measured by colorimetry. The bulk of UHMW-PE darkened just like the external surfaces, however the fracture surface of PTFE appeared white compared to the PTFE external surfaces. The white interior could have been formed while the sample was breaking or could reflect the extra tritium dose at the surface directly from the gas. The dynamic mechanical response of UHMW-PE was typical of radiation effects on polymers- an initial stiffening (increased storage modulus) and reduction of viscous behavior after three months exposure, followed by lowering of the storage modulus after one year exposure and longer. The storage modulus of PTFE increased through about nine months tritium exposure, then the samples became too weak to handle or test using DMA. Characterization of Vespel{reg_sign} using DMA was problematic--sample-to-sample variations were significant and no systematic change with tritium exposure could be discerned. Isotopic exchange and incorporation of tritium into UHMW-PE (exchanging for protium) and into PTFE (exchanging for fluorine) was observed by FT-IR using an attenuated total reflectance method. No significant change in the Vespel{reg_sign} infrared spectrum was observed after three months exposure. Protium significantly pressurized the UHMW-PE containers during exposure to about nine atmospheres (the initial pressure was one atmosphere of tritium). This is consistent with the well-known production of hydrogen by irradiation of polyethylene by ionizing radiation. The total pressure in the PTFE containers decreased, and a mass balance reveals that the observed decrease is consistent with the formation of small amounts of {sup 3}HF, which is condensed at ambient temperature. No significant change of pressure occurred in the Vespel{reg_sign} containers; however the composition of the gas became about 50% protium, showing that Vespel{reg_sign} interacted with the tritium gas atmosphere to some degree. The relative resistance to degradation from tritium exposure is least for PTFE, more for UHMW-PE, and the most for Vespel{reg_sign}, which is consistent with the known relative resistance of these polymers to gamma irradiation. This qualitatively agrees with the concept of equivalent effects for equivalent absorbed doses of radiation damage of polymers. Some of the changes of different polymers are qualitatively similar; however each polymer exhibited unique property changes when exposed to tritium. Information from this study that can be applied to a tritium facility is: (1) the relative resistance to tritium degradation of the three polymers studied is the same as the relative resistance to gamma irradiation in air (so relative rankings of polymer resistance to ionizing radiation can be used as a relative ranking for assessing tritium compatibility and polymer selection); and (2) all three polymers changed the gas atmosphere during tritium exposure--UHMW-PE and Vespel{reg_sign} exposed to tritium formed H{sub 2} gas (UHMW-PE much more so), and PTFE exposed to tritium formed {sup 3}HF. This observation of forming {sup 3}HF supports the general concept of minimizing chlorofluorocarbon polymers in tritium systems.

Clark, E; Kirk Shanahan, K

2006-05-31T23:59:59.000Z

105

Chemical behavior of tritium in/on various materials  

SciTech Connect (OSTI)

In this paper, the chemical interaction of tritium with various materials is studied. The chemical state of tritium resting in materials depended on their chemical and physical conditions. The state of tritium can be classified into four categories, chemically bounded tritium, molecularly trapped tritium, tritium trapped as atomic state, and tritium localized in a special part. These chemical states in or on materials controlled the diffusivity of tritium in them and release from their surfaces. The chemical properties of materials mainly affect the resting state of tritium, but in some cases, the effects of physical properties are more important than those of the chemical ones.

Saeki, M.; Hirabayashi, T.; Aratono, Y.; Nakashima, M.; Masaki, N.M.; Tachikawa, E. (Dept. of Chemistry, Japan Atomic Energy Research Inst., Tokai-mura, Ibaraki-ken 319-11 (JP))

1992-03-01T23:59:59.000Z

106

Trees as indicators of subterranean migration of tritium at a commercial shallow land radioactive waste disposal site. [Maxey Flats, KY  

SciTech Connect (OSTI)

Leaf water and tree sap collected from deciduous trees in a natural forest growing outside the fenced exclusion area of the Maxey Flats Waste Disposal Facility in eastern Kentucky, USA were radiochemically analyzed to detect movement of tritium via subterranean flows of water at depths of three meters. These data indicate that trees can be used to detect the subterranean migration of tritium from shallow land burial sites. 4 references, 5 figures, 1 table.

Rickard, W.H.; Kirby, L.J.

1984-09-01T23:59:59.000Z

107

Tritium Handling and Safe Storage  

Broader source: Energy.gov (indexed) [DOE]

DOE-HDBK-1129-2008 December 2008 DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-HDBK-1129-2008 ii This page is intentionally blank. DOE-HDBK-1129-2008 iii TABLE OF CONTENTS SECTION PAGE FOREWORD................................................................................................................................ ix ACRONYMS ................................................................................................................................ xi 1.0 INTRODUCTION ....................................................................................................................

108

DEPLOYMENT OF THE BULK TRITIUM SHIPPING PACKAGE  

SciTech Connect (OSTI)

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

Blanton, P.

2013-10-10T23:59:59.000Z

109

Tritium Removal from Carbon Plasma Facing Components  

SciTech Connect (OSTI)

Tritium removal is a major unsolved development task for next-step devices with carbon plasma-facing components. The 2-3 order of magnitude increase in duty cycle and associated tritium accumulation rate in a next-step tokamak will place unprecedented demands on tritium removal technology. The associated technical risk can be mitigated only if suitable removal techniques are demonstrated on tokamaks before the construction of a next-step device. This article reviews the history of codeposition, the tritium experience of TFTR (Tokamak Fusion Test Reactor) and JET (Joint European Torus) and the tritium removal rate required to support ITER's planned operational schedule. The merits and shortcomings of various tritium removal techniques are discussed with particular emphasis on oxidation and laser surface heating.

C.H. Skinner; J.P. Coad; G. Federici

2003-11-24T23:59:59.000Z

110

Assembly of High-Areal-Density Deuterium-Tritium Fuel from Indirectly Driven Cryogenic Implosions  

E-Print Network [OSTI]

The National Ignition Facility has been used to compress deuterium-tritium to an average areal density of ~1.0±0.1??g?cm[superscript -2], which is 67% of the ignition requirement. These conditions were obtained using 192 ...

Casey, Daniel Thomas

111

Tritium radioluminescent devices, Health and Safety Manual  

SciTech Connect (OSTI)

This document consolidates available information on the properties of tritium, including its environmental chemistry, its health physics, and safe practices in using tritium-activated RL lighting. It also summarizes relevant government regulations on RL lighting. Chapters are divided into a single-column part, which provides an overview of the topic for readers simply requiring guidance on the safety of tritium RL lighting, and a dual-column part for readers requiring more technical and detailed information.

Traub, R.J.; Jensen, G.A.

1995-06-01T23:59:59.000Z

112

Use of Metal Hydrides for Handling Tritium  

Science Journals Connector (OSTI)

Material Interaction / Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985)

Mark S. Ortman; Thomas J. Warren; Daniel J. Smith

113

Development of Catalyst for Recovery of Tritium  

Science Journals Connector (OSTI)

Blanket Material and Process / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

Kenzo Munakata; Satoshi Yamatsuki; Yoshihiro Yokoyama; Seigo Kanjo; Dmitri Ianovski; Yamato Asakura; Tatsuhiko Uda

114

Overview of Tritium Activities in Japan  

Science Journals Connector (OSTI)

Plenary Session / Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

Makoto Okamoto; Kenji Okuno

115

Thermal Removal Of Tritium From Concrete And Soil To Reduce Groundwater Impacts  

SciTech Connect (OSTI)

Legacy heavy-water moderator operations at the Savannah River Site (SRS) have resulted in the contamination of equipment pads, building slabs, and surrounding soil with tritium. At the time of discovery the tritium had impacted the shallow (< 3-m) groundwater at the facility. While tritium was present in the groundwater, characterization efforts determined that a significant source remained in a concrete slab at the surface and within the associated vadose zone soils. To prevent continued long-term impacts to the shallow groundwater a CERCLA non-time critical removal action for these source materials was conducted to reduce the leaching of tritium from the vadose zone soils and concrete slabs. In order to minimize transportation and disposal costs, an on-site thermal treatment process was designed, tested, and implemented. The on-site treatment consisted of thermal detritiation of the concrete rubble and soil. During this process concrete rubble was heated to a temperature of 815 deg C (1,500 deg F) resulting in the dehydration and removal of water bound tritium. During heating, tritium contaminated soil was used to provide thermal insulation during which it's temperature exceeded 100 deg C (212 deg F), causing drying and removal of tritium. The thermal treatment process volatiles the water bound tritium and releases it to the atmosphere. The released tritium was considered insignificant based upon Clean Air Act Compliance Package (CAP88) analysis and did not exceed exposure thresholds. A treatability study evaluated the effectiveness of this thermal configuration and viability as a decontamination method for tritium in concrete and soil materials. Post treatment sampling confirmed the effectiveness at reducing tritium to acceptable waste site specific levels. With American Recovery and Reinvestment Act (ARRA) funding three additional treatment cells were assembled utilizing commercial heating equipment and common construction materials. This provided a total of four units to batch treat concrete rubble and soil. Post treatment sampling verified that the activity in the treated soil and concrete met the treatment standards for each medium which allowed the treated concrete rubble and soil to be disposed of on site as backfill. During testing and operations a total of 1,261-m{sup 3} (1,650-yd{sup 3}) of contaminated concrete and soils were treated with an actual incurred cost of $3,980,000. This represents a unit treatment cost of $3,156/m{sup 3} ($2,412/yd{sup 3}). In 2011 the project was recognized with an e-Star Sustainability Award by DOE's Office of Environmental Management.

Jackson, Dennis G.; Blount, Gerald C.; Wells, Leslie H.; Cardoso-Neto, Joao E.; Kmetz, Thomas F.; Reed, Misty L.

2012-12-04T23:59:59.000Z

116

TRITIUM EFFECTS ON WELDMENT FRACTURE TOUGHNESS  

SciTech Connect (OSTI)

The effects of tritium on the fracture toughness properties of Type 304L stainless steel and its weldments were measured. Fracture toughness data are needed for assessing tritium reservoir structural integrity. This report provides data from J-Integral fracture toughness tests on unexposed and tritium-exposed weldments. The effect of tritium on weldment toughness has not been measured until now. The data include tests on tritium-exposed weldments after aging for up to three years to measure the effect of increasing decay helium concentration on toughness. The results indicate that Type 304L stainless steel weldments have high fracture toughness and are resistant to tritium aging effects on toughness. For unexposed alloys, weldment fracture toughness was higher than base metal toughness. Tritium-exposed-and-aged base metals and weldments had lower toughness values than unexposed ones but still retained good toughness properties. In both base metals and weldments there was an initial reduction in fracture toughness after tritium exposure but little change in fracture toughness values with increasing helium content in the range tested. Fracture modes occurred by the dimpled rupture process in unexposed and tritium-exposed steels and welds. This corroborates further the resistance of Type 304L steel to tritium embrittlement. This report fulfills the requirements for the FY06 Level 3 milestone, TSR15.3 ''Issue summary report for tritium reservoir material aging studies'' for the Enhanced Surveillance Campaign (ESC). The milestone was in support of ESC L2-1866 Milestone-''Complete an annual Enhanced Surveillance stockpile aging assessment report to support the annual assessment process''.

Morgan, M; Michael Tosten, M; Scott West, S

2006-07-17T23:59:59.000Z

117

Quick management of accidental tritium exposure cases  

Science Journals Connector (OSTI)

......as it turns into the regulatory dose limit. The slow...reference point for action plans against tritium removal...the boundary line of regulatory dose limits, the individual...incident) becomes below regulatory dose limits. CONCLUSIONS...Technol. ITER design review: tritium issues. Fusion......

Vishwanath P. Singh; N. M. Badiger; S. S. Managanvi; H. R. Bhat

2012-07-01T23:59:59.000Z

118

Tritium issues in commercial pressurized water reactors  

SciTech Connect (OSTI)

Tritium has become an important radionuclide in commercial Pressurized Water Reactors because of its mobility and tendency to concentrate in plant systems as tritiated water during the recycling of reactor coolant. Small quantities of tritium are released in routine regulated effluents as liquid water and as water vapor. Tritium has become a focus of attention at commercial nuclear power plants in recent years due to inadvertent, low-level, chronic releases arising from routine maintenance operations and from component failures. Tritium has been observed in groundwater in the vicinity of stations. The nuclear industry has undertaken strong proactive corrective measures to prevent recurrence, and continues to eliminate emission sources through its singular focus on public safety and environmental stewardship. This paper will discuss: production mechanisms for tritium, transport mechanisms from the reactor through plant, systems to the environment, examples of routine effluent releases, offsite doses, basic groundwater transport and geological issues, and recent nuclear industry environmental and legal ramifications. (authors)

Jones, G. [Constellation Energy Group, R.E. Ginna Nuclear Power Plant, Ontario, NY (United States)

2008-07-15T23:59:59.000Z

119

Tritium laboratory with multiple purposes at NIPNE Magurele Romania  

SciTech Connect (OSTI)

The Tritium Laboratory from NIPNE (Romania)) is part of Radioisotope Research and Production Center. The Tritium Laboratory has been in operation since 1960, and carries out R and D activities involving tritium sources in gaseous, liquids and solid state, provides specialized service to CANDU NPP Cernavoda (Romania)), and provides tritium assay services to internal and external customers. The paper presents the activities and perspectives of Tritium Laboratory and its performances in accordance with Quality System Management. (authors)

Matei, L.; Postolache, C. [Horia Hulubei, National Inst. for Physics and Nuclear Engineering NIPNE, 407 Atomistilor street, 077125 Magurele Ilfov (Romania)

2008-07-15T23:59:59.000Z

120

Tritium containing polymers having a polymer backbone substantially void of tritium  

DOE Patents [OSTI]

A radioluminescent light source comprises a solid mixture of a phosphorescent substance and a tritiated polymer. The solid mixture forms a solid mass having length, width, and thickness dimensions, and is capable of self-support. In one aspect of the invention, the phosphorescent substance comprises solid phosphor particles supported or surrounded within a solid matrix by a tritium containing polymer. The tritium containing polymer comprises a polymer backbone which is essentially void of tritium. 2 figs.

Jensen, G.A.; Nelson, D.A.; Molton, P.M.

1992-03-31T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Overview of tritium processing development at the tritium systems test assembly  

SciTech Connect (OSTI)

The Tritium Systems Test Assembly (TSTA) at the Los Alamos National Laboratory has been operating with tritium since June 1984. Presently there are some 50 g of tritium in the main processing loop. This 50 g has been sufficient to do a number of experiments involving the cryogenic distillation isotope separation system and to integrate the fuel cleanup system into the main fuel processing loop. In January 1986 two major experiments were conducted. During these experiments the fuel cleanup system was integrated, through the transfer pumping system, with the isotope separation system, thus permitting testing on the integrated fuel processing loop. This integration of these systems leaves only the main vacuum system to be integrated into the TSTA fuel processing loop. In September 1986 another major tritium experiment was performed in which the integrated loop was operated, the tritium inventory increased to 50 g and additional measurements on the performance of the distillation system were taken. In the period June 1984 through September 1986 the TSTA system has processed well over 10/sup 8/ Ci of tritium. Total tritium emissions to the environment over this period have been less than 15 Ci. Personnel exposures during this period have totaled less than 100 person-mRem. To date, the development of tritium technology at TSTA has proceeded in progressive and orderly steps. In two years of operation with tritium, no major design flows have been uncovered.

Anderson, J.L.

1986-10-22T23:59:59.000Z

122

Operation of the Room Air Tritium Removal System at the Tritium Systems Test Assembly  

Science Journals Connector (OSTI)

Blanket and Process Engineering / Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985)

R. V. Carlson; F. A. Damiano; K. E. Binning

123

Tritium in a deciduous forest adjacent to a commercial shallow land burial site: implications for monitoring to detect radionuclide migration. [Maxey Flats, Kentucky  

SciTech Connect (OSTI)

Tritium as tritiated water was measured in the sap taken from the trunks of 26 maple trees growing in the vicinity of the shallow-land, low-level radioactive waste disposal site at Maxey Flats, Kentucky. Tritium values ranged between 10,000 and 290,000 pCi/l with the highest levels measured in sap from trees growing downslope from the burial site's western boundary. Levels of tritium of less than 1000 pCi/l were measured at a distance of 20 kilometers from the site: The source of elevated tritium levels in the vicinity of the disposal site is the evaporator facility which has released tritiated water vapor into the air more or less continuously for 10 years. Another possible source of at least some of the tritium is subterranean leakage from the trenches located near the western boundary. The evaporator facility has been shut down since December 1982. With the shutdown of the evaporator the levels of tritium in tree sap in future years is expected to show a marked decline as the tritiated soil water in the root zone becomes increasingly diluted with fresh rainwater and the residual tritium is dissipated to the air by evaporation and plant transpiration processes. 11 references.

Rickard, W.H.; Kirby, L.J.

1983-09-01T23:59:59.000Z

124

Development of Tritium Permeation Analysis Code (TPAC)  

SciTech Connect (OSTI)

Idaho National Laboratory developed the Tritium Permeation Analysis Code (TPAC) for tritium permeation in the Very High Temperature Gas Cooled Reactor (VHTR). All the component models in the VHTR were developed and were embedded into the MATHLAB SIMULINK package with a Graphic User Interface. The governing equations of the nuclear ternary reaction and thermal neutron capture reactions from impurities in helium and graphite core, reflector, and control rods were implemented. The TPAC code was verified using analytical solutions for the tritium birth rate from the ternary fission, the birth rate from 3He, and the birth rate from 10B. This paper also provides comparisons of the TPAC with the existing other codes. A VHTR reference design was selected for tritium permeation study from the reference design to the nuclear-assisted hydrogen production plant and some sensitivity study results are presented based on the HTGR outlet temperature of 750 degrees C.

Eung S. Kim; Chang H. Oh; Mike Patterson

2010-10-01T23:59:59.000Z

125

EIS-0161: Tritium Supply and Recycling  

Broader source: Energy.gov [DOE]

This PEIS evaluates the potential environmental impacts of technology and siting alternatives for the production of tritium for national security purposes as well as the impacts of constructing a...

126

Experiments at the Safety and Tritium Applied Research Facility...  

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

chamber is housed inside a glovebox so that hazardous dusts can be safely tested. When fusion reactors operate, some of the wall material is eroded from the solid surface,...

127

In vitro Determination of Oxidation of Atmospheric Tritium Gas in Vegetation and Soil in Ibaraki and Gifu, JAPAN  

Science Journals Connector (OSTI)

......amounts of tritium gas (HT) as fuel. When HT from a nuclear facility...use. In a 12.5 ml glass vessel, 100 mg (fresh weight) of...water was introduced into each vessel and the supernatant was obtained...catalyze the production or consumption of molecular hydrogen with......

Michiko Ichimasa; Masatomo Suzuki; Haruo Obayashi; Youichi Sakuma; Yusuke Ichimasa

1999-09-01T23:59:59.000Z

128

Computational modeling and analysis of airflow in a tritium storage room  

SciTech Connect (OSTI)

In this study, a commercial computational fluid dynamics (CFD) code, CFX-5.5, was utilized to assess flow field characteristics, and to simulate tritium gas releases and subsequent transport in a storage room in the tritium handling facility at Los Alamos. This study was done with mesh refinement and results compared. The results show a complex, ventilation-induced flow field with vortices, velocity gradients, and stagnant air pockets. This paper also explains the timedependent gas dispersion results. The numerical analysis method used in this study provides important information that is possible to be validated with an experimental technique of aerosol tracer measurement method frequently used at Los Alamos. Application of CFD can have a favorable impact on the design of ventilation systems and worker safety with consideration to facility costs.

Chen, Z. (Zukun); Konecni, S. (Snezana); Whicker, J. J. (Jeffrey J.)

2003-01-01T23:59:59.000Z

129

Method and apparatus for controlling accidental releases of tritium  

DOE Patents [OSTI]

An improvement is described in a tritium control system based on a catalytic oxidation reactor wherein accidental releases of tritium into room air are controlled by flooding the catalytic oxidation reactor with hydrogen when the tritium concentration in the room air exceeds a specified limit. The sudden flooding with hydrogen heats the catalyst to a high temperature within seconds, thereby greatly increasing the catalytic oxidation rate of tritium to tritiated water vapor. Thus, the catalyst is heated only when needed. In addition to the heating effect, the hydrogen flow also swamps the tritium and further reduces the tritium release. 1 fig.

Galloway, T.R.

1980-04-01T23:59:59.000Z

130

System support software for TSTA (Tritium Systems Test Assembly)  

SciTech Connect (OSTI)

The fact that Tritium Systems Test Assembly (TSTA) is an experimental facility makes it impossible and undesirable to try to forecast the exact software requirements. Thus the software had to be written in a manner that would allow modifications without compromising the safety requirements imposed by the handling of tritium. This suggested a multi-level approach to the software. In this approach (much like the ISO network model) each level is isolated from the level below and above by cleanly defined interfaces. For example, the subsystem support level interfaces with the subsystem hardware through the software support level. Routines in the software support level provide operations like ''OPEN VALVE'' and CLOSE VALVE'' to the subsystem level. This isolates the subsystem level from the actual hardware. This is advantageous because changes can occur in any level without the need for propagating the change to any other level. The TSTA control system consists of the hardware level, the data conversion level, the operator interface level, and the subsystem process level. These levels are described.

Claborn, G.W.; Mann, L.W.; Nielson, C.W.

1987-10-01T23:59:59.000Z

131

EFFECTS OF TRITIUM GAS EXPOSURE ON ELECTRICALLY CONDUCTING POLYMERS  

SciTech Connect (OSTI)

Effects of beta (tritium) and gamma irradiation on the surface electrical conductivity of two types of conducting polymer films are documented to determine their potential use as a sensing and surveillance device for the tritium facility. It was shown that surface conductivity was significantly reduced by irradiation with both gamma and tritium gas. In order to compare the results from the two radiation sources, an approximate dose equivalence was calculated. The materials were also sensitive to small radiation doses (<10{sup 5} rad), showing that there is a measurable response to relatively small total doses of tritium gas. Spectroscopy was also used to confirm the mechanism by which this sensing device would operate in order to calibrate this sensor for potential use. It was determined that one material (polyaniline) was very sensitive to oxidation while the other material (PEDOT-PSS) was not. However, polyaniline provided the best response as a sensing material, and it is suggested that an oxygen-impermeable, radiation-transparent coating be applied to this material for future device prototype fabrication. A great deal of interest has developed in recent years in the area of conducting polymers due to the high levels of conductivity that can be achieved, some comparable to that of metals [Gerard 2002]. Additionally, the desirable physical and chemical properties of a polymer are retained and can be exploited for various applications, including light emitting diodes (LED), anti-static packaging, electronic coatings, and sensors. The electron transfer mechanism is generally accepted as one of electron 'hopping' through delocalized electrons in the conjugated backbone, although other mechanisms have been proposed based on the type of polymer and dopant [Inzelt 2000, Gerard 2002]. The conducting polymer polyaniline (PANi) is of particular interest because there are extensive studies on the modulation of the conductivity by changing either the oxidation state of the main backbone chain, or by protonation of the imine groups [de Acevedo, 1999]. There are several types of radiation sensors commercially available, including ionization chambers, geiger counters, proportional counters, scintillators and solid state detectors. Each type has advantages, although many of these sensors require expensive electronics for signal amplification, are large and bulky, have limited battery life or require expensive materials for fabrication. A radiation sensor constructed of a polymeric material could be flexible, light, and the geometry designed to suit the application. Very simple and inexpensive electronics would be necessary to measure the change in conductivity with exposure to radiation and provide an alarm system when a set change of conductivity occurs in the sensor that corresponds to a predetermined radiation dose having been absorbed by the polymer. The advantages of using a polymeric sensor of this type rather than those currently in use are the flexibility of sensor geometry and relatively low cost. It is anticipated that these sensors can be made small enough for glovebox applications or have the ability to monitor the air tritium levels in places where a traditional monitor cannot be placed. There have been a few studies on the changes in conductivity of polyaniline specifically for radiation detection [de Acevedo, 1999; Lima Pacheco, 2003], but there have been no reports on the effects of tritium (beta radiation) on conducting polymers, such as polyaniline or polythiophene. The direct implementation of conducting polymers as radiation sensor materials has not yet been commercialized due to differing responses with total dose, dose rate, etc. Some have reported a large increase in the surface conductivity with radiation dose while others report a marked decrease in conductive properties; these differing observations may reflect the competing mechanisms of chain scission and cross-linking. However, it is clear that the radiation dose effects on conducting polymers must be fully understood before these materials can be used

Kane, M.; Clark, E.; Lascola, R.

2009-12-16T23:59:59.000Z

132

Selection of fluids for tritium pumping systems  

SciTech Connect (OSTI)

The degradation characteristics of three types of vacuum pump fluids, polyphenyl ethers, perfluoropolyethers and hydrocarbon oils were reviewed. Fluid selection proved to be a critical factor in the long-term performance of tritium pumping systems and subsequent tritium recovery operations. Thermal degradation and tritium radiolysis of pump fluids produce contaminants which can damage equipment and interfere with tritium recovery operations. General characteristics of these fluids are as follows: polyphenyl ether has outstanding radiation resistance, is very stable under normal diffusion pump conditions, but breaks down in the presence of oxygen at anticipated operating temperatures. Perfluoropolyether fluids are very stable and do not react chemically with most gases. Thermal and mechanical degradation products are inert, but the radiolysis products are very corrosive. Most of the degradation products of hydrogen oils are volatile and the principal radiolysis product is methane. Our studies show that polyphenyl ethers and hydrocarbon oils are the preferred fluids for use in tritium pumping systems. No corrosive materials are formed and most of the degradation products can be removed with suitable filter systems.

Chastagner, P

1984-02-01T23:59:59.000Z

133

UV/Ozone Treatment to Decontaminate Tritium Contaminated Surfaces  

Science Journals Connector (OSTI)

Design, Operation, and Maintenance of Tritium System / Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

John P. Krasznai; Reid Mowat

134

Enrichment reliability of solid polymer electrolysis for tritium water analysis  

Science Journals Connector (OSTI)

We have developed a novel advanced enrichment apparatus for environmental tritium analysis called SPET (Solid Polymer Electrolysis for Tritium Water). It generates no explosive gas, requires ... of SPET was studi...

M. Saito

2008-02-01T23:59:59.000Z

135

Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State-Approved Land Disposal Site-FY1999  

SciTech Connect (OSTI)

The Hanford Site 200 Area Effluent Treatment Facility (ETF) processes contaminated liquids derived from Hanford Site facilities. The clean water generated by these processes is occasionally enriched in tritium and is discharged to the 200 Area State Approved Land Disposal Site (SALDS). Groundwater monitoring for tritium and other constituents is required by the state-issued permit at 21 wells surrounding the facility. During FY 1999, average tritium activities in most wells declined from average activities in 1998. The exception was deep well 69948-77C, where tritium results were at an all-time high (77,000 pCi/L) as a result of the delayed penetration of effluent deeper into the aquifer. Of the 12 constituents with permit enforcement limits, which are monitored in SALDS proximal wells, all were within limits during FY 1999. Water level measurements in nearby wells indicate that a small hydraulic mound exists around the SALDS facility as a result of discharges. This feature is directing groundwater flow radially outward a short distance before the regional northeasterly flow predominates. Evaluation of this condition indicates that the network is currently adequate for tracking potential effects of the SALDS on the groundwater. Recommendations include the discontinuation of ammonia, benzene, tetrahydrofuran, and acetone from the regular groundwater constituent list; designating background well 299-W8-1 as a tritium-tracking well only, and the use of quadruplicate averages of field pH, instead of a single laboratory measurement, as a permit compliance parameter.

Barnett, D.B.

1999-10-20T23:59:59.000Z

136

The Progress of Tritium Science & Technology in China  

Science Journals Connector (OSTI)

Plenary / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

Sun Ying

137

Application of Lichens for Assessment of Atmospheric Pollution by Tritium  

Science Journals Connector (OSTI)

Biology / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

A.V.Golubev; T.A.Kosheleva; Kris Surano; L.F.Belovodsky; V.F.Kuznetsova; William Hoppes; V.N.Golubeva; S.V.Mavrin

138

Update: tritium at Fermilab Fermilab Community Advisory Board  

E-Print Network [OSTI]

, Fermilab #12;2 How is tritium produced? · In nature, tritium is produced when cosmic particles hit the particles in Earth's atmosphere · Tritium is also produced in small quantities in accelerator operations. · Becomes part of water molecules like normal hydrogen · Cannot penetrate skin. · Does not accumulate

Quigg, Chris

139

Design for a fusion materials irradiation facility  

SciTech Connect (OSTI)

A fusion materials irradiation facility is required for the timely and cost-effective development of economical fusion power. Our conceptual machine provides sufficient neutron fluence for accelerated lifetime material tests in a time span of 1--2 y while producing less than 1 MW of fusion power. Neutral deuterium beams at 150 keV are injected into the center of a high-density warm tritium plasma housed in a 12-m-long cylindrical vessel. Superconducting magnets hold the plasma, which transfers the power to each end of the solenoid. The stainless steel end sections absorb the beam power and are externally cooled by high-pressure water to maintain the plasma-side wall temperature below 740 K. A service loop separates tritium from deuterium in the plasma effluent. Tritium is reinjected at each end. 9 refs., 2 figs., 2 tabs.

Walter, C.E.; Coensgen, F.H.

1988-09-02T23:59:59.000Z

140

GASFLOW analysis of a tritium leak accident  

SciTech Connect (OSTI)

The consequences of an earthquake-induced fire involving a tritium leak were analyzed using the GASFLOW computer code. Modeling features required by the analysis include ventilation boundary conditions, flow of a gas mixture in an enclosure containing obstacles, thermally induced buoyancy, and combustion phenomena.

Farman, R.F.; Fujita, R.K. [Los Alamos National Lab., NM (United States); Travis, J.R. [Engineering and Scientific software, Inc. (Untied States)

1994-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Tokamak fusion reactors with less than full tritium breeding  

SciTech Connect (OSTI)

A study of commercial, tokamak fusion reactors with tritium concentrations and tritium breeding ratios ranging from full deuterium-tritium operation to operation with no tritium breeding is presented. The design basis for these reactors is similar to those of STARFIRE and WILDCAT. Optimum operating temperatures, sizes, toroidal field strengths, and blanket/shield configurations are determined for a sequence of reactor designs spanning the range of tritium breeding, each having the same values of beta, thermal power, and first-wall heat load. Additional reactor parameters, tritium inventories and throughputs, and detailed costs are calculated for each reactor design. The disadvantages, advantages, implications, and ramifications of tritium-depleted operation are presented and discussed.

Evans, K. Jr.; Gilligan, J.G.; Jung, J.

1983-05-01T23:59:59.000Z

142

Radiological Control Programs for Special Tritium Compounds  

Broader source: Energy.gov (indexed) [DOE]

F 1325.8 F 1325.8 (08-93) United States Government Department of Energy memorandum DATE: May 11, 2006 REPLY TO EH-52:JRabovsky:3-2 135 ATTN OF: APPROVAL OF CHANGE NOTICE 1 TO DEPARTMENT OF ENERGY (DOE) SUBJECT. HANDBOOK 1184-2004, RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS TO: Dennis Kubicki, EH-24 Technical Standards Manager This memorandum forwards the subject Change Notice 1 to DOE Handbook, DOE- HDBK- 1184-2004, which has approved for publication and distribution. The change to this handbook consists of a correction to the rule of thumb, listed in Appendix A, for converting the uptake of tritium oxide into radiation dose. A factor of 1/100 was inadvertently omitted from this rule of thumb when this DOE Handbook was originally published. This change does not affect the references, is not of a technical nature, and

143

Development of Tritium Storage and Transport Vessels  

SciTech Connect (OSTI)

The purpose of this study is to develop tritium storage and transport vessels for industrial applications. Prototype tritium storage and transport vessels were designed and manufactured. Uranium and zirconium/cobalt (ZrCo) metals were selected for the storage materials. The prototype transport container for the vessel was designed on the basis of Type B transportation package standards. The transport container was composed of a steel drum, inner packing materials, and a storage vessel. A second refinement cap was installed on the prototype vessel to protect the valves on the 100 kCi vessel. The vessel is stored in a steel drum packed with a thermal barrier and a shock absorber. Structural, thermal, shielding, and confinement analyses have to be performed for this container based on Type B requirements. (authors)

Paek, S.; Lee, M.; Kim, K.R.; Ahn, D.H. [Korea Atomic Energy Research Institute, Yuseong, Daejeon (Korea, Republic of); Song, K.M.; Shon, S.H. [Korea Electric Power Research Institute, Yuseong-Gu, Daejeon (Korea, Republic of)

2008-07-01T23:59:59.000Z

144

Facility effluent monitoring plan for the 324 Facility  

SciTech Connect (OSTI)

The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements.

NONE

1994-11-01T23:59:59.000Z

145

US plan for proton accelerator to produce tritium for warheads  

Science Journals Connector (OSTI)

... construction of a huge linear proton accelerator for the production of tritium; it may be powered by excess electricity from hydroelectric sources.

David Swinbanks

1989-02-02T23:59:59.000Z

146

EFFECTS OF TRITIUM GAS EXPOSURE ON EPDM ELASTOMER  

SciTech Connect (OSTI)

Samples of four formulations of ethylene-propylene diene monomer (EPDM) elastomer were exposed to initially pure tritium gas at one atmosphere and ambient temperature for various times up to about 420 days in closed containers. Two formulations were carbon-black-filled commercial formulations, and two were the equivalent formulations without filler synthesized for this work. Tritium effects on the samples were characterized by measuring the sample volume, mass, flexibility, and dynamic mechanical properties and by noting changes in appearance. The glass transition temperature was determined by analysis of the dynamic mechanical properties. The glass transition temperature increased significantly with tritium exposure, and the unfilled formulations ceased to behave as elastomers after the longest tritium exposure. The filled formulations were more resistant to tritium exposure. Tritium exposure made all samples significantly stiffer and therefore much less able to form a reliable seal when employed as O-rings. No consistent change of volume or density was observed; there was a systematic lowering of sample mass with tritium exposure. In addition, the significant radiolytic production of gas, mainly protium (H{sub 2}) and HT, by the samples when exposed to tritium was characterized by measuring total pressure in the container at the end of each exposure and by mass spectroscopy of a gas sample at the end of each exposure. The total pressure in the containers more than doubled after {approx}420 days tritium exposure.

Clark, E.

2009-12-11T23:59:59.000Z

147

DOE - Office of Legacy Management -- Rulsion Tritium Transport...  

Office of Legacy Management (LM)

September 2007 pdficon Tritium Transport Model Comments and Responses Colorado Oil and Gas Conservation Commission Colorado Department of Public Health and Environment...

148

Ion Cyclotron Range of Frequency Heating of a Deuterium-Tritium Plasma via the Second-Harmonic Tritium Cyclotron Resonance  

Science Journals Connector (OSTI)

Experiments have been performed on the TFTR to study rf wave heating of a D-T plasma by way of the second-harmonic tritium cyclotron resonance. The addition of tritium ions to a deuterium plasma allows for absorption of the rf waves at the tritium cyclotron harmonics and by electron damping of a mode converted ion Bernstein wave. Competing mechanisms include direct electron damping and damping at the fundamental cyclotron resonance of deuterium, ? particles, and 3He ions. The contribution of each is estimated from a series of plasma discharges where various plasma parameters are varied. The majority of the rf power is found to damp on the tritium ions.

J. R. Wilson; C. E. Bush; D. Darrow; J. C. Hosea; E. F. Jaeger; R. Majeski; M. Murakami; C. K. Phillips; J. H. Rogers; G. Schilling; J. E. Stevens; E. Synakowski; G. Taylor

1995-07-31T23:59:59.000Z

149

E-Print Network 3.0 - adrenal hyperplasia tritium Sample Search...  

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

liquid scintillation analysis of tritium... which has been doped electrolytically in the bulk specimen. The tritium release showed quantitatively Source: Ecole Polytechnique,...

150

E-Print Network 3.0 - assess tritium levels Sample Search Results  

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

12, 2009 Mohamed Abdou Summary: & Shield Components 4. Tritium Processing Systems 5. Remote Maintenance Components 6. Heat Transport... (feasibility) 2. Tritium Fuel...

151

E-Print Network 3.0 - activity tritium labelled Sample Search...  

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

12, 2009 Mohamed Abdou Summary: & Shield Components 4. Tritium Processing Systems 5. Remote Maintenance Components 6. Heat Transport... (feasibility) 2. Tritium Fuel...

152

Mixed Waste Management Facility Groundwater Monitoring Report  

SciTech Connect (OSTI)

During fourth quarter 1997, eleven constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from upgradient monitoring wells. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

Chase, J.

1998-03-01T23:59:59.000Z

153

Report on use of excess M-area facilities  

SciTech Connect (OSTI)

The purpose of this report is to document the results of a study which investigated the feasibility of physically locating one or more functions that will be required to support the Accelerator Production of Tritium (APT) Project in M-Area facilities at the Savannah River Site (SRS).

Reynolds, R W; Driesen, G

1996-09-25T23:59:59.000Z

154

Effect of sweep gas composition on ionization chamber response in the BEATRIX-II tritium recovery experiment  

SciTech Connect (OSTI)

The BEATRIX-II irradiation experiment was an in situ tritium recovery experiment to evaluate the tritium release characteristics of fusion ceramic breeder materials and to characterize their stability under fast neutron irradiation to extended burnups. This is an International Energy Agency (IEA) sponsored experiment which is being carried out in the Materials Open Test Assembly of Fast Flux Test Facility (FFTF). The participants are Japan, Canada and the US The in situ tritium recovery experiment consisted of two individual in-reactor experimental assemblies (Phase I and Phase II) that were irradiated for 300 and 200 EFPD, respectively. Each experimental phase included two specimens: a thin annular specimen capable of temperature changes and a larger temperature-gradient specimen. In Phase I both specimens were Li{sub 2}O while for Phase II the temperature-change specimen consisted of Li{sub 2}O and the temperature-gradient specimen was a Li{sub 2}ZrO{sub 3} spherebed. Real-time measurements of the tritium release from the specimens during changing conditions (neutronics, temperature and sweep gas composition) were made using ion chambers. In order to correctly interpret the response of the ionization chambers it is necessary to understand the effect of changing sweep gas composition on the operation of the chambers. The purpose of this paper is to describe activities carried out to determine the effect of hydrogen additions to a helium sweep gas on the operation of these ionization chambers.

Slagle, O.D.; Hollenberg, G.W. [Pacific Northwest Lab., Richland, WA (United States); Baker, D.E. [Westinghouse Hanford Co., Richland, WA (United States)

1992-10-01T23:59:59.000Z

155

Effect of sweep gas composition on ionization chamber response in the BEATRIX-II tritium recovery experiment  

SciTech Connect (OSTI)

The BEATRIX-II irradiation experiment was an in situ tritium recovery experiment to evaluate the tritium release characteristics of fusion ceramic breeder materials and to characterize their stability under fast neutron irradiation to extended burnups. This is an International Energy Agency (IEA) sponsored experiment which is being carried out in the Materials Open Test Assembly of Fast Flux Test Facility (FFTF). The participants are Japan, Canada and the US The in situ tritium recovery experiment consisted of two individual in-reactor experimental assemblies (Phase I and Phase II) that were irradiated for 300 and 200 EFPD, respectively. Each experimental phase included two specimens: a thin annular specimen capable of temperature changes and a larger temperature-gradient specimen. In Phase I both specimens were Li[sub 2]O while for Phase II the temperature-change specimen consisted of Li[sub 2]O and the temperature-gradient specimen was a Li[sub 2]ZrO[sub 3] spherebed. Real-time measurements of the tritium release from the specimens during changing conditions (neutronics, temperature and sweep gas composition) were made using ion chambers. In order to correctly interpret the response of the ionization chambers it is necessary to understand the effect of changing sweep gas composition on the operation of the chambers. The purpose of this paper is to describe activities carried out to determine the effect of hydrogen additions to a helium sweep gas on the operation of these ionization chambers.

Slagle, O.D.; Hollenberg, G.W. (Pacific Northwest Lab., Richland, WA (United States)); Baker, D.E. (Westinghouse Hanford Co., Richland, WA (United States))

1992-10-01T23:59:59.000Z

156

Improving cryogenic deuterium–tritium implosion performance on OMEGA  

SciTech Connect (OSTI)

A flexible direct-drive target platform is used to implode cryogenic deuterium–tritium (DT) capsules on the OMEGA laser [Boehly et al., Opt. Commun. 133, 495 (1997)]. The goal of these experiments is to demonstrate ignition hydrodynamically equivalent performance where the laser drive intensity, the implosion velocity, the fuel adiabat, and the in-flight aspect ratio (IFAR) are the same as those for a 1.5-MJ target [Goncharov et al., Phys. Rev. Lett. 104, 165001 (2010)] designed to ignite on the National Ignition Facility [Hogan et al., Nucl. Fusion 41, 567 (2001)]. The results from a series of 29 cryogenic DT implosions are presented. The implosions were designed to span a broad region of design space to study target performance as a function of shell stability (adiabat) and implosion velocity. Ablation-front perturbation growth appears to limit target performance at high implosion velocities. Target outer-surface defects associated with contaminant gases in the DT fuel are identified as the dominant perturbation source at the ablation surface; performance degradation is confirmed by 2D hydrodynamic simulations that include these defects. A trend in the value of the Lawson criterion [Betti et al., Phys. Plasmas 17, 058102 (2010)] for each of the implosions in adiabat–IFAR space suggests the existence of a stability boundary that leads to ablator mixing into the hot spot for the most ignition-equivalent designs.

Sangster, T. C.; Goncharov, V. N.; Betti, R.; Radha, P. B.; Boehly, T. R.; Collins, T. J. B.; Craxton, R. S.; Delettrez, J. A.; Edgell, D. H.; Epstein, R.; Forrest, C. J.; Froula, D. H.; Glebov, Y. Yu.; Harding, D. R.; Hohenberger, M.; Hu, S. X.; Igumenshchev, I. V.; Janezic, R.; Kelly, J. H.; Kessler, T. J. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623 (United States)] [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623 (United States); and others

2013-05-15T23:59:59.000Z

157

Determination of tritium distribution in labeled compounds using EPR spectrometry  

SciTech Connect (OSTI)

Usually, the tritium distribution in a labeled compound is analyzed by T-NMR spectrometry. NMR equipment is expensive and its sensitivity is lower in comparison to EPR spectrometry. In this paper, the possibility of determining the distribution of tritium in a labeled molecule using self-radiolytic decay processes was analyzed. (authors)

Postolache, C.; Matei, L.; Georgescu, R. [Horia Hulubei, National Inst. for Physics and Nuclear Engineering IFIN HH, 407 Atomistilor street, 077125 Magurele Ilfov (Romania)

2008-07-15T23:59:59.000Z

158

The safety record at the tritium systems test assembly  

SciTech Connect (OSTI)

This work addresses an important objective of the TSTA-demonstrating that the large tritium inventories required for fusion reactors can be routinely handled, without radiation exposure to operating personnel and without significant environemtnal releases. The techniques by which TSTA has achieved low releases and personnel exposures include high-integrity primary piping systems that exclude contact between tritium and organic materials, a secondary containment system that encloses all primary tritium piping in a controlled environment, an efficient, all-purpose tritium waste-treatment plant with 100% availability, and ultrasensitive, real-time diagnostics for anticipating and preventing releases, and for detection and location of tritium leaks in a low-risk mode. 5 refs., 11 figs., 2 tabs.

Coffin, D.O.

1988-02-01T23:59:59.000Z

159

LANSCE | Facilities  

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

Isotope Production Facility (IPF) Lujan Neutron Scattering Center Materials Test Station (MTS) Proton Radiography (pRad) Ultracold Neutrons (UCN) Weapons Neutron Research Facility...

160

FACILITY SURVEY & TRANSFER Facility Survey & Transfer Overview  

Broader source: Energy.gov (indexed) [DOE]

SURVEY & TRANSFER SURVEY & TRANSFER Facility Survey & Transfer Overview Transfer Activities Checklist Pre-Survey Information Request Survey Report Content Detailed Walkdown Checklist Walkdown Checklist Clipboard Aids S & M Checklist Survey Report Example - Hot Storage Garden Survey Report Example - Tritium System Test Assembly Survey Report Example - Calutron Overview As DOE facilities become excess, many that are radioactively and/or chemically contaminated will become candidate for transfer to DOE-EM for deactivation and decommissioning. Requirements and guidance for such transfers are contained in:  DOE Order 430.1B Chg. 2, REAL PROPERTY & ASSET MANAGEMENT  DOE Guide 430.1-5, TRANSITION IMPLEMENTATION GUIDE The transfer process is illustrated in the Transfer Process figure. The purpose here is to provide examples of methods and

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Progress report on the accelerator production of tritium materials irradiation program  

SciTech Connect (OSTI)

The Accelerator Production of Tritium (APT) project is developing an accelerator and a spoliation neutron source capable of producing tritium through neutron capture on He-3. A high atomic weight target is used to produce neutrons that are then multiplied and moderated in a blanket prior to capture. Materials used in the target and blanket region of an APT facility will be subjected to several different and mixed particle radiation environments; high energy protons (1-2 GeV), protons in the 20 MeV range, high energy neutrons, and low energy neutrons, depending on position in the target and blanket. Flux levels exceed 10{sup 14}/cm{sup 2}s in some areas. The APT project is sponsoring an irradiation damage effects program that will generate the first data-base for materials exposed to high energy particles typical of spallation neutron sources. The program includes a number of candidate materials in small specimen and model component form and uses the Los Alamos Spallation Radiation Effects Facility (LASREF) at the 800 MeV, Los Alamos Neutron Science Center (LANSCE) accelerator.

Maloy, S.A.; Sommer, W.F.; Brown, R.D.; Roberts, J.E. [and others

1997-05-01T23:59:59.000Z

162

Effect of Water Formation Reaction on Tritium Release Behavior from Li4SiO4  

Science Journals Connector (OSTI)

Blanket and Breeder Materials / Proceedings of the Ninth International Conference on Tritium Science and Technology

H. Yamasaki; K. Kashimura; T. Kanazawa; K. Katayama; N. Yamashita; S. Fukada; M. Nishikawa

163

EFFECT OF TRITIUM AND DECAY HELIUM ON WELDMENT FRACTURE TOUGHNESS  

SciTech Connect (OSTI)

The fracture toughness data collected in this study are needed to assess the long-term effects of tritium and its decay product on tritium reservoirs. The results show that tritium and decay helium have negative effects on the fracture toughness properties of stainless steel and its weldments. The data and report from this study has been included in a material property database for use in tritium reservoir modeling efforts like the Technology Investment Program ''Lifecycle Engineering for Tritium Reservoirs''. A number of conclusions can be drawn from the data: (1) For unexposed Type 304L stainless steel, the fracture toughness of weldments was two to three times higher than the base metal toughness. (2) Tritium exposure lowered the fracture toughness properties of both base metals and weldments. This was characterized by lower J{sub Q} values and lower J-da curves. (3) Tritium-exposed-and-aged base metals and weldments had lower fracture toughness values than unexposed ones but still retained good toughness properties.

Morgan, M; Scott West, S; Michael Tosten, M

2006-09-26T23:59:59.000Z

164

Tritium activities in Canada supporting CANDU{sup R} nuclear power reactors  

SciTech Connect (OSTI)

An overview of the various Canadian tritium research and operational activities supporting the development, refurbishment and operation of CANDU{sup R} nuclear power reactors is presented. These activities encompass tritium health and safety, tritium in the environment, tritium interaction with materials, and tritium processing, and relate to both supporting R and D advances as well as operational best practices. The collective results of these activities contribute to our goals of improving worker and public safety, and operational efficiency. (authors)

Miller, J. M. [AECL, Chalk River Laboratories, Chalk River, ON K0J 1J0 (Canada)

2008-07-15T23:59:59.000Z

165

Tritium Superpermeability: Experimental Investigation and Simulation of Tritium Recirculation in 'Prometheus' Setup  

SciTech Connect (OSTI)

The superpermeability phenomenon was suggested to use in fusion machines to separate the fuel mixture from helium ashes, to arrange in-vessel fuel recirculation contours and effective evacuation of fuel mixture out of machine exhaust. To develop this technology and to simulate tritium recirculation in RFNC-VNIIEF at the 'Prometheus' setup the experiments on superpermeation of hydrogen isotopes through metal membrane were realized.The results of experiments on superpermeation of hydrogen isotopes through cylindrical niobium membrane are presented. As the experiment has shown, membrane pumping rate is inversely proportional to square root of isotope mass and amount to 2.5 l/cm{sup 2}s for protium, 1.8 l/cm{sup 2}s for deuterium and 1.5 l/cm{sup 2}s for tritium. The possibility of effective pumping, separation of hydrogen isotopes from helium and residual gas, compression and recuperation of hydrogen isotopes by means of superpermeable membrane was demonstrated. It follows from results that the separation of D/T from He with employment of the techniques of superpermeable membranes might reduce the total amount of tritium in fuel cycle and substantially enhance the resource of cryogenic pumps evacuating helium.

Musyaev, R.K. [Russian Federal Nuclear Center-All-Russian Research Institute of Experimental Physics (Russian Federation); Lebedev, B.S. [Russian Federal Nuclear Center-All-Russian Research Institute of Experimental Physics (Russian Federation); Grishechkin, S.K. [Russian Federal Nuclear Center-All-Russian Research Institute of Experimental Physics (Russian Federation); Yukhimchuk, A.A. [Russian Federal Nuclear Center-All-Russian Research Institute of Experimental Physics (Russian Federation); Busnyuk, A.A [St.-Peterburg State University of Telecommunications (Russian Federation); Notkin, M.E. [St.-Peterburg State University of Telecommunications (Russian Federation); Samartsev, A.A. [St.-Peterburg State University of Telecommunications (Russian Federation); Livshits, A.I. [St.-Peterburg State University of Telecommunications (Russian Federation)

2005-07-15T23:59:59.000Z

166

Radiological Control Programs for Special Tritium Compounds  

Broader source: Energy.gov (indexed) [DOE]

84-2004 84-2004 SEPTEMBER 2004 CHANGE NOTICE NO. 1 Date June 2006 DOE HANDBOOK RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS U.S. Department of Energy AREA OCSH Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Table of Changes Page Change 67 (near bottom) In row 1, column 2 of the table titled "dosimetric properties" 6 mrem was changed to 6 x 10 -2 mrem Available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techstds/ DOE-HDBK-1184-2004 iii Foreword The Department of Energy (DOE) and its predecessor agencies have undertaken a wide variety

167

Ignition of deuterium-tritium fuel targets  

DOE Patents [OSTI]

Disclosed is a method of igniting a deuterium-tritium ICF fuel target to obtain fuel burn in which the fuel target initially includes a hollow spherical shell having a frozen layer of DT material at substantially uniform thickness and cryogenic temperature around the interior surface of the shell. The target is permitted to free-fall through a target chamber having walls heated by successive target ignitions, so that the target is uniformly heated during free-fall to at least partially melt the frozen fuel layer and form a liquid single-phase layer or a mixed liquid/solid bi-phase layer of substantially uniform thickness around the interior shell surface. The falling target is then illuminated from exteriorly of the chamber while the fuel layer is at substantially uniformly single or bi-phase so as to ignite the fuel layer and release energy therefrom. 5 figures.

Musinski, D.L.; Mruzek, M.T.

1991-08-27T23:59:59.000Z

168

Savannah River Tritium Enterprise exceeds productivity savings goals for  

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

Tritium Enterprise exceeds productivity savings goals for Tritium Enterprise exceeds productivity savings goals for FY13 | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Savannah River Tritium Enterprise exceeds productivity savings ... Savannah River Tritium Enterprise exceeds productivity savings goals for FY13 Posted By Office of Public Affairs

169

Savannah River Tritium Enterprise exceeds productivity savings goals for  

National Nuclear Security Administration (NNSA)

Tritium Enterprise exceeds productivity savings goals for Tritium Enterprise exceeds productivity savings goals for FY13 | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Savannah River Tritium Enterprise exceeds productivity savings ... Savannah River Tritium Enterprise exceeds productivity savings goals for FY13 Posted By Office of Public Affairs

170

Assessment of tritium in the Savannah River Site environment  

SciTech Connect (OSTI)

This report is the first revision to a series of reports on radionuclides inn the SRS environment. Tritium was chosen as the first radionuclide in the series because the calculations used to assess the dose to the offsite population from SRS releases indicate that the dose due to tritium, through of small consequence, is one of the most important the radionuclides. This was recognized early in the site operation, and extensive measurements of tritium in the atmosphere, surface water, and ground water exist due to the effort of the Environmental Monitoring Section. In addition, research into the transport and fate of tritium in the environment has been supported at the SRS by both the local Department of Energy (DOE) Office and DOE`s Office of Health and Environmental Research.

Carlton, W.H.; Murphy, C.E. Jr.; Bauer, L.R. [and others

1993-10-01T23:59:59.000Z

171

System design for disposal of tritium at TFTR  

SciTech Connect (OSTI)

The Tokamak Fusion Test Reactor (TFTR) has cleanup systems which convert tritium gas to the oxide form and absorb it on molecular sieve beds. These beds are regenerated by transferring their moisture content to disposable sieve beds. Preparing this sieve for disposal can be awkward and hazardous. Monitoring the tritium and moisture content of the disposable sieve is not straightforward. Modifications to the regeneration system at the TFTR are being made to address these concerns and others relating to maintainability.

Tuohy, J.M.; Cherdack, R.; Lacy, N.H.

1988-09-01T23:59:59.000Z

172

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1996-10-24T23:59:59.000Z

173

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1995-11-16T23:59:59.000Z

174

Certified Facilities  

Broader source: Energy.gov [DOE]

Industrial Leaders: The industrial facilities shown below are among the first to earn certification for Superior Energy Performance® (SEP™).

175

Low-energy beta spectroscopy using pin diodes to monitor tritium surface contamination  

SciTech Connect (OSTI)

We show that tritium betas emitted from a surface can be counted using a pin photodiode as a solid state charged particle detector. Furthermore, we show that the range of tritium betas through air is sufficient to allow measurement of tritium on samples in air by this method. These two findings make possible a new method to survey tritium surface contamination which has advantages over existing methods. We have built and tested several prototype instruments which use this method to measure tritium surface contamination, including a compact portable unit. The design of these instruments and results from tests and calibrations are described. Potential applications of this new method to monitor tritium are discussed.

Wampler, W.R.; Doyle, B.L.

1994-06-01T23:59:59.000Z

176

Tritium plasma experiment: Parameters and potentials for fusion plasma-wall interaction studies  

SciTech Connect (OSTI)

The tritium plasma experiment (TPE) is a unique facility devoted to experiments on the behavior of deuterium/tritium in toxic (e.g., beryllium) and radioactive materials for fusion plasma-wall interaction studies. A Langmuir probe was added to the system to characterize the plasma conditions in TPE. With this new diagnostic, we found the achievable electron temperature ranged from 5.0 to 10.0 eV, the electron density varied from 5.0 x 10{sup 16} to 2.5 x 10{sup 18} m{sup -3}, and the ion flux density varied between 5.0 x 10{sup 20} to 2.5 x 10{sup 22} m{sup -2} s{sup -1} along the centerline of the plasma. A comparison of these plasma parameters with the conditions expected for the plasma facing components (PFCs) in ITER shows that TPE is capable of achieving most ({approx}800 m{sup 2} of 850 m{sup 2} total PFCs area) of the expected ion flux density and electron density conditions.

Shimada, Masashi; Sharpe, J. Phillip [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, Idaho 83415 (United States); Kolasinski, Robert D.; Causey, Rion A. [Hydrogen and Metallurgical Science Department, Sandia National Laboratories, Livermore, California 94551 (United States)

2011-08-15T23:59:59.000Z

177

Groundwater Monitoring and Tritium-Tracking Plan for the 200 Area State-Approved Land Disposal Site  

SciTech Connect (OSTI)

The 200 Area State-Approved Land Disposal Site (SALDS) is a drainfield which receives treated wastewater, occasionally containing high levels of tritium from treatment of Hanford Site liquid wastes. Only the SALDS proximal wells (699-48-77A, 699-48-77C, and 699-48-77D) have been affected by tritium from the facility thus far; the highest activity observed (2.1E+6 pCi/L) occurred in well 699-48-77D in February 1998. Analytical results of groundwater geochemistry since groundwater monitoring began at the SALDS indicate that all constituents with permit enforcement limits have been below those limits with the exception of one measurement of total dissolved solids (TDS) in 1996. The revised groundwater monitoring sampling and analysis plan eliminates chloroform, acetone, tetrahydrofuran, benzene, and ammonia as constituents. Replicate field measurements will replace laboratory measurements of pH for compliance purposes. A deep companion well to well 699-51-75 will be monitored for tritium deeper in the uppermost aquifer.

Barnett, D. Brent

2000-08-31T23:59:59.000Z

178

A neutron poison tritium breeding controller applied to a water cooled fusion reactor model  

Science Journals Connector (OSTI)

Abstract The generation of tritium in sufficient quantities is an absolute requirement for a next step fusion device such as DEMO due to the scarcity of tritium sources. Although the production of sufficient quantities of tritium will be one of the main challenges for DEMO, within an energy economy featuring several fusion power plants the active control of tritium production may be required in order to manage surplus tritium inventories at power plant sites. The primary reason for controlling the tritium inventory in such an economy would therefore be to minimise the risk and storage costs associated with large quantities of surplus tritium. In order to ensure that enough tritium will be produced in a reactor which contains a solid tritium breeder, over the reactor's lifetime, the tritium breeding rate at the beginning of its lifetime is relatively high and reduces over time. This causes a large surplus tritium inventory to build up until approximately halfway through the lifetime of the blanket, when the inventory begins to decrease. This surplus tritium inventory could exceed several tens of kilograms of tritium, impacting on possible safety and licensing conditions that may exist. This paper describes a possible solution to the surplus tritium inventory problem that involves neutron poison injection into the coolant, which is managed with a tritium breeding controller. A simple PID controller and is used to manage the injection of the neutron absorbing compounds into the water coolant of a stratified blanket model, depending on the difference between the required tritium excess inventory and the measured tritium excess inventory. The compounds effectively reduce the amount of low energy neutrons available to react with lithium compounds, thus reducing the tritium breeding ratio. This controller reduces the amount of tritium being produced at the start of the reactor's lifetime and increases the rate of tritium production towards the end of its lifetime. Thus, a relatively stable tritium production level may be maintained, allowing the control system to minimize the stored tritium with obvious safety benefits. The FATI code (Fusion Activation and Transport Interface) will be used to perform the tritium breeding and controller calculations.

L.W.G. Morgan; L.W. Packer

2014-01-01T23:59:59.000Z

179

Tritium minority heating with mode conversion of fast waves  

SciTech Connect (OSTI)

A new ion-heating scenario in tokamak plasmas, based on cyclotron damping of ion Bernstein waves (IBWs) by tritium minority at the first ion cyclotron harmonic (i.e., omega=2OMEGA{sub cT}), is proposed. The IBWs are coupled by mode conversion of fast magnetosonic waves in a D-H(T) (tritium minority in hydrogen-deuterium) plasma. The mode conversion layer is located near the center of the plasma column as well as the resonant layer of the tritium minority. A possible scenario for the JET (Joint European Torus) tokamak [J. Wesson, JET Report No. 99, 1999], based on the present idea, has been analyzed by means of the numerical codes TORIC and SSFPQL (toroidal ion cyclotron and steady state Fokker-Planck quasilinear) [M. Brambilla, Nucl. Fusion 34, 1121 (1994); Plasma Phys. Controlled Fusion 41, 1 (1999)]. As a result, tritium ions are accelerated up to energies close to the peak value of the DT cross section and steady state breakeven condition (Qapprox =1.3) can be reached with 25% minority tritium concentration.

Castaldo, Carmine; Cardinali, Alessandro [Euratom ENEA Association, Via Enrico Fermi 45, CP65, 00044 Frascati (Rome) (Italy)

2010-07-15T23:59:59.000Z

180

RADIOLYTIC GAS PRODUCTION RATES OF POLYMERS EXPOSED TO TRITIUM GAS  

SciTech Connect (OSTI)

Data from previous reports on studies of polymers exposed to tritium gas is further analyzed to estimate rates of radiolytic gas production. Also, graphs of gas release during tritium exposure from ultrahigh molecular weight polyethylene (UHMW-PE), polytetrafluoroethylene (PTFE, a trade name is Teflon®), and Vespel® polyimide are re-plotted as moles of gas as a function of time, which is consistent with a later study of tritium effects on various formulations of the elastomer ethylene-propylene-diene monomer (EPDM). These gas production rate estimates may be useful while considering using these polymers in tritium processing systems. These rates are valid at least for the longest exposure times for each material, two years for UHMW-PE, PTFE, and Vespel®, and fourteen months for filled and unfilled EPDM. Note that the production “rate” for Vespel® is a quantity of H{sub 2} produced during a single exposure to tritium, independent of length of time. The larger production rate per unit mass for unfilled EPDM results from the lack of filler- the carbon black in filled EPDM does not produce H{sub 2} or HT. This is one aspect of how inert fillers reduce the effects of ionizing radiation on polymers.

Clark, E.

2013-08-31T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Science Facilities  

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

Electron Microscopy Lab Ion Beam Materials Lab Matter-Radiation Interactions in Extremes (MaRIE) Proton Radiography Trident Laser Facility LOOK INTO LANL - highlights...

182

EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor  

Broader source: Energy.gov (indexed) [DOE]

8-S1: Production of Tritium in a Commercial Light Water 8-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement Summary This Supplemental EIS updates the environmental analyses in DOE's 1999 EIS for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS). The CLWR EIS addressed the production of tritium in Tennessee Valley Authority reactors in Tennessee using tritium-producing burnable absorber rods. Public Comment Opportunities No public comment opportunities at this time. Documents Available for Download September 28, 2011 EIS-0288-S1: Notice of Intent to Prepare a Supplemental Environmental

183

Continuous production of tritium in an isotope-production reactor with a separate circulation system  

DOE Patents [OSTI]

A method is described for producing tritium in a fast breeder reactor cooled with liquid metal. Lithium is allowed to flow through the reactor in separate loops in order to facilitate the production and removal of tritium.

Cawley, W.E.; Omberg, R.P.

1982-08-19T23:59:59.000Z

184

Tritium separation from heavy water by electrolysis with solid polymer electrolyte  

Science Journals Connector (OSTI)

A tritium separation from heavy water by electrolysis using a solid polymer electrode layer was ... made of stainless steel or nickel. The electrolysis was performed for 1 hour at 5, ... tritium separation factor...

Y. Ogata; Y. Sakuma; N. Ohtani; M. Kotaka

2003-03-01T23:59:59.000Z

185

Tritium concentrations of the deep sea-water in the Japan Sea and the Pacific Ocean  

Science Journals Connector (OSTI)

Tritium concentrations were determined for sea-water samples collected from the Japan Sea and the Pacific Ocean. In the Japan Sea, it was ... place. On the other hand, in the Pacific Ocean, the tritium concentrat...

T. Kajì; N. Momoshima; Y. Takashima

1988-08-10T23:59:59.000Z

186

Operation Experience on Safety System of Tritium Process Laboratory in Japan Atomic Energy Research Institute  

Science Journals Connector (OSTI)

Design, Operation, and Maintenance of Tritium System / Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995

Masayuki Yamada; Mikio Enoeda; Takashi Honma; Takumi Hayashi; Yuji Matsuda; Kenji Okuno

187

Determination of transport parameters from coincident chloride and tritium plumes at the Idaho National Engineering Laboratory  

E-Print Network [OSTI]

wells from the ICPP tritium plume. 41 42 Sets of simulated tritium concentrations for selected wells. 44 Insensitivity of steady-state concentrations to the longitudinal dispersivity nx for an ideal radionuclide plume... the ICPP chloride plume. Simulated contour map of the ICPP chloride plume. 34 38 12 Iteration diagram for Y source size versus the trans- verse dispersivity ny from the ICPP tritium plume. Total monthly quantities of (a) tritium and (b) waste- water...

Fryar, Alan Ernest

2012-06-07T23:59:59.000Z

188

Behavior of Tritium in the Mouse Body After Oral Intake and Estimation of the Absorbed Dose  

Science Journals Connector (OSTI)

Biology / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

Masahiro Saito

189

TRITIUM EFFECTS ON DYNAMIC MECHANICAL PROPERTIES OF POLYMERIC MATERIALS  

SciTech Connect (OSTI)

Dynamic mechanical analysis has been used to characterize the effects of tritium gas (initially 1 atm. pressure, ambient temperature) exposure over times up to 2.3 years on several thermoplastics-ultrahigh molecular weight polyethylene (UHMW-PE), polytetrafluoroethylene (PTFE), and Vespel{reg_sign} polyimide, and on several formulations of elastomers based on ethylene propylene diene monomer (EPDM). Tritium exposure stiffened the elastic modulus of UHMW-PE up to about 1 year and then softened it, and reduced the viscous response monotonically with time. PTFE initially stiffened, however the samples became too weak to handle after nine months exposure. The dynamic properties of Vespel{reg_sign} were not affected. The glass transition temperature of the EPDM formulations increased approximately 4 C. following three months tritium exposure.

Clark, E

2008-11-12T23:59:59.000Z

190

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

2005-12-22T23:59:59.000Z

191

PPPL-2878 UC-426 February 1993 Tritium Diagnostics by Balmer-alpha Emission  

E-Print Network [OSTI]

PPPL-2878 UC-426 February 1993 Tritium Diagnostics by Balmer-alpha Emission C H Skinner, A T Ramsey emission from tritium in a plasma may be distinguished from deuterium emission by a small isotope shift. A diagnostic system to measure tritium Balmer-alpha emission from the plasma edge has been installed on TFTR

192

Detection of tritium sorption on four soil materials Yanguo Teng a,b  

E-Print Network [OSTI]

Detection of tritium sorption on four soil materials Yanguo Teng a,b , Rui Zuo a,b,*, Jinsheng Wang, it is important to understand the sorption behavior of tritium on soils. In this study, batch tests were carried.2 mL/g for the four types of soil samples. This relatively modest sorption of tritium in soils needs

Hu, Qinhong "Max"

193

Mobile Facility  

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

Facility Facility AMF Information Science Architecture Baseline Instruments AMF1 AMF2 AMF3 Data Operations AMF Fact Sheet Images Contacts AMF Deployments Hyytiälä, Finland, 2014 Manacapuru, Brazil, 2014 Oliktok Point, Alaska, 2013 Los Angeles, California, to Honolulu, Hawaii, 2012 Cape Cod, Massachusetts, 2012 Gan Island, Maldives, 2011 Ganges Valley, India, 2011 Steamboat Springs, Colorado, 2010 Graciosa Island, Azores, 2009-2010 Shouxian, China, 2008 Black Forest, Germany, 2007 Niamey, Niger, 2006 Point Reyes, California, 2005 Mobile Facilities Pictured here in Gan, the second mobile facility is configured in a standard layout. Pictured here in Gan, the second mobile facility is configured in a standard layout. To explore science questions beyond those addressed by ARM's fixed sites at

194

Comparison of the recently proposed super-Marx generator approach to thermonuclear ignition with the deuterium-tritium laser fusion-fission hybrid concept by the Lawrence Livermore National Laboratory  

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

The recently proposed super-Marx generator pure deuterium microdetonation ignition concept is compared to the Lawrence Livermore National Ignition Facility (NIF) Laser deuterium-tritium fusion-fission hybrid concept (LIFE). In a super-Marx generator, a large number of ordinary Marx generators charge up a much larger second stage ultrahigh voltage Marx generator from which for the ignition of a pure deuterium microexplosion an intense GeV ion beam can be extracted. Typical examples of the LIFE concept are a fusion gain of 30 and a fission gain of 10, making up a total gain of 300, with about ten times more energy released into fission as compared to fusion. This means the substantial release of fission products, as in fissionless pure fission reactors. In the super-Marx approach for the ignition of pure deuterium microdetonation, a gain of the same magnitude can, in theory, be reached. If feasible, the super-Marx generator deuterium ignition approach would make lasers obsolete as a means for the ignition of thermonuclear microexplosions.

Winterberg, F.

2009-10-29T23:59:59.000Z

195

A tritium compatible plasma exhaust system for a large tokamak  

SciTech Connect (OSTI)

A tritium compatible system has been designed to handle the exhaust gas produced by neutral beam operations in the Tokamak Fusion Test Reactor (TFTR). The system transfers gas highly concentrated in hydrogen isotopes to intermediate storage and final shipping containers using a combination of dry pumping and gettering. Details are given for functional and design requirements, component characteristics, and estimated system performance. Process flow and equipment arrangements are diagrammed, and various modes of operation are illustrated. The system is designed to provide safe handling of the tritiated exhaust and the rapid tritium turnaround necessary for operation with TFTR's small on-site inventory.

Rossmassler, R.L.; Lamarche, P.H.; Cherdack, R.

1988-09-01T23:59:59.000Z

196

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

2002-05-20T23:59:59.000Z

197

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

2000-11-20T23:59:59.000Z

198

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

2005-12-22T23:59:59.000Z

199

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

2013-06-21T23:59:59.000Z

200

Safety analysis report for packaging: the ORNL DOT specification 6M - tritium trap package. [Tritium absorbed as solid uranium tritide in depleted uranium trap  

SciTech Connect (OSTI)

The ORNL DOT Specification 6M--Tritium Trap Package was fabricated at the Oak Ridge National Laboratory (ORNL) for the transport of Type B quantities of tritium as solid uranium tritide. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container, a drop test performed by the ORNL Operations Division, and International Atomic Energy Agency (IAEA) approvals on a similar tritium transport container. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of Type B quantities of tritium. 4 references, 8 figures.

DeVore, J.R.

1984-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Conditioning Matrices of Liquid Scintillation Cocktails Contaminated with Tritium  

SciTech Connect (OSTI)

This paper describes a viable solidification technology to convert the liquid scintillation cocktail into a stable form which minimizes the probability to release tritium in the environment.This radioactive waste type is generated by the radio-chemical analysis lab of a CANDU nuclear power plant.

Dianu, Magdalena [Institute for Nuclear Research (Romania)

2005-07-15T23:59:59.000Z

202

EIS-0270: Accelerator Production of Tritium at the Savannah River Site |  

Broader source: Energy.gov (indexed) [DOE]

EIS-0270: Accelerator Production of Tritium at the Savannah River EIS-0270: Accelerator Production of Tritium at the Savannah River Site EIS-0270: Accelerator Production of Tritium at the Savannah River Site Summary This EIS evaluates the potential environmental impact of a proposal to construct and operate an Accelerator for the Production of Tritium at the Savannah River Site. Public Comment Opportunities None available at this time. Documents Available for Download May 14, 1999 EIS-0288: Consolidated Record of Decision (EIS-0270 & EIS-0271) Tritium Supply and Recycling March 1, 1999 EIS-0270: Final Environmental Impact Statement Accelerator Production of Tritium at the Savannah River Site September 5, 1996 EIS-0270: Notice of Intent to Prepare an Environmental Impact Statement Construction and Operation of an Accelerator for the Production of Tritium

203

Advanced nuclear reactors and tritium impacts. Modeling the aquatic pathway  

Science Journals Connector (OSTI)

The effective contribution of nuclear energy will depend on various factors related to economics, safety, public acceptance and sustainability. To assure, however, the nuclear energy development, reactor accident impacts, as Fukushima, must be evaluated in a predictive way. Environmental assessment models are used for evaluating the radiological impact of potential releases of radionuclides from nuclear reactors to the environment. It is important to evaluate, to the extent possible, the reliability of the predictions of such models, by comparing with measured values in the environment or by comparing with the predictions of other models. Tritium has a complex environmental behavior once released into the environment. It is essential to establish reference scenarios to allow the simulation of tritium aquatic pathway subsequent to accidental releases. For this purpose, two scenarios for seawater circulation were analyzed by hydrodynamic modeling. An inverse modeling procedure was successfully applied to estimate tide elevations on the borders, which are based on applying the harmonic constants and using the same overestimation percentage produced by model results to correct the border values. Simulations of validated model for postulated accidental releases of tritium inventory from heavy water reactors, whose doses could be relevant, were presented here. It was observed differences between the two scenarios for the transport modeling that were caused by the removal of large volume of polluted waters from the accident site and its dilution in the discharge area, which has minor tritium concentrations. Moreover, the processes involved in the dynamic transfer of tritium in the environment were analyzed in dependence on the environmental conditions of tropical coastal ecosystem.

Francisco Fernando Lamego Simões Filho; Abner Duarte Soares; André da Silva Aguiar; Celso Marcelo Franklin Lapa; Antonio Carlos Ferreira Guimarães

2013-01-01T23:59:59.000Z

204

Mixed Waste Management Facility (MWMF) groundwater monitoring report. Fourth quarter 1992 and 1992 summary  

SciTech Connect (OSTI)

During fourth quarter 1992, nine constituents exceeded final Primary Drinking Water Standards (PDWS) in one or more groundwater samples from monitoring wells at the Mixed Waste Management Facility (MWMF) and adjacent facilities. As in previous quarters, tritium and trichloroethylene were the most widespread constituents. Fifty-seven (48%) of the 120 monitoring wells, contained elevated tritium activities, and 23 (19%) contained elevated trichloroethylene concentrations. Total alpha-emitting radium, tetrachloroethylene, chloroethene, cadmium, 1,1-dichloroethylene, lead, or nonvolatile beta levels exceeded standards in one or more wells. During 1992, elevated levels of 13 constituents were found in one or more of 80 of the 120 groundwater monitoring wells (67%) at the MWMF and adjacent facilities. Tritium and trichloroethylene exceeded their final PDWS more frequently and more consistently than did other constituents. Tritium activity exceeded its final PDWS m 67 wells and trichloroethylene was. elevated in 28 wells. Lead, tetrachloroethylene, total alpha-emitting radium, gross alpha, cadmium, chloroethene, 1,1-dichloroethylene 1,2-dichloroethane, mercury, or nitrate exceeded standards in one or more wells during the year. Nonvolatile beta exceeded its drinking water screening level in 3 wells during the year.

Not Available

1993-03-01T23:59:59.000Z

205

3HE RECOVERY FROM A TRITIUM-AGED LANA75 SAMPLE  

SciTech Connect (OSTI)

{sup 3}He recovery is a topic of recent interest. One potential recovery source is from metal hydride materials once used to store tritium, as the decay product, {sup 3}He, is primarily trapped in the metal lattice, usually in bubbles, with such materials. In 2001, a Tritium Exposure Program (TEP) sample known as LANA75-SP1 was retired and the material was removed from the test cell and stored. Subsequently scoping temperature programmed desorption (TPD) experiments were conducted on that material to see what it might take to drive out He and residual H isotopes (the heel). Two experiments consisted of heating the sample in the presence of an excess of tin (the so-called Sn fusion experiment), and one was a simple TPD with no additives. Prior data on the so-called '21-month bed' material in the 1980's had produced {approx}21 cc of gas per gram of a LANA30 material (LaNi4.7Al0.3), with approximately 67% of that being {sup 3}He and the rest being D{sub 2} (Fig.3). However, the material had to be heated in excess of 850 C to obtain that level. Heating to less produced approximately half that amount of gas. The data also showed that {sup 3}He was released at different temperatures than the residual hydrogen isotopes. Unfortunately this implies full {sup 3}He recovery will be a difficult process. Therefore, it seemed advisable to attempt to extract as much information from the 3 scoping experiments from 2001-2 as possible.

Shanahan, K.

2010-12-01T23:59:59.000Z

206

Measurements of collective fuel velocities in deuterium-tritium exploding pusher and cryogenically layered deuterium-tritium implosions on the NIF  

E-Print Network [OSTI]

Science and Fusion Center, Cambridge, Massachusetts 02139, USA 2 Lawrence Livermore National Laboratory layered deuterium-tritium implosions on the NIF M. Gatu Johnson, D. T. Casey, J. A. Frenje, C.-K. Li, F. H layered deuterium-tritium implosions on the NIF M. Gatu Johnson,1,a) D. T. Casey,1,b) J. A. Frenje,1 C

207

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

1995-10-13T23:59:59.000Z

208

Facility Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

2012-12-04T23:59:59.000Z

209

FINITE ELEMENT ANALYSIS OF BULK TRITIUM SHIPPING PACKAGE  

SciTech Connect (OSTI)

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

Jordan, J.

2010-06-02T23:59:59.000Z

210

Silicon carbide tritium permeation barrier for steel structural components.  

SciTech Connect (OSTI)

Chemical vapor deposited (CVD) silicon carbide (SiC) has superior resistance to tritium permeation even after irradiation. Prior work has shown Ultrametfoam to be forgiving when bonded to substrates with large CTE differences. The technical objectives are: (1) Evaluate foams of vanadium, niobium and molybdenum metals and SiC for CTE mitigation between a dense SiC barrier and steel structure; (2) Thermostructural modeling of SiC TPB/Ultramet foam/ferritic steel architecture; (3) Evaluate deuterium permeation of chemical vapor deposited (CVD) SiC; (4) D testing involved construction of a new higher temperature (> 1000 C) permeation testing system and development of improved sealing techniques; (5) Fabricate prototype tube similar to that shown with dimensions of 7cm {theta} and 35cm long; and (6) Tritium and hermeticity testing of prototype tube.

Causey, Rion A. (Sandia National Laboratories, Livermore, CA); Garde, Joseph Maurico; Buchenauer, Dean A. (Sandia National Laboratories, Livermore, CA); Calderoni, Pattrick (Idaho National Laboratory); Holschuh, Thomas, Jr.; Youchison, Dennis Lee; Wright, Matt; Kolasinski, Robert D. (Sandia National Laboratories, Livermore, CA)

2010-09-01T23:59:59.000Z

211

Progress report on the Los Alamos tritium beta decay experiment  

SciTech Connect (OSTI)

Measurements near the endpoint of the tritium beta-decay spectrum using a gaseous molecular tritium source yield an essentially model-independent upper limit of 27 eV on the /ovr ..nu..//sub e/ mass at the 95% confidence level. Since demonstrating from this initial measurement the successful operation of a gaseous source based system, most of our effort has been concentrated towards the upgrade and optimization of the experimental apparatus. The emphasis of this work has been to eliminate or further reduce effects that generate systematic errors. Based on realistic projections from our initial measurement, an ultimate sensitivity to neutrino mass of 10 eV is expected. 12 refs., 1 fig.

Wilkerson, J.F.; Bowles, T.J.; Knapp, D.A.; Robertson, R.G.H.; Wark, D.L.

1988-01-01T23:59:59.000Z

212

Elastic Electron Scattering from Tritium and Helium-3  

DOE R&D Accomplishments [OSTI]

The mirror nuclei of tritium and helium-3 have been studied by the method of elastic electron scattering. Absolute cross sections have been measured for incident electron energies in the range 110 - 690 MeV at scattering angles lying between 40 degrees and 135 degrees in this energy range. The data have been interpreted in a straightforward manner and form factors are given for the distributions of charge and magnetic moment in the two nuclei over a range of four-momentum transfer squared 1.0 - 8.0 F{sup -2}. Model-independent radii of the charge and magnetic moment distributions are given and an attempt is made to deduce form factors describing the spatial distribution of the protons in tritium and helium-3.

Collard, H.; Hofstadter, R.; Hughes, E. B.; Johansson, A.; Yearian, M. R.; Day, R. B.; Wagner, R. T.

1964-10-00T23:59:59.000Z

213

IN-LINE CHEMICAL SENSOR DEPLOYMENT IN A TRITIUM PLANT  

SciTech Connect (OSTI)

The Savannah River Tritium Plant (TP) relies on well understood but aging sensor technology for process gas analysis. Though new sensor technologies have been brought to various readiness levels, the TP has been reluctant to install technologies that have not been tested in tritium service. This gap between sensor technology development and incorporating new technologies into practical applications demonstrates fundamental challenges that exist when transitioning from status quo to state-of-the-art in an extreme environment such as a tritium plant. These challenges stem from three root obstacles: 1) The need for a comprehensive assessment of process sensing needs and requirements; 2) The lack of a pick-list of process-compatible sensor technologies; and 3) The need to test technologies in a tritium-contaminated process environment without risking production. At Savannah River, these issues are being addressed in a two phase project. In the first phase, TP sensing requirements were determined by a team of process experts. Meanwhile, Savannah River National Laboratory sensor experts identified candidate technologies and related them to the TP processing requirements. The resulting roadmap links the candidate technologies to actual plant needs. To provide accurate assessments of how a candidate sensor technology would perform in a contaminated process environment, an instrument demonstration station was established within a TP glove box. This station was fabricated to TP process requirements and designed to handle high activity samples. The combination of roadmap and demonstration station provides the following assets: ? Creates a partnership between the process engineers and researchers for sensor selection, maturation, and insertion, ? Selects the right sensors for process conditions ? Provides a means for safely inserting new sensor technology into the process without risking production, and ? Provides a means to evaluate off normal occurrences where and when they occur. This paper discusses the process to identify and demonstrate new sensor technologies for the Savannah River TP.

Tovo, L.; Wright, J.; Torres, R.; Peters, B.

2013-10-02T23:59:59.000Z

214

Dose reconstruction for an occupational cohort at the Savannah River nuclear facility: evaluation of a hybrid method  

Science Journals Connector (OSTI)

......tritium dose estimation methods, including International...workers at a nuclear fuels production facility. Am. J...evaluation of a hybrid method. | The Savannah River...radioactive isotope of hydrogen. The purpose of the...matrix. The proposed method is unique in that along......

Ghassan Hamra; Leena A. Nylander-French; David Richardson

2008-08-01T23:59:59.000Z

215

EIS-0288: Production of Tritium in a Commercial Light Water Reactor |  

Broader source: Energy.gov (indexed) [DOE]

288: Production of Tritium in a Commercial Light Water Reactor 288: Production of Tritium in a Commercial Light Water Reactor EIS-0288: Production of Tritium in a Commercial Light Water Reactor SUMMARY This Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS) evaluates the environmental impacts associated with producing tritium at one or more of the following five CLWRs: (1) Watts Bar Nuclear Plant Unit 1 (Spring City, Tennessee); (2) Sequoyah Nuclear Plant Unit 1 (Soddy Daisy, Tennessee); (3) Sequoyah Nuclear Plant Unit 2 (Soddy Daisy, Tennessee); (4) Bellefonte Nuclear Plant Unit 1 (Hollywood, Alabama); and (5) Bellefonte Nuclear Plant Unit 2 (Hollywood, Alabama). Specifically, this EIS analyzes the potential environmental impacts associated with fabricating tritium-producing

216

from Savannah River Nuclear Solutions, LLC NEWS Savannah River Tritium Enterprise Achieves High Marks for  

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

Tritium Enterprise Achieves High Marks for Tritium Enterprise Achieves High Marks for Support to Nation's Security Fiscal Year 2012 Performance Prepares Enterprise for Continued Service AIKEN, S.C. (February 7, 2013) - The National Nuclear Security Administration (NNSA) has rated the Savannah River Tritium Enterprise's overall Fiscal Year 2012 performance as "excel- lent," meaning that the Savannah River Site's tritium-related work has once again success- fully met and exceeded NNSA's Defense Programs goals. The Savannah River Tritium Enterprise (SRTE), which is managed for NNSA by Savannah River Nuclear Solutions (SRNS), earned the rating for its successful performance of the four missions it carries out in support of the nation's security: tritium supply, nuclear stockpile maintenance,

217

Fermilab | Tritium at Fermilab | Steps taken to reduce the amount of  

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

Steps taken to reduce the amount of tritium Steps taken to reduce the amount of tritium Actions taken in response to the detection of low levels of tritium in surface and sewer water in November 2005 What did we detect in November 2005? In November 2005, for the first time in the then-35-year history of our environmental monitoring program at Fermilab, we detected low levels of tritium in a stream leaving the Fermilab site, and in the sanitary sewers that pump water to the Batavia Wastewater Treatment Plant. The levels detected were far lower than the federal water standards that Fermilab is required to meet, and pose no threat to human health or the environment. (Our Frequently Asked Questions page provides more general information about tritium.) How much tritium did we find? Very little. Samples of Indian Creek, taken just inside the Fermilab

218

Fast Flux Test Facility (FFTF) Briefing Book 1 Summary  

SciTech Connect (OSTI)

This report documents the results of evaluations preformed during 1997 to determine what, if an, future role the Fast Flux Test Facility (FFTF) might have in support of the Department of Energy’s tritium productions strategy. An evaluation was also conducted to assess the potential for the FFTF to produce medical isotopes. No safety, environmental, or technical issues associated with producing 1.5 kilograms of tritium per year in the FFTF have been identified that would change the previous evaluations by the Department of Energy, the JASON panel, or Putnam, Hayes & Bartlett. The FFTF can be refitted and restated by July 2002 for a total expenditure of $371 million, with an additional $64 million of startup expense necessary to incorporate the production of medical isotopes. Therapeutic and diagnostic applications of reactor-generated medical isotopes will increase dramatically over the next decade. Essential medical isotopes can be produced in the FFTF simultaneously with tritium production, and while a stand-alone medical isotope mission for the facility cannot be economically justified given current marker conditions, conservative estimates based on a report by Frost &Sullivan indicate that 60% of the annual operational costs (reactor and fuel supply) could be offset by revenues from medical isotope production within 10 yeas of restart. The recommendation of the report is for the Department of Energy to continue to maintain the FFTF in standby and proceed with preparation of appropriate Nations Environmental Policy Act documentation in full consultation with the public to consider the FFTF as an interim tritium production option (1.5 kilograms/year) with a secondary mission of producing medical isotopes.

WJ Apley

1997-12-01T23:59:59.000Z

219

Tritium and neutron measurements of a solid state cell  

SciTech Connect (OSTI)

A solid state cold fusion'' cell was constructed to test for non-equilibrium fusion in a solid. The stimulus for the design was the hypothesis that the electrochemical surface layer in the Pons- Fleischmann cell could be replaced with a metal-insulator- semiconductor (MIS) barrier. Cells were constructed of alternating layers of palladium and silicon powders pressed into a ceramic form and exposed to deuterium gas at 110 psia resulting in a D/Pd ratio of 0.7. Pulses of current were passed through the cells to populate non-equilibrium states at the MIS barriers. One cell showed neutron activity and was found to have a large amount of tritium, other cells have produced tritium at a low rate consistent with neutron emission below the threshold of observability. The branching ratio for n/p has been about 1 {times} 10{sup {minus}9} in all the experiments where a substantial amount of tritium has been found. 11 refs., 9 figs., 2 tabs.

Claytor, T.N.; Seeger, P.A.; Rohwer, R.K.; Tuggle, D.G.; Doty, W.R.

1989-01-01T23:59:59.000Z

220

Experiments on a Ceramic Electrolysis Cell and a Palladium Diffuser at the Tritium Systems Test Assembly  

Science Journals Connector (OSTI)

Fusion Reactor / Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985)

S. Konishi; H. Yoshida; H. Ohno; Y. Naruse; D. O. Coffin; C. R. Walthers; K. E. Binning

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

In-Situ Imaging and Quantification of Tritium Surface Contamination via Coherent Fiber Bundle  

Science Journals Connector (OSTI)

Analysis and Monitoring / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

Charles A. Gentile; John J. Parker; Stewart J. Zweben

222

Observation of Hydrogen Distribution in Oxidized Zircaloy-2 with Tritium Microautoradiography  

Science Journals Connector (OSTI)

Material Interaction and Permeation / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

Hitoshi Hanada; Yuji Hatano; Kanetsugu Isobe; Kan Sakamoto; Masayasu Sugisaki

223

SGP Central Facility  

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

Central Facility Central Facility SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts SGP Central Facility The ARM Climate Research Facility deploys specialized remote sensing instruments in a fixed location at the site to gather atmospheric data of unprecedented quality, consistency, and completeness. More than 30 instrument clusters have been placed around the site; the central facility; and the boundary, intermediate, and extended facilities. The locations for the instruments were chosen so that the measurements reflect conditions

224

ARM - SGP Central Facility  

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

Central Facility Central Facility SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts SGP Central Facility The ARM Climate Research Facility deploys specialized remote sensing instruments in a fixed location at the site to gather atmospheric data of unprecedented quality, consistency, and completeness. More than 30 instrument clusters have been placed around the site; the central facility; and the boundary, intermediate, and extended facilities. The locations for the instruments were chosen so that the measurements reflect conditions

225

Fast Flux Test Facility (FFTF) standby plan  

SciTech Connect (OSTI)

The FFTF Standby Plan, Revision 0, provides changes to the major elements and project baselines to maintain the FFTF plant in a standby condition and to continue washing sodium from irradiated reactor fuel. The Plan is consistent with the Memorandum of Decision approved by the Secretary of Energy on January 17, 1997, which directed that FFTF be maintained in a standby condition to permit the Department to make a decision on whether the facility should play a future role in the Department of Energy`s dual track tritium production strategy. This decision would be made in parallel with the intended December 1998 decision on the selection of the primary, long- term source of tritium. This also allows the Department to review the economic and technical feasibility of using the FFTF to produce isotopes for the medical community. Formal direction has been received from DOE-RL and Fluor 2020 Daniel Hanford to implement the FFTF standby decision. The objective of the Plan is maintain the condition of the FFTF systems, equipment and personnel to preserve the option for plant restart within three and one-half years of a decision to restart, while continuing deactivation work which is consistent with the standby mode.

Hulvey, R.K.

1997-03-06T23:59:59.000Z

226

NREL: Energy Systems Integration Facility - Facility Design  

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

Facility Design Throughout the Energy Systems Integration Facility design process, the National Renewable Energy Laboratory hosted workshops in which stakeholders from across the...

227

Letter Report for Analytical Results for five Swipe Samples from the Northern Biomedical Research Facility, Muskegon Michigan  

SciTech Connect (OSTI)

Oak Ridge Associated Universities (ORAU), under the Oak Ridge Institute for Science and Education (ORISE) contract, received five swipe samples on December 10, 2013 from the Northern Biomedical Research Facility in Norton Shores, Michigan. The samples were analyzed for tritium and carbon-14 according to the NRC Form 303 supplied with the samples. The sample identification numbers are presented in Table 1 and the tritium and carbon-14 results are provided in Table 2. The pertinent procedure references are included with the data tables.

Ivey, Wade

2013-12-17T23:59:59.000Z

228

Investigation on tritium breeding capability of solid-liquid breeders in a (DT) fusion driven hybrid reactor  

Science Journals Connector (OSTI)

In design of deuterium-tritium (DT) fusion driven hybrid reactors, maintaining tritium self-sufficiency is very important ... to decrease operational costs. A (DT) fusion driven hybrid reactor must produce its ow...

M. Übeyli

2006-10-01T23:59:59.000Z

229

Effect of Lithium Enrichment on the Tritium Breeding Characteristics of Various Breeders in a Fusion Driven Hybrid Reactor  

Science Journals Connector (OSTI)

Selection of lithium containing materials is very important in the design of a deuterium–tritium (DT) fusion driven hybrid reactor in order to supply its tritium self- ... lithium-6 enrichment in the coolant of t...

Mustafa Übeyli

2009-09-01T23:59:59.000Z

230

4858 recreation facility [n  

Science Journals Connector (OSTI)

plan. recr. (Installation and equipment provided for recreation; ? simply-provided recreation facility , ? well-provided recreation facility ...

2010-01-01T23:59:59.000Z

231

Facilities | Argonne National Laboratory  

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

Engineering Research Facility Distributed Energy Research Center Engine Research Facility Heat Transfer Laboratory Tribology Laboratory Transportation Beamline at the Advanced...

232

Shock timing measurements and analysis in deuterium-tritium-ice layered capsule implosions on NIF  

SciTech Connect (OSTI)

Recent advances in shock timing experiments and analysis techniques now enable shock measurements to be performed in cryogenic deuterium-tritium (DT) ice layered capsule implosions on the National Ignition Facility (NIF). Previous measurements of shock timing in inertial confinement fusion implosions [Boehly et al., Phys. Rev. Lett. 106, 195005 (2011); Robey et al., Phys. Rev. Lett. 108, 215004 (2012)] were performed in surrogate targets, where the solid DT ice shell and central DT gas were replaced with a continuous liquid deuterium (D2) fill. These previous experiments pose two surrogacy issues: a material surrogacy due to the difference of species (D2 vs. DT) and densities of the materials used and a geometric surrogacy due to presence of an additional interface (ice/gas) previously absent in the liquid-filled targets. This report presents experimental data and a new analysis method for validating the assumptions underlying this surrogate technique. Comparison of the data with simulation shows good agreement for the timing of the first three shocks, but reveals a considerable discrepancy in the timing of the 4th shock in DT ice layered implosions. Electron preheat is examined as a potential cause of the observed discrepancy in the 4th shock timing.

Robey, H. F.; Celliers, P. M.; Moody, J. D.; Sater, J.; Parham, T.; Kozioziemski, B.; Dylla-Spears, R.; Ross, J. S.; LePape, S.; Ralph, J. E.; Dewald, E. L.; Berzak Hopkins, L.; Kroll, J. J.; Yoxall, B. E.; Hamza, A. V.; Landen, O. L.; Edwards, M. J. [Lawrence Livermore National Laboratory, Livermore, California 94551 (United States)] [Lawrence Livermore National Laboratory, Livermore, California 94551 (United States); Hohenberger, M.; Boehly, T. R. [Laboratory for Laser Energetics, Rochester, New York 14623 (United States)] [Laboratory for Laser Energetics, Rochester, New York 14623 (United States); Nikroo, A. [General Atomics, San Diego, California 92196 (United States)] [General Atomics, San Diego, California 92196 (United States)

2014-02-15T23:59:59.000Z

233

Mixed Waste Management Facility groundwater monitoring report. Second quarter 1994  

SciTech Connect (OSTI)

Currently, 125 wells monitor groundwater quality in the uppermost aquifer beneath the Mixed Waste Management Facility (MWMF) at the Savannah River Site. Samples from the wells are analyzed for selected heavy metals, indicator parameters, radionuclides, volatile organic compounds, and other constituents. During second quarter 1994, chloroethene (vinyl chloride), 1,1-dichloroethylene, gross alpha, lead, tetrachloroethylene, trichloroethylene, or tritium exceeded final Primary Drinking Water Standards (PDWS) in approximately half of the downgradient wells at the MWMF. Consistent with historical trends, elevated constituent levels were found primarily in Aquifer Zone. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents during second quarter 1994. Sixty-two of the 125 monitoring wells contained elevated tritium activities. Trichloroethylene concentrations exceeded the final PDWS in 23 wells. Chloroethene, 1,1-dichloroethylene, lead, and tetrachloroethylene, elevated in one or more wells during second quarter 1994, also occurred in elevated levels during first quarter 1994. These constituents generally were elevated in the same wells during both quarters. Gross alpha, which was not elevated in any well during first quarter 1994, was elevated in one well during second quarter. Copper, mercury, and nonvolatile beta were elevated during first quarter 1994 but not during second quarter.

Chase, J.A.

1994-09-01T23:59:59.000Z

234

Facility Representatives  

Broader source: Energy.gov (indexed) [DOE]

063-2011 063-2011 February 2011 Superseding DOE-STD-1063-2006 April 2006 DOE STANDARD FACILITY REPRESENTATIVES U.S. Department of Energy AREA MGMT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1063-2011 ii Available on the Department of Energy Technical Standards Program Web site at http://www.hss.doe.gov/nuclearsafety/ns/techstds/ DOE-STD-1063-2011 iii FOREWORD 1. This Department of Energy (DOE) standard is approved for use by all DOE/National Nuclear Security Administration (NNSA) Components. 2. The revision to this DOE standard was developed by a working group consisting of headquarters and field participants. Beneficial comments (recommendations,

235

Facility Representatives  

Broader source: Energy.gov (indexed) [DOE]

DOE-STD-1063-2006 April 2006 Superseding DOE-STD-1063-2000 March 2000 DOE STANDARD FACILITY REPRESENTATIVES U.S. Department of Energy AREA MGMT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1063-2006 ii Available on the Department of Energy Technical Standards Program web site at http://www.eh.doe.gov/techstds/ DOE-STD-1063-2006 iii FOREWORD 1. This Department of Energy standard is approved for use by all DOE Components. 2. The revision to this DOE standard was developed by a working group consisting of headquarters and field participants. Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should

236

Facility Type!  

Office of Legacy Management (LM)

ITY: ITY: --&L~ ----------- srct-r~ -----------~------~------- if yee, date contacted ------------- cl Facility Type! i I 0 Theoretical Studies Cl Sample 84 Analysis ] Production 1 Diepasal/Storage 'YPE OF CONTRACT .--------------- 1 Prime J Subcontract&- 1 Purchase Order rl i '1 ! Other information (i.e., ---------~---~--~-------- :ontrait/Pirchaee Order # , I C -qXlJ- --~-------~~-------~~~~~~ I I ~~~---~~~~~~~T~~~ FONTRACTING PERIODi IWNERSHIP: ,I 1 AECIMED AECMED GOVT GOUT &NTtiAC+OR GUN-I OWNED ----- LEEE!? M!s LE!Ps2 -LdJG?- ---L .ANDS ILJILDINGS X2UIPilENT IRE OR RAW HA-I-L :INAL PRODUCT IASTE Z. RESIDUE I I kility l pt I ,-- 7- ,+- &!d,, ' IN&"E~:EW AT SITE -' ---------------- , . Control 0 AEC/tlED managed operations

237

Research Facility,  

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

Collecting and Delivering the Data Collecting and Delivering the Data As a general condition for use of the ARM Climate Research Facility, users are required to include their data in the ARM Data Archive. All data acquired must be of sufficient quality to be useful and must be documented such that users will be able to clearly understand the meaning and organization of the data. Final, quality-assured data sets are stored in the Data Archive and are freely accessible to the general scientific community. Preliminary data may be shared among field campaign participants during and shortly following the campaign. To facilitate sharing of preliminary data, the ARM Data Archive establishes restricted access capability, limited to participants and data managers.

238

A Fusion Development Facility on the Critical Path to Fusion Energy  

SciTech Connect (OSTI)

A fusion development facility (FDF) based on the tokamak approach with normal conducting magnetic field coils is presented. FDF is envisioned as a facility with the dual objective of carrying forward advanced tokamak (AT) physics and enabling the development of fusion energy applications. AT physics enables the design of a compact steady-state machine of moderate gain that can provide the neutron fluence required for FDF's nuclear science development objective. A compact device offers a uniquely viable path for research and development in closing the fusion fuel cycle because of the demand to consume only a moderate quantity of the limited supply of tritium fuel before the technology is in hand for breeding tritium.

Chan, V. S. [General Atomics, San Diego; Stambaugh, R [General Atomics, San Diego

2011-01-01T23:59:59.000Z

239

A fusion development facility on the critical path to fusion energy  

SciTech Connect (OSTI)

A fusion development facility (FDF) based on the tokamak approach with normal conducting magnetic field coils is presented. FDF is envisioned as a facility with the dual objective of carrying forward advanced tokamak (AT) physics and enabling the development of fusion energy applications. AT physics enables the design of a compact steady-state machine of moderate gain that can provide the neutron fluence required for FDF s nuclear science development objective. A compact device offers a uniquely viable path for research and development in closing the fusion fuel cycle because of the demand to consume only a moderate quantity of the limited supply of tritium fuel before the technology is in hand for breeding tritium.

Chan, Dr. Vincent [General Atomics; Canik, John [ORNL; Peng, Yueng Kay Martin [ORNL

2011-01-01T23:59:59.000Z

240

Radiological performance assessment for the E-Area Vaults Disposal Facility  

SciTech Connect (OSTI)

The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

Cook, J.R.; Hunt, P.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1994-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Accelerator Production of Tritium project process waste assessment  

SciTech Connect (OSTI)

DOE has made a commitment to compliance with all applicable environmental regulatory requirements. In this respect, it is important to consider and design all tritium supply alternatives so that they can comply with these requirements. The management of waste is an integral part of this activity and it is therefore necessary to estimate the quantities and specific wastes that will be generated by all tritium supply alternatives. A thorough assessment of waste streams includes waste characterization, quantification, and the identification of treatment and disposal options. The waste assessment for APT has been covered in two reports. The first report was a process waste assessment (PWA) that identified and quantified waste streams associated with both target designs and fulfilled the requirements of APT Work Breakdown Structure (WBS) Item 5.5.2.1. This second report is an expanded version of the first that includes all of the data of the first report, plus an assessment of treatment and disposal options for each waste stream identified in the initial report. The latter information was initially planned to be issued as a separate Waste Treatment and Disposal Options Assessment Report (WBS Item 5.5.2.2).

Carson, S.D.; Peterson, P.K.

1995-09-01T23:59:59.000Z

242

Tritium Specific Adsorption Simulation Utilizing the OSPREY Model  

SciTech Connect (OSTI)

During the processing of used nuclear fuel, volatile radionuclides will be discharged to the atmosphere if no recovery processes are in place to limit their release. The volatile radionuclides of concern are 3H, 14C, 85Kr, and 129I. Methods are being developed, via adsorption and absorption unit operations, to capture these radionuclides. It is necessary to model these unit operations to aid in the evaluation of technologies and in the future development of an advanced used nuclear fuel processing plant. A collaboration between Fuel Cycle Research and Development Offgas Sigma Team member INL and a NEUP grant including ORNL, Syracuse University, and Georgia Institute of Technology has been formed to develop off gas models and support off gas research. This report is discusses the development of a tritium specific adsorption model. Using the OSPREY model and integrating it with a fundamental level isotherm model developed under and experimental data provided by the NEUP grant, the tritium specific adsorption model was developed.

Veronica Rutledge; Lawrence Tavlarides; Ronghong Lin; Austin Ladshaw

2013-09-01T23:59:59.000Z

243

Harrisburg Facility Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Harrisburg Facility Biomass Facility Harrisburg Facility Biomass Facility Jump to: navigation, search Name Harrisburg Facility Biomass Facility Facility Harrisburg Facility Sector Biomass Facility Type Landfill Gas Location Dauphin County, Pennsylvania Coordinates 40.2734277°, -76.7336521° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.2734277,"lon":-76.7336521,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

244

Brookhaven Facility Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Brookhaven Facility Biomass Facility Brookhaven Facility Biomass Facility Jump to: navigation, search Name Brookhaven Facility Biomass Facility Facility Brookhaven Facility Sector Biomass Facility Type Landfill Gas Location Suffolk County, New York Coordinates 40.9848784°, -72.6151169° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.9848784,"lon":-72.6151169,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

245

Development and Verification of Tritium Analyses Code for a Very High Temperature Reactor  

SciTech Connect (OSTI)

A tritium permeation analyses code (TPAC) has been developed by Idaho National Laboratory for the purpose of analyzing tritium distributions in the VHTR systems including integrated hydrogen production systems. A MATLAB SIMULINK software package was used for development of the code. The TPAC is based on the mass balance equations of tritium-containing species and a various form of hydrogen (i.e., HT, H2, HTO, HTSO4, and TI) coupled with a variety of tritium source, sink, and permeation models. In the TPAC, ternary fission and neutron reactions with 6Li, 7Li 10B, 3He were taken into considerations as tritium sources. Purification and leakage models were implemented as main tritium sinks. Permeation of HT and H2 through pipes, vessels, and heat exchangers were importantly considered as main tritium transport paths. In addition, electroyzer and isotope exchange models were developed for analyzing hydrogen production systems including both high-temperature electrolysis and sulfur-iodine process. The TPAC has unlimited flexibility for the system configurations, and provides easy drag-and-drops for making models by adopting a graphical user interface. Verification of the code has been performed by comparisons with the analytical solutions and the experimental data based on the Peach Bottom reactor design. The preliminary results calculated with a former tritium analyses code, THYTAN which was developed in Japan and adopted by Japan Atomic Energy Agency were also compared with the TPAC solutions. This report contains descriptions of the basic tritium pathways, theory, simple user guide, verifications, sensitivity studies, sample cases, and code tutorials. Tritium behaviors in a very high temperature reactor/high temperature steam electrolysis system have been analyzed by the TPAC based on the reference indirect parallel configuration proposed by Oh et al. (2007). This analysis showed that only 0.4% of tritium released from the core is transferred to the product hydrogen. The amount of tritium in the product hydrogen was estimated to be approximately an order less than the gaseous effluent limit for tritium.

Chang H. Oh; Eung S. Kim

2009-09-01T23:59:59.000Z

246

DNA Extraction  

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

DNA Extraction DNA Extraction Being able to extract deoxyribonucleic acid (DNA) is important for a number of reasons. By studying DNA, scientists can identify genetic disorders or diseases, and they can also possibly find cures for them by manipulating or experimenting with this DNA. At the Laboratory, researchers have studied DNA to detect biothreat agents in environmental and forensic samples. Scientists also are studying how human DNA may be destroyed by certain types of electromagnetic waves at certain frequencies. Classroom Activity: This activity is about the extraction of DNA from strawberries. Strawberries are a great fruit to use for this lesson because each student can work on his or her own. Strawberries are recommended because they yield more DNA than any other fruit. Strawberries are octoploid, which means that they have eight copies of each

247

Results of tritium experiments on ceramic electrolysis cells and palladium diffusers for application to fusion reactor fuel cleanup systems  

SciTech Connect (OSTI)

Tritium tests at the Tritium Systems Test Assembly have demonstrated that ceramic electrolysis cells and palladium alloy diffuser developed in Japan are possible components for a fusion reactor fuel cleanup system. Both components have been successfully operated with tritium for over a year. A failure of the first electrolysis cell was most likely the result of an over voltage on the ceramic. A simple circuit was developed to eliminate this mode of failure. The palladium diffusers tubes exhibited some degradation of mechanical properties as a result of the build up of helium from the tritium decay, after 450 days of operation with tritium, however the effects were not significant enough to affect the performance. New models of the diffuser and electrolysis cell, providing higher flow rates and more tritium compatible designs are currently being tested with tritium. 8 refs., 5 figs.

Carlson, R.V.; Binning, K.E.; Konishi, S.; Yoshida, H.; Naruse, Y.

1987-01-01T23:59:59.000Z

248

International Facility Management Association Strategic Facility  

Broader source: Energy.gov (indexed) [DOE]

Facility Management Association Facility Management Association Strategic Facility Planning: A WhIte PAPer Strategic Facility Planning: A White Paper on Strategic Facility Planning © 2009 | International Facility Management Association For additional information, contact: 1 e. Greenway Plaza, Suite 1100 houston, tX 77046-0104 USA P: + 1-713-623-4362 F: + 1-713-623-6124 www.ifma.org taBle OF cOntentS PreFace ......................................................... 2 executive Summary .................................... 3 Overview ....................................................... 4 DeFinitiOn OF Strategic Facility Planning within the Overall cOntext OF Facility Planning ................. 5 SPecializeD analySeS ................................ 9 OrganizatiOnal aPPrOacheS tO SFP ... 10 the SFP PrOceSS .......................................

249

Hydrodynamic instability growth and mix experiments at the National Ignition Facility  

SciTech Connect (OSTI)

Hydrodynamic instability growth and its effects on implosion performance were studied at the National Ignition Facility [G. H. Miller, E. I. Moses, and C. R. Wuest, Opt. Eng. 443, 2841 (2004)]. Implosion performance and mix have been measured at peak compression using plastic shells filled with tritium gas and containing embedded localized carbon-deuterium diagnostic layers in various locations in the ablator. Neutron yield and ion temperature of the deuterium-tritium fusion reactions were used as a measure of shell-gas mix, while neutron yield of the tritium-tritium fusion reaction was used as a measure of implosion performance. The results have indicated that the low-mode hydrodynamic instabilities due to surface roughness were the primary culprits for yield degradation, with atomic ablator-gas mix playing a secondary role. In addition, spherical shells with pre-imposed 2D modulations were used to measure instability growth in the acceleration phase of the implosions. The capsules were imploded using ignition-relevant laser pulses, and ablation-front modulation growth was measured using x-ray radiography for a shell convergence ratio of ?2. The measured growth was in good agreement with that predicted, thus validating simulations for the fastest growing modulations with mode numbers up to 90 in the acceleration phase. Future experiments will be focused on measurements at higher convergence, higher-mode number modulations, and growth occurring during the deceleration phase.

Smalyuk, V. A.; Barrios, M.; Caggiano, J. A.; Casey, D. T.; Cerjan, C. J.; Clark, D. S.; Edwards, M. J.; Haan, S. W.; Hammel, B. A.; Hamza, A.; Hsing, W. W.; Hurricane, O.; Kroll, J.; Landen, O. L.; Lindl, J. D.; Ma, T.; McNaney, J. M.; Mintz, M.; Parham, T.; Peterson, J. L. [Lawrence Livermore National Laboratory, NIF Directorate, Livermore, California 94550 (United States)] [Lawrence Livermore National Laboratory, NIF Directorate, Livermore, California 94550 (United States); and others

2014-05-15T23:59:59.000Z

250

ARM - Facility News Article  

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

January 11, 2011 Facility News ARM Mobile Facility Completes Extended Campaign in the Azores; Next Stop-India Bookmark and Share The ARM Mobile Facility obtained data on Graciosa...

251

Facilities Services Overview & Discussion  

E-Print Network [OSTI]

& Finance Facilities Services Director: Jeff Butler Human Resources Administrative Services Engineering) Environmental Services Morrison (3) Admin Services Evans (1) Human Resources Engineering (4) ·EngineeringFacilities Services Overview & Discussion Jeff Butler Director ­ Facilities Services November 2011

Maxwell, Bruce D.

252

Technical aspects of the upgrade and commissioning of the tritium and related systems at TFTR  

SciTech Connect (OSTI)

Systems for delivering tritium to the Tokamak Fusion Test Reactor, and for cleaning the tritiated glovebox and room atmospheres, are being upgraded and commissioned as are the HVAC for the rooms and areas which will house tritium bearing systems. Major activities on the tritium systems included: alterations to glovebox atmosphere control logic; redesigning of cleanup system skids to allow maintenance and repairs; improvement of process instrumentation and logic, including increased capability for control and monitoring by a distributed control system; addition of a monitored vent system; preparation of operating instructions; and other enhancements. Design of changes to the HVAC are in the conceptual state.

Cherdack, R.N.; Sarker, C.R.; Palmer, J.; Tuohy, J.M.

1988-09-01T23:59:59.000Z

253

Fuel Fabrication Facility  

National Nuclear Security Administration (NNSA)

Construction of the Mixed Oxide Fuel Fabrication Facility Construction of the Mixed Oxide Fuel Fabrication Facility November 2005 May 2007 June 2008 May 2012...

254

Sandia National Laboratories: Facilities  

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

Center in Vermont Achieves Milestone Installation On September 23, 2014, in Concentrating Solar Power, Energy, Facilities, National Solar Thermal Test Facility, News, News &...

255

ARM - Facility News Article  

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

January 15, 2008 Facility News ARM Mobile Facility Completes Field Campaign in Germany Bookmark and Share Researchers will study severe precipitation events that occurred in...

256

from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Facility April 13, 2012 Isotope Production Facility produces cancer-fighting actinium 2:32 Isotope cancer treatment...

257

Programs & User Facilities  

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

Facilities Programs & User Facilities Enabling remarkable discoveries and tools that transform our understanding of energy and matter and advance national, economic, and energy...

258

Facility Data Policy  

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

Facility Data Policy About ESnet Our Mission The Network ESnet History Governance & Policies ESnet Policy Board ESCC Acceptable Use Policy Facility Data Policy Career Opportunities...

259

ARM - Facility News Article  

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

November 15, 2005 Facility News More Server Power Improves Performance at the ARM Data Management Facility Bookmark and Share Recently, several new Sun servers joined the...

260

ARM - Facility News Article  

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

approximately 22,500 square kilometers, or the approximate area of a modern climate model grid cell. Centered around the SGP Central Facility, these extended facilities are...

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

ARM - Facility News Article  

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

From Coastal Clouds to Desert Dust: ARM Mobile Facility Headed to Africa Bookmark and Share ARM operations staff prepare the ARM Mobile Facility in Point Reyes, California, for...

262

Nuclear Facilities | Department of Energy  

Energy Savers [EERE]

Nuclear Facilities Nuclear Facilities Nuclear Facilities Locator Map Numerical map data points indicate two or more nuclear facilities in the same geographic location. Nuclear...

263

Facility Representative Program: 2003 Facility Representative Workshop  

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

3 Facility Representative Workshop 3 Facility Representative Workshop May 13 - 15, 2003 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Day 1: Tuesday, May 13, 2003 Theme: Program Successes and Challenges 8:00 a.m. John Evans, Facility Representative Program Manager 8:15 a.m. Welcome Kathleen Carlson Manager, Nevada Site Office 8:30 a.m. Keynote Address Savannah River Site and Facility Reps - A Shared History and Common Future Jeffrey M. Allison Manager, Savannah River Operations Office 9:00 a.m. Videotaped Remarks from the Deputy Secretary Kyle E. McSlarrow, Deputy Secretary of Energy 9:10 a.m. Facility Representative of the Year Presentation Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board

264

NREL: Research Facilities - Test and User Facilities  

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

Test and User Facilities Test and User Facilities NREL has test and user facilities available to industry and other organizations for researching, developing, and evaluating renewable energy and energy efficiency technologies. Here you'll find an alphabetical listing and brief descriptions of NREL's test and user facilities. A | B | C | D | E | F | G | H | I | J | K | L | M | N | O | P | Q | R | S | T | U | V | W | X | Y | Z A Advanced Research Turbines At our wind testing facilities, we have turbines available to test new control schemes and equipment for reducing loads on wind turbine components. Learn more about the Advanced Research Turbines on our Wind Research website. Back to Top D Distributed Energy Resources Test Facility This facility was designed to assist the distributed power industry in the

265

Facility Representative Program: 2000 Facility Representative Workshop  

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

0 Facility Representative Workshop 0 Facility Representative Workshop May 16-18, 2000 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Tuesday, May 16, 2000 Theme for Day 1: Sustaining the Success of the Facility Representative Program 8:00 a.m. - Opening Remarks - Joe Arango, Facility Representative Program Manager 8:05 a.m. - Welcome - Kenneth Powers, Deputy Manager Nevada Operations Office 8:15 a.m. - Deputy Secretary Remarks - T. J. Glauthier, Deputy Secretary of Energy 8:30 a.m. - Keynote Address - Jerry Lyle, Assistant Manager for Environmental Management, Idaho Operations Office 9:00 a.m. - Facility Representative of the Year Presentation - Mark B. Whitaker, Departmental Representative 9:30 a.m. - Break 9:50 a.m. - Program Results and Goals - Joe Arango, Facility Representative Program Manager

266

A Study on the Tritium Behavior in the Rice Plant after a Short-Term Exposure of HTO  

SciTech Connect (OSTI)

In many Asian countries including Korea, rice is a very important food crop. Its grain is consumed by humans and its straw is used to feed animals. In Korea, there are four CANDU type reactors that release relatively large amounts of tritium into the environment. Since 1997, KAERI (Korea Atomic Energy Research Institute) has carried out the experimental studies to obtain domestic data on various parameters concerning the direct contamination of plant. In this study, the behavior of tritium in the rice plant is predicted and compared with the measurement performed at KAERI. Using the conceptual model of the soil-plant-atmosphere tritiated water transport system which was suggested by Charles E. Murphy, tritium concentrations in the soil and in leaves to time were derived. If the effect of tritium concentration in the soil is considered, the tritium concentration in leaves is described as a double exponential model. On the other hand if the tritium concentration in the soil is disregarded, the tritium concentration in leaves is described by a single exponential term as other models (e.g. Belot's or STAR-H3 model). Also concentration of organically bound tritium in the seed is predicted and compared with measurements. The results can be used to predict the tritium concentration in the rice plant at a field around the site and the ingestion dose following the release of tritium to the environment.

Yook, D-S.; Lee, K. J.; Choi, Y-H.

2002-02-26T23:59:59.000Z

267

TRITIUM PERMEATION AND TRANSPORT IN THE GASOLINE PRODUCTION SYSTEM COUPLED WITH HIGH TEMPERATURE GAS-COOLED REACTORS (HTGRS)  

SciTech Connect (OSTI)

This paper describes scoping analyses on tritium behaviors in the HTGR-integrated gasoline production system, which is based on a methanol-to-gasoline (MTG) plant. In this system, the HTGR transfers heat and electricity to the MTG system. This system was analyzed using the TPAC code, which was recently developed by Idaho National Laboratory. The global sensitivity analyses were performed to understand and characterize tritium behaviors in the coupled HTGR/MTG system. This Monte Carlo based random sampling method was used to evaluate maximum 17,408 numbers of samples with different input values. According to the analyses, the average tritium concentration in the product gasoline is about 3.05×10-3 Bq/cm3, and 62 % cases are within the tritium effluent limit (= 3.7x10-3 Bq/cm3[STP]). About 0.19% of released tritium is finally transported from the core to the gasoline product through permeations. This study also identified that the following four parameters are important concerning tritium behaviors in the HTGR/MTG system: (1) tritium source, (2) wall thickness of process heat exchanger, (3) operating temperature, and (4) tritium permeation coefficient of process heat exchanger. These four parameters contribute about 95 % of the total output uncertainties. This study strongly recommends focusing our future research on these four parameters to improve modeling accuracy and to mitigate tritium permeation into the gasol ine product. If the permeation barrier is included in the future study, the tritium concentration will be significantly reduced.

Chang H. Oh; Eung S. Kim; Mike Patterson

2011-05-01T23:59:59.000Z

268

Assessment of radiation exposure for materials in the LANSCE Spallation Irradiation Facility  

SciTech Connect (OSTI)

Materials samples were irradiated in the Los Alamos Radiation Effects Facility (LASREF) at the Los Alamos Neutron Science Center (LANSCE) to provide data for the Accelerator Production of Tritium (APT) project on the changes in mechanical and physical properties of materials in a spallation target environment. The targets were configured to expose samples to a variety of radiation environments including high-energy protons, mixed protons and neutrons, and predominantly neutrons. The irradiation was driven by an 800 MeV 1 mA proton beam with a circular Gaussian shape of approximately 2{sigma} = 3.5 cm. Two irradiation campaigns were conducted in which samples were exposed for approximately six months and two months, respectively. At the end of this period, the samples were extracted and tested. Activation foils that had been placed in proximity to the materials samples were used to quantify the fluences in various locations. The STAYSL2 code was used to estimate the fluences by combining the activation foil data with calculated data from the LAHET Code System (LCS) and MCNPX. The exposure for each sample was determined from the estimated fluences using interpolation based on a mathematical fitting to the fluence results. The final results included displacement damage (dpa) and gas (H, He) production for each sample from the irradiation. Based on the activation foil analysis, samples from several locations in both irradiation campaigns were characterized. The radiation damage to each sample was highly dependent upon location and varied from 0.023 to 13 dpa and was accompanied by high levels of H and He production.

James, M. R. (Michael R.); Maloy, S. A. (Stuart A.); Sommer, W. F. (Walter F.), Jr.; Fowler, Malcolm M.; Dry, D. E. (Donald E.); Ferguson, P. D. (Phillip D.); Corzine, R. K. (R. Karen); Mueller, G. E. (Gary E.)

2001-01-01T23:59:59.000Z

269

Coal extraction  

SciTech Connect (OSTI)

Coal is extracted using a mixed solvent which includes a substantially aromatic component and a substantially naphthenic component, at a temperature of 400/sup 0/ to 500/sup 0/C. Although neither component is an especially good solvent for coal by itself, the use of mixed solvent gives greater flexibility to the process and offers efficiency gains.

Clarke, J.W.; Kimber, G.M.; Rantell, T.D.; Snape, C.E.

1985-06-04T23:59:59.000Z

270

Potential Emissions of Tritium in Air from Wells on the Nevada National Security Site  

SciTech Connect (OSTI)

This slide-show discusses the Nevada National Security Site (NNSS) and tritium in the groundwater. It describes the wells and boreholes and potential airflow from these sources. Monitoring of selected wells is discussed and preliminary results are presented.

Warren, R.

2012-10-08T23:59:59.000Z

271

Plant-Based Plume-Scale Mapping of Tritium Contamination in Desert Soils  

Science Journals Connector (OSTI)

...interred at radioactive-waste disposal sites. Because tritiated water...contaminants, the associated site disturbance and costs of equipment...subsurface tritium movement from the Maxey Flats, KY LLRW disposal site (Rickard and Kirby, 1987 Kalisz...

B. J. Andraski; D. A. Stonestrom; R. L. Michel; K. J. Halford; J. C. Radyk

272

Laser design basis for the National Ignition Facility  

SciTech Connect (OSTI)

Controlled nuclear fusion initiated by highly intense laser beams has been the subject of experiment for many years. The National Ignition Facility (NIF) represents the culmination of design efforts to provide a laser facility that will successfully demonstrate fusion ignition in the laboratory. In this so-called inertial confinement approach, energetic driver beams (laser, X-ray, or charged particle) heat the outer surface of a spherical capsule containing deuterium and tritium (DT) fuel. As the capsule surface explosively evaporates, reaction pressure compresses the DT fuel causing the central core of the fuel to reach extreme density and temperature. When the central temperature is high enough, DT fusion reactions occur. The energy released from these reactions further heats the compressed fuel, and fusion burn propagates outward through the colder regions of the capsule much more rapidly than the inertially confined capsule can expand. The resulting fusion reactions yield many times more energy than was absorbed from the driver beams.

Hunt, J.T.; Manes, K.R.; Murray, J.R.; Renard, P.A.; Sawicki, R.; Trenholme, J.B.; Williams, W.

1994-06-01T23:59:59.000Z

273

Optimal conditions for shock ignition of scaled cryogenic deuterium-tritium targets  

SciTech Connect (OSTI)

Within the framework of the shock-ignition (SI) scheme, ignition conditions are reached following the separation of the compression and heating phases. First, the shell is compressed at a sub-ignition implosion velocity; then an intense laser spike is launched at the end of the main drive, leading to the propagation of a strong shock through the precompressed fuel. The minimal laser energy required for ignition of scaled deuterium-tritium (DT) targets is assessed by calculations. A semi-empiric model describing the ignitor shock generation and propagation in the fuel assembly is defined. The minimal power needed in the laser spike pulse to achieve ignition is derived from the hydrodynamic model. Optimal conditions for ignition of scaled targets are explored in terms of laser intensity, shell-implosion velocity, and target scale range for the SI process. Curves of minimal laser requirements for ignition are plotted in the energy-power diagram. The most economic and reliable conditions for ignition of a millimeter DT target are observed in the 240- to 320-km/s implosion velocity range and for the peak laser intensity ranging from {approx}2 Multiplication-Sign 10{sup 15} W/cm{sup 2} up to 5 Multiplication-Sign 10{sup 15} W/cm{sup 2}. These optimal conditions correspond to shock-ignited targets for a laser energy of {approx}250 kJ and a laser power of 100 to 200 TW. Large, self-ignited targets are particularly attractive by offering ignition at a lower implosion velocity and a reduced laser intensity than for conventional ignition. The SI scheme allows for the compression and heating phases of the high power laser energy research facility target to be performed at a peak laser intensity below 10{sup 16} W/cm{sup 2}. A better control of parametric and hydrodynamic instabilities within the SI scheme sets it as an optimal and reliable approach to attain ignition of large targets.

Lafon, M. [Laboratory for Laser Energetics and Fusion Science Center, University of Rochester, Rochester, New York 14623 (United States); University of Bordeaux-CNRS-CEA, Centre Lasers Intenses et Applications, UMR 5107, 33405 Talence (France); Ribeyre, X.; Schurtz, G. [University of Bordeaux-CNRS-CEA, Centre Lasers Intenses et Applications, UMR 5107, 33405 Talence (France)

2013-02-15T23:59:59.000Z

274

The Concentration Of Tritium In Urine And Internal Radiation Dose Estimation Of PTNBR Radiation Workers  

SciTech Connect (OSTI)

The operation of Triga 2000 reactor in Nuclear Technology Center for Materials and Radiometry (PTNBR BATAN) normally produce tritium radionuclide which is the activation product of deuterium atom in reactor primary cooling water. According to previous monitoring, tritium was detected with the concentration of 8.236{+-}0.677 kBq/L and 1.704{+-}0.046 Bq/L in the primary cooling water and in reactor hall air, respectively. The tritium in reactor hall air chronically can be inhaled by the workers. In this research, tritium content in radiation workers' urine was determined to estimate the internal radiation doses received by the workers. About 50-100 mL of urine samples were collected from 48 PTNBR workers that is classified as 24 radiation workers and 24 administration staffs as a control. Urine samples of 25 mL were then prepared by active charcoal and KMnO{sub 4} addition and followed with complete distillation. The 2 mL of distillate was added with 13 mL scintillator, shaked vigorously and remained in cool and dark condition for about 24 hours. The tritium in the samples was then measured using liquid scintillation counter (LSC) for 1 hour. From the measurement results it was obtained that the tritium concentration in the urine of radiation workers were in the range of not detected and 5.191 Bq/mL, whereas in the administration staffs the concentration were between not detected and 4.607 Bq/mL. Internally radiation doses were calculated using the tritium concentration data, and it was found the averages about 0.602 {mu}Sv/year and 0.532 {mu}Sv/year for radiation workers and administration staffs, respectively. The doses received by the workers were lower than that of the permissible doses from tritium, i.e. 40 {mu}Sv/year.

Tjahaja, Poppy Intan; Sukmabuana, Putu; Aisyah, Neneng Nur [PTNBR BATAN, Jl. Tamansari no. 71, Bandung 40132 (Indonesia)

2010-12-23T23:59:59.000Z

275

Commissioning for Federal Facilities  

Broader source: Energy.gov [DOE]

Guide describes building commissioning, recommissioning, retrocommissioning, and continuous commissioning for federal facilities.

276

MANAGING BERYLLIUM IN NUCLEAR FACILITY APPLICATIONS  

SciTech Connect (OSTI)

Beryllium plays important roles in nuclear facilities. Its neutron multiplication capability and low atomic weight make it very useful as a reflector in fission reactors. Its low atomic number and high chemical affinity for oxygen have led to its consideration as a plasma-facing material in fusion reactors. In both applications, the beryllium and the impurities in it become activated by neutrons, transmuting them to radionuclides, some of which are long-lived and difficult to dispose of. Also, gas production, notably helium and tritium, results in swelling, embrittlement, and cracking, which means that the beryllium must be replaced periodically, especially in fission reactors where dimensional tolerances must be maintained. It has long been known that neutron activation of inherent iron and cobalt in the beryllium results in significant {sup 60}Co activity. In 2001, it was discovered that activation of naturally occurring contaminants in the beryllium creates sufficient {sup 14}C and {sup 94}Nb to render the irradiated beryllium 'Greater-Than-Class-C' for disposal in U.S. radioactive waste facilities. It was further found that there was sufficient uranium impurity in beryllium that had been used in fission reactors up to that time that the irradiated beryllium had become transuranic in character, making it even more difficult to dispose of. In this paper we review the extent of the disposal issue, processes that have been investigated or considered for improving the disposability of irradiated beryllium, and approaches for recycling.

R. Rohe; T. N. Tranter

2011-12-01T23:59:59.000Z

277

Tritium trapping in silicon carbide in contact with solid breeder under high flux isotope reactor irradiation  

SciTech Connect (OSTI)

The trapping of tritium in silicon carbide (SiC) injected from ceramic breeding materials was examined via tritium measurements using imaging plate (IP) techniques. Monolithic SiC in contact with ternary lithium oxide (lithium titanate and lithium aluminate) as a ceramic breeder was irradiated in the High Flux Isotope Reactor (HFIR) in Oak Ridge, Tennessee, USA. The distribution of photo-stimulated luminescence (PSL) of tritium in SiC was successfully obtained, which separated the contribution of 14C ß-rays to the PSL. The tritium incident from ceramic breeders was retained in the vicinity of the SiC surface even after irradiation at 1073 K over the duration of ~3000 h, while trapping of tritium was not observed in the bulk region. The PSL intensity near the SiC surface in contact with lithium titanate was higher than that obtained with lithium aluminate. The amount of the incident tritium and/or the formation of a Li2SiO3 phase on SiC due to the reaction with lithium aluminate under irradiation likely were responsible for this observation.

H. Katsui; Y. Katoh; A. Hasegawa; M. Shimada; Y. Hatano; T. Hinoki; S. Nogami; T. Tanaka; S. Nagata; T. Shikama

2013-11-01T23:59:59.000Z

278

Facility Representative Program: 2010 Facility Representative Workshop  

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

10 Facility Representative Workshop 10 Facility Representative Workshop May 12 - 13, 2010 Las Vegas, NV Facility Rep of the Year Award | Attendees | Summary Report Workshop Agenda and Presentations Day 1: Wednesday, May 12, 2010 8:00 a.m. Opening Remarks James Heffner, Facility Representative Program Manager Earl Hughes, Safety System Oversight Program Manager Office of Nuclear Safety Policy and Assistance Office of Health, Safety and Security 8:15 a.m. Welcome from the Nevada Site Office John Mallin, Deputy Assistant Manager for Site Operations Nevada Site Office 8:30 a.m. Workshop Keynote Address Todd Lapointe Chief of Nuclear Safety Central Technical Authority Staff 9:15 a.m. Facility Representative and Safety System Oversight Award Ceremony James Heffner, Facility Representative Program Manager

279

Facility Representative Program: 2007 Facility Representative Workshop  

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

7 Facility Representative Workshop 7 Facility Representative Workshop May 15 - 17, 2007 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Final Day 1: Tuesday, May 15, 2007 8:00 a.m. Opening Remarks Joanne Lorence, Facility Representative Program Manager 8:15 a.m. Welcome from the Nevada Site Office Gerald Talbot, Manager, Nevada Site Office 8:30 a.m. Videotaped Remarks from the Deputy Secretary The Honorable Clay Sell, Deputy Secretary of Energy 8:45 a.m. Keynote Address - Safety Oversight Perspective and Expectations Glenn Podonsky, Chief Health, Safety and Security Officer, Office of Health, Safety and Security 9:10 a.m. Facility Representative of the Year Presentation Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board,

280

Facility Representative Program: 2001 Facility Representative Workshop  

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

1 Facility Representative Workshop 1 Facility Representative Workshop May 15 - 17, 2001 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Day 1: Tuesday, May 15, 2001 Theme: Program Successes and Challenges 8:00 a.m. - Logistics Announcements & Opening Remarks - Joe Arango, Facility Representative Program Manager 8:15 a.m. - Welcome - Debbie Monette, Assistant Manager for National Security, Nevada Operations Office 8:30 a.m. - Keynote Address - Ralph Erickson, National Nuclear Security Administration 9:00 a.m.- DOE Facility Representative of the Year Presentation - Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board 9:30 a.m. - Break 9:50 a.m. - Program Summary - Joe Arango 10:10 a.m. - Management Panel/Questions and Answers

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

The setup of an extraction system coupled to a hydrogen isotopes distillation column  

SciTech Connect (OSTI)

Among the most difficult problems of cryogenic distillation one stands apart: the extraction of the heavy fraction. By an optimal design of the cycle scheme, this problem could be avoided. A 'worst case scenario' is usually occurring when the extracted fraction consists of one prevalent isotope such as hydrogen and small amounts of the other two hydrogen isotopes (deuterium and/or tritium). This situation is further complicated by two parameters of the distillation column: the extraction flow rate and the hold-up. The present work proposes the conceptual design of an extraction system associated to the cryogenic distillation column used in hydrogen separation processes. During this process, the heavy fraction (DT, T{sub 2}) is separated, its concentration being the highest at the bottom of the distillation column. From this place the extraction of the gaseous phase can now begin. Being filled with adsorbent, the extraction system is used to temporarily store the heavy fraction. Also the extraction system provides samples for the gas Chromatograph. The research work is focused on the existent pilot plant for tritium and deuterium separation from our institute to validate the experiments carried out until now. (authors)

Zamfirache, M.; Bornea, A.; Stefanescu, I.; Bidica, N.; Balteanu, O.; Bucur, C. [INC-DTCI, ICSIRm. Valcea, Uzinei Street 4, Rm. Valcea (Romania)

2008-07-15T23:59:59.000Z

282

Physical protection design approach for the Complex 21/Reconfiguration facilities  

SciTech Connect (OSTI)

Sandia National Laboratories and Los Alamos National Laboratory have been designated as the technical lead for Security, Safeguards and Computer/Information Security systems for all the DOE Complex 21/Weapons Complex Reconfiguration (WCR) facilities. The physical protection systems in these facilities will be required to meet the most current DOE orders and incorporate the latest physical protection technologies, proven state-of-the-art systems and strategies. The planned approach requires that security assistance and information be provided to the designers (e.g. the Complex 21 Architect & Engineer and the Weapons Complex Lead Laboratories) as early as possible and throughout all design phases. The outcome should avoid the costly retrofits to existing facilities that have occurred in the past and result in effective and comprehensive protection against current and projected threats with minimal impact on operations, safety and costs. This paper discusses the physical protection considerations being promoted for the integrated design effort for the Complex 21/Reconfiguration facilities, such as the tritium, uranium/lithium, plutonium processing and storage, high explosive and assembly and disassembly facilities.

Jaeger, C.D. [Sandia National Labs., Albuquerque, NM (US); Zack, N.R.; Hunteman, W.J. [Los Alamos National Lab., NM (US)

1993-07-01T23:59:59.000Z

283

NREL: Photovoltaics Research - Facilities  

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

Facilities Facilities NREL's world-class research facilities provide the venue for innovative advances in photovoltaic technologies and applications. These facilities within the National Center for Photovoltaics (NCPV) serve both multi-use and dedicated-use functions. We encourage our research colleagues in industry, universities, and other laboratories to pursue opportunities in working with our staff in these facilities. Dedicated-Use Facilities Photo of a red-hot coil glowing inside a round machine. Research within these facilities focuses on targeted areas of interest that require specific tools, techniques, or unique capabilities. Our two main dedicated-use facilities are the following: Outdoor Test Facility (OTF) OTF researchers study and evaluate advanced or emerging PV technologies

284

Proceedings of the tenth annual DOE low-level waste management conference: Session 3: Disposal technology and facility development  

SciTech Connect (OSTI)

This document contains ten papers on various aspects of low-level radioactive waste management. Topics include: design and construction of a facility; alternatives to shallow land burial; the fate of tritium and carbon 14 released to the environment; defense waste management; engineered sorbent barriers; remedial action status report; and the disposal of mixed waste in Texas. Individual papers were processed separately for the data base. (TEM)

Not Available

1988-12-01T23:59:59.000Z

285

Tritium distribution in the environment in the vicinity of a chronic atmospheric source-assessment of the steady state hypothesis  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a major radionuclide production center. Tritium has been released to the atmosphere over the 36 year period of operation. The tritiated water concentration of the atmosphere, rain, vegetation and food have been routinely monitored during this period. Special studies have been made of tritium in soils and in the organic fractions of these same materials. The available data suggest that the average tritium concentration in the components of the terrestrial environment have approached a steady state with the two main sources of tritium, rainfall and atmospheric water vapor.

Murphy, C.E. Jr.; Bauer, L.R.; Zeigler, C.C.

1990-01-01T23:59:59.000Z

286

Tritium distribution in the environment in the vicinity of a chronic atmospheric source-assessment of the steady state hypothesis  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a major radionuclide production center. Tritium has been released to the atmosphere over the 36 year period of operation. The tritiated water concentration of the atmosphere, rain, vegetation and food have been routinely monitored during this period. Special studies have been made of tritium in soils and in the organic fractions of these same materials. The available data suggest that the average tritium concentration in the components of the terrestrial environment have approached a steady state with the two main sources of tritium, rainfall and atmospheric water vapor.

Murphy, C.E. Jr.; Bauer, L.R.; Zeigler, C.C.

1990-12-31T23:59:59.000Z

287

Secondary Startup Neutron Sources as a Source of Tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS)  

SciTech Connect (OSTI)

The hypothesis of this paper is that the Zircaloy clad fuel source is minimal and that secondary startup neutron sources are the significant contributors of the tritium in the RCS that was previously assigned to release from fuel. Currently there are large uncertainties in the attribution of tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS). The measured amount of tritium in the coolant cannot be separated out empirically into its individual sources. Therefore, to quantify individual contributors, all sources of tritium in the RCS of a PWR must be understood theoretically and verified by the sum of the individual components equaling the measured values.

Shaver, Mark W.; Lanning, Donald D.

2010-02-01T23:59:59.000Z

288

CRAD, Facility Safety- Nuclear Facility Safety Basis  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

289

User Facilities | ORNL  

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

USER PORTAL USER PORTAL BTRICBuilding Technologies Research Integration Center CNMSCenter for Nanophase Materials Sciences CSMBCenter for Structural Molecular Biology CFTFCarbon Fiber Technology Facility HFIRHigh Flux Isotope Reactor MDF Manufacturing Demonstration Facility NTRCNational Transportation Research Center OLCFOak Ridge Leadership Computing Facility SNSSpallation Neutron Source Keeping it fresh at the Spallation Neutron Source Nanophase material sciences' nanotech toolbox Home | User Facilities SHARE ORNL User Facilities ORNL is home to a number of highly sophisticated experimental user facilities that provide unmatched capabilities to the broader scientific community, including a growing user community from universities, industry, and other laboratories research institutions, as well as to ORNL

290

Facility Representative Program: Facility Representative Program Sponsors  

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

Facility Representative Program Sponsors Facility Representative Program Sponsors There are 29 Facility Representative Program Sponsors Office Name Title E-Mail Phone ASO Larry Pendexter ES&H Div Dir (Argonne) larry.pendexter@ch.doe.gov 630-252-1485 BHSO Bob Desmarais Operations Management Division Director desmarai@bnl.gov 631-344-5434 CBFO Glenn Gamlin Facility Representative Supervisor glenn.gamlin@wipp.ws 575-234-8136 CBFO Casey Gadbury Operations Manager casey.gadbury@wipp.ws 575-234-7372 FSO Mark Bollinger Deputy Manager Mark.Bollinger@ch.doe.gov 630-840-8130 FSO John Scott FR Team Lead john.scott@ch.doe.gov 630-840-2250 HS-30 James O'Brien Director, Office of Nuclear Safety James.O'Brien@hq.doe.gov 301-903-1408 HS-32 Earl Hughes Facility Representative Program Manager Earl.Hughes@hq.doe.gov 202-586-0065

291

Non-conventional passive sensors for monitoring tritium on surfaces  

SciTech Connect (OSTI)

The authors describe development of small passive, solid-state detectors for in-situ measurements of tritium, or other weak beta-emitting radionuclides, on surfaces. One form of detector operates on the principle of thermally stimulated exoelectron emission (TSEE), the other by discharge of an electret ion chamber (EIC). There are currently two specific types of commercially available detector systems that lend themselves to making surface measurements. One is the thin-film BeO on a graphite disc, and the other is the Teflon EIC. Two other types of TSEE dosimeters (ceramic BeO and carbon doped alumina) are described but lack either a suitable commercially available reader or standardized methods of fabrication. The small size of these detectors allows deployment in locations difficult to access with conventional windowless gas-flow proportional counters. Preliminary testing shows that quantitative measurements are realized with exposure times of 1--10 hours for the TSEE dosimeters (at the DOE release guideline of 5,000 dpm/100 cm{sup 2} for fixed beta contamination). The EIC detectors exhibit an MDA of 26,000 dpm/100 cm{sup 2} for a 24 hour exposure. Both types of integrating device are inexpensive and reusable. Measurements can, therefore, be made that are faster, cheaper, safer, and better than those possible with baseline monitoring technology.

Gammage, R.B.; Brock, J.L.; Meyer, K.E. [Oak Ridge National Lab., TN (United States). Health Sciences Research Div.

1995-06-01T23:59:59.000Z

292

Tritium Movement and Accumulation in the NGNP System Interface and Hydrogen Plant  

SciTech Connect (OSTI)

Tritium movement and accumulation in a Next Generation Nuclear Plant with a hydrogen plant using a high temperature electrolysis process and a thermochemical water splitting sulfur iodine process are estimated by the numerical code THYTAN as a function of design, operational, and material parameters. Estimated tritium concentrations in the hydrogen product and in process chemicals in the hydrogen plant of the Next Generation Nuclear Plant using the high temperature electrolysis process are slightly higher than the drinking water limit defined by the U.S. Environmental Protection Agency and the limit in the effluent at the boundary of an unrestricted area of a nuclear plant as defined by the U.S. Nuclear Regulatory Commission. However, these concentrations can be reduced to within the limits through use of some designs and modified operations. Tritium concentrations in the Next Generation Nuclear Plant using the Sulfur-Iodine Process are significantly higher as calculated and are affected by parameters with large uncertainties (i.e., tritium permeability of the process heat exchanger, the hydrogen concentration in the heat transfer and process fluids, the equilibrium constant of the isotope exchange reaction between HT and H2SO4). These parameters, including tritium generation and the release rate in the reactor core, should be more accurately estimated in the near future to improve the calculations for the NGNP using the Sulfur-Iodine Process. Decreasing the tritium permeation through the heat exchanger between the primary and secondary circuits may be an an effective measure for decreasing tritium concentrations in the hydrogen product, the hydrogen plant, and the tertiary coolant.

Hirofumi Ohashi; Steven R. Sherman

2007-06-01T23:59:59.000Z

293

NREL: Wind Research - Facilities  

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

Facilities Facilities Our facilities are designed to meet the wind industry's critical research needs with state-of-the-art design and testing facilities. NREL's unique and highly versatile facilities at the National Wind Technology Center offer research and analysis of wind turbine components and prototypes rated from 400 watts to 3 megawatts. Satellite facilities support the growth of wind energy development across the United States. National Wind Technology Center Facilities Our facilities are contained within a 305-acre area that comprises field test sites, test laboratories, industrial high-bay work areas, machine shops, electronics and instrumentation laboratories, and office areas. In addition, there are hundreds of test articles and supporting components such as turbines, meteorological towers, custom test apparatus, test sheds,

294

FACET User Facility  

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

AD SLACPortal > Accelerator Research Division > FACET User Facility AD SLACPortal > Accelerator Research Division > FACET User Facility Sign In Launch the Developer Dashboard SLAC National Accelerator Laboratory DOE | Stanford | SLAC | SSRL | LCLS | AD | PPA | Photon Science | PULSE | SIMES FACET User Facility : FACET An Office of Science User Facility Search this site... Search Help (new window) Top Link Bar FACET User Facility FACET Home About FACET FACET Experimental Facilities FACET Users Research at FACET SAREC Expand SAREC FACET FAQs FACET User Facility Quick Launch FACET Users Home FACET Division ARD Home About FACET FACET News FACET Users FACET Experimental Facilities FACET Research Expand FACET Research FACET Images Expand FACET Images SAREC Expand SAREC FACET Project Site (restricted) FACET FAQs FACET Site TOC All Site Content

295

ARM - Facility News Article  

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

October 15, 2005 [Facility News] October 15, 2005 [Facility News] Room to Share-New Guest Facility Ready for Users at North Slope of Alaska Bookmark and Share In September, installation was completed on the new Guest Instrument Facility in Barrow to provide additional space and ease crowded conditions. In September, installation was completed on the new Guest Instrument Facility in Barrow to provide additional space and ease crowded conditions. To alleviate crowded conditions at its research facilities on the North Slope of Alaska (NSA) site in Barrow, ARM operations staff recently completed the installation of a new Guest Instrument Facility. Similar to the platform at the Atqasuk site, the facility consists of two insulated shipping containers mounted on pilings, with a mezzanine to accommodate

296

Jupiter Laser Facility  

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

Jupiter Laser Facility The commissioning of the Titan Petawatt-Class laser to LLNL's Jupiter Laser Facility (JLF) has provided a unique platform for the use of petawatt (PW)-class...

297

Facilities | Jefferson Lab  

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

JLab Buildings Facilities Management & Logistics is responsible for performing or specifying performance of all Jefferson Lab facility maintenance. A D D I T I O N A L L I N K S:...

298

The digital preservation facility  

Science Journals Connector (OSTI)

Critical listening should be an essential part of all archiving and restoration facilities quality control. We review the priorities and requirements for listening spaces ranging from the individual collector and small community archives to large?scale facilities. Examples discussed include the Library of Congress Culpepper facility university libraries and commercial facilities. Adapting listening rooms to the requirements of n?channel audio are discussed. Public recommendations of the Sound Preservation Board of the Library of Congress will be reviewed.

2006-01-01T23:59:59.000Z

299

Sandia National Laboratories: Facilities  

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

DETL, Energy, Facilities, Materials Science, News, News & Events, Photovoltaic, Renewable Energy, Research & Capabilities, Solar, Solar Newsletter, Systems Analysis Sandia...

300

ORAU South Campus Facility  

Broader source: Energy.gov [DOE]

This document explains the cleanup activities and any use limitations for the land surrounding the ORAU South Campus Facility.

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

DOE Designated Facilities  

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

Research Argonne Wakefield Accelerator (AWA) Argonne Tandem Linac Accelerator System (ATLAS) Center for Nanoscale Materials Leadership Computing Facility* Brookhaven National...

302

Electrolytic Enrichment of Tritium with Solid Polymer Electrolyte for Application to Environmental Measurements  

SciTech Connect (OSTI)

We evaluated electrolytic separation factors of hydrogen isotopes by SPE (Solid Polymer Electrolyte) for application to environmental tritium analysis. The apparent separation factors {alpha}{sub a} for deuterium and {beta}{sub a} for tritium were determined as 3.5 {+-} 0.1 and 6.2 {+-} 0.5, respectively. The tritium enrichment of 8.4 times was achieved, when a 1000 ml of sample water was electrolyzed to about 60 ml. The chemical composition changes before and after the electrolysis were examined, showing an increase in H{sup +} and Na{sup +} concentrations and a decrease in Mg{sup 2+} and Ca{sup 2+}concentrations. F{sup -}, which was not contained in the sample water, was detected after electrolysis accompanying with a reduction of SO{sub 4}{sup 2-}, Cl{sup -} and NO{sub 3}{sup -}. The memory of tritium and ions in the electrolysis cell after electrolysis was possible to be eliminated by washings with de-ionized water. Tritium concentrations of rain at Kumamoto, Japan were determined with a combination of the present electrolytic enrichment system and liquid scintillation counting.

Momoshima, Noriyuki; Nagao, Yusaku; Toyoshima, Takahiro [Kumamoto University (Japan)

2005-07-15T23:59:59.000Z

303

Wheelabrator Bridgeport Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Wheelabrator Bridgeport Biomass Facility Jump to: navigation, search Name Wheelabrator Bridgeport Biomass Facility Facility Wheelabrator Bridgeport Sector Biomass Facility Type...

304

Facility Representative Program: 2004 Facility Representative Workshop  

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

4 Facility Representative Workshop 4 Facility Representative Workshop May 18 - 20, 2004 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Final Day 1: Tuesday, May 18, 2004 Theme: Program Successes and Challenges 8:00 a.m. Opening Remarks John Evans, Facility Representative Program Manager 8:15 a.m. Welcome Kathy Carlson, Nevada Site Office Manager 8:30 a.m. Videotaped Remarks from the Deputy Secretary Kyle E. McSlarrow, Deputy Secretary of Energy Deputy Secretary's Remarks 8:40 a.m. Keynote Address - NNSA Evaluation of Columbia Accident Investigation Board Report Brigadier General Ronald J. Haeckel, Principal Assistant Deputy Administrator for Military Applications, NNSA Other Information: NASAÂ’S Columbia Accident Investigation Board Report

305

Facility Representative Program: 2006 Facility Representative Workshop  

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

6 Facility Representative Workshop 6 Facility Representative Workshop May 16 - 19, 2006 Knoxville, Tennessee Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Final To view Pictures, scroll the mouse over the Picture icon To view Presentations, Picture Slideshows and Video, click on the icon Day 1: Tuesday, May 16, 2006 8:00 a.m. Opening Remarks John Evans, Facility Representative Program Manager 8:15 a.m. Welcome from Oak Ridge Office Gerald Boyd, Manager, Oak Ridge Office 8:25 a.m. Welcome from Y-12 Site Office Theodore Sherry, Manager, Y-12 Site Office 8:35 a.m. Videotaped Remarks from the Deputy Secretary The Honorable Clay Sell, Deputy Secretary of Energy 8:40 a.m. Keynote Address - Safety Oversight at Environmental Management Activities Dr. Inés Triay, Chief Operating Officer, Office of Environmental Management

306

NREL: Buildings Research - Facilities  

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

Facilities Facilities NREL provides industry, government, and university researchers with access to state-of-the-art and unique equipment for analyzing a wide spectrum of building energy efficiency technologies and innovations. NREL engineers and researchers work closely with industry partners to research and develop advanced technologies. NREL's existing facilities have been used to test and develop many award-winning building technologies and innovations that deliver significant energy savings in buildings, and the new facilities further extend those capabilities. In addition, the NREL campus includes living laboratories, buildings that researchers and other NREL staff use every day. Researchers monitor real-time building performance data in these facilities to study energy use

307

Difference in HETP and HTU for Isotopic Mixtures of Protium-Tritium and Protium Deuterium in Isotopic Exchange Between Water and Hydrogen on Hydrophobic Catalyst  

Science Journals Connector (OSTI)

Isotope Separation / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

A. Perevezentsev; B.M. Andreev; E.P. Magomedbekov; Yu.S. Pak; M.B. Rozenkevich; Yu.A. Sakharovskii

308

Mixed Waste Management Facility groundwater monitoring report: Third quarter 1994  

SciTech Connect (OSTI)

Currently, 125 wells monitor groundwater quality in the uppermost aquifer beneath the Mixed Waste Management Facility (MWMF) at the Savannah River Site. Samples from the wells are analyzed for selected heavy metals, herbicides/pesticides, indicator parameters, radionuclides, volatile organic compounds, and other constituents. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents during third quarter 1994. Sixty-four (51%) of the 125 monitoring wells contained elevated tritium activities. Trichloroethylene concentrations exceeded the final PDWS in 22 (18%) wells. Chloroethene, 1,1-dichloroethylene, and tetrachloroethylene, elevated in one or more wells during third quarter 1994, also occurred in elevated levels during second quarter 1994. These constituents generally were elevated in the same wells during both quarters. Gross alpha, which was elevated in only one well during second quarter 1994, was elevated again during third quarter. Mercury, which was elevated during first quarter 1994, was elevated again in one well. Dichloromethane was elevated in two wells for the first time in several quarters.

Not Available

1994-12-01T23:59:59.000Z

309

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect (OSTI)

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

310

Fusion Technologies for Tritium-Suppressed D-D Fusion White Paper prepared for FESAC Materials Science Subcommittee  

E-Print Network [OSTI]

1 Fusion Technologies for Tritium-Suppressed D-D Fusion White Paper prepared for FESAC Materials, Columbia University 2 Plasma Science and Fusion Center, MIT December 19, 2011 Summary The proposal for tritium-suppressed D-D fusion and the understanding of the turbulent pinch in magnetically confined plasma

311

Facility Name Facility Name Facility FacilityType Owner Developer EnergyPurchaser  

Open Energy Info (EERE)

Name Facility Name Facility FacilityType Owner Developer EnergyPurchaser Name Facility Name Facility FacilityType Owner Developer EnergyPurchaser Place GeneratingCapacity NumberOfUnits CommercialOnlineDate WindTurbineManufacturer FacilityStatus Coordinates D Metals D Metals D Metals Definition Small Scale Wind Valley City OH MW Northern Power Systems In Service AB Tehachapi Wind Farm AB Tehachapi Wind Farm AB Tehachapi Definition Commercial Scale Wind Coram Energy AB Energy Southern California Edison Co Tehachapi CA MW Vestas In Service AFCEE MMR Turbines AFCEE MMR Turbines AFCEE MMR Turbines Definition Commercial Scale Wind AFCEE Air Force Center for Engineering and the Environment Distributed generation net metered Camp Edwards Sandwich MA MW GE Energy In Service AG Land AG Land AG Land Definition Community Wind AG Land Energy LLC

312

ARM - Facility News Article  

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

March 22, 2007 [Facility News] March 22, 2007 [Facility News] GEWEX News Features Dust Data from ARM Mobile Facility Deployment Bookmark and Share Data from the recent deployment of the ARM Mobile Facility are featured in the February issue of GEWEX News. Data from the recent deployment of the ARM Mobile Facility are featured in the February issue of GEWEX News. The February 2007 issue (Vol. 17, No. 1) of GEWEX News features early results from special observing periods of the African Monsoon Mutidisciplinary Analysis, including data obtained by the ARM Mobile Facility (AMF). The AMF was stationed in the central Sahel from January through December 2006, with the primary facility at the Niamey airport, and an ancillary site in Banizoumbou. The AMF recorded a major dust storm that passed through the area in March, and combined with simultaneous satellite

313

ARM - Facility News Article  

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

February 16, 2005 [Facility News] February 16, 2005 [Facility News] Mobile Facility Arrives Safe and Sound in Point Reyes Bookmark and Share Image - The ARM Mobile Facility in Point Reyes, California Image - The ARM Mobile Facility in Point Reyes, California Safe and sound at Point Reyes, the ARM Mobile Facility instrumentation is set up on the roof of a shelter until a fence is installed to keep out the curious local cattle. On February 9, the ARM Mobile Facility (AMF) withstood an accident on the way to its deployment location at Point Reyes, California. About an hour from its destination, the truck carrying the two AMF shelters packed with instrumentation and associated equipment swerved to avoid another vehicle and slid off the road and down a steep embankment. Emergency personnel soon

314

ARM - Facility News Article  

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

22, 2011 [Facility News] 22, 2011 [Facility News] Request for Proposals Now Open Bookmark and Share The ARM Climate Research Facility is now accepting applications for use of an ARM mobile facility (AMF), the ARM aerial facility (AAF), and fixed sites. Proposals are welcome from all members of the scientific community for conducting field campaigns and scientific research using the ARM Facility, with availability as follows: AMF2 available December 2013 AMF1 available March 2015 AAF available between June and October 2013 Fixed sites available FY2013 Priority will be given to proposals that make comprehensive use of the ARM facilities and focus on long-term goals of the DOE Office of Biological and Environmental Research. Successful proposals will be supplied all operational and logistical resources (provided at no cost to the principal

315

Investigation of non-magnetic alloys for the suppression of tritium permeation. Final report  

SciTech Connect (OSTI)

This report describes a small (300 man hour) literature survey relating to the suppression of tritium loss by permeation through the walls of fusion reactors. The program was based on prior in-house Thermacore work to suppress hydrogen permeation into high temperature (800/sup 0/C) heat pipes. The Thermacore approach involves selection of a steel with a small (.5 to 5%) aluminum content. The aluminum is diffused to the surface and oxidized. The present work was aimed at identification of alloys which might combine low tritium permeation with other properties desired in fusion reactor vessels, heat exchangers, lithium-handling plumbing and other components likely to contain tritium. These properties include low radiation damage, low magnetic permeability, high temperature strength, and compatibility with potential heat transfer and blanket materials. The work consisted of two tasks: Problem Definition and Literature Search and Analysis.

None

1980-07-01T23:59:59.000Z

316

Production cross sections of tritium in high energy nuclear reactions with 12 GeV protons  

Science Journals Connector (OSTI)

Production cross sections of tritium in high energy nuclear reactions with 12 GeV protons were measured for Al, Co, Cu, Nb, Ag, In, Sn, Au and Pb targets. Large production cross sections of > 500 (mb) were obtained for Au and Pb targets. From their atomic weight dependence, tritium cross sections (?) in mb can be expressed as a function of target atomic weight (A) by the following simple equation: ?(A) = 95 exp(A107), which should be useful for predicting unknown cross sections. Together with other existing data at different energies, the present data suggest that there is no energy dependence of tritium cross section at proton energies above several GeV.

Masaharu Noguchi; Taichi Miura; Kenjiro Kondo; Takenori Suzuki; Yuichi Oki; Minoru Takasaki; Kazuhiro H. Tanaka; Masaharu Ieiri

1991-01-01T23:59:59.000Z

317

Migration in alluvium of chlorine-36 and tritium from an underground nuclear test  

SciTech Connect (OSTI)

This article describes a field experiment studying the migration in alluvium of radioactive elements away from an underground nuclear explosion at the Nevada Test Site in the United States. Nuclides detected in the pumped water are tritium, chlorine-36, iodine-129, and krypton-85 - all at levels below the maximum permissible concentration for drinking water in controlled areas. The chlorine-36 elution curve precedes that of tritium, and is due to an anion exclusion process. A conventional two-dimensional convection-diffusion equation does not fully describe the elution curves for tritium and chlorine-36; the tailing of the curves is longer than predicted. Successful modeling of this experiment will be important for validating codes and models to be used in the high-level nuclear waste program.

Ogard, A.E.; Thompson, J.L.; Rundberg, R.S.; Wolfsberg, K.; Kubik, P.W.; Elmore, D.; Bentley, H.W.

1987-01-01T23:59:59.000Z

318

224-T Facility - Hanford Site  

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

T Facility Projects & Facilities 100 Area 118-K-1 Burial Ground 200 Area 209-E Critical Mass Laboratory 222-S Laboratory 224-B Facility 224-T Facility 242-A Evaporator 300 Area 324...

319

Cold Test Facility - Hanford Site  

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

Projects & Facilities > Cold Test Facility Projects & Facilities 100 Area 118-K-1 Burial Ground 200 Area 209-E Critical Mass Laboratory 222-S Laboratory 224-B Facility 224-T...

320

Final Environmental Assessment for the Proposed Consolidation of Neutron Generator Tritium Target Loading Production  

Broader source: Energy.gov (indexed) [DOE]

Final Environmental Assessment Final Environmental Assessment for the Proposed Consolidation of Neutron Generator Tritium Target Loading Production DOE/EA-1532 June 2005 National Nuclear Security Administration Sandia Site Office P.O. Box 5400 Albuquerque, New Mexico 87185-5400 Environmental Assessment for the Proposed Consolidation of Neutron Generator Tritium Target Loading Production i Final EA DOE/EA-1532 June 2005 TABLE OF CONTENTS 1.0 PURPOSE AND NEED FOR AGENCY ACTION ........................................................................ 1 2.0 NO ACTION AND PROPOSED ACTION ALTERNATIVES...................................................... 2 2.1 No Action Alternative....................................................................................... 5

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Investigation of non-magnetic alloys for the suppression of tritium permeation  

SciTech Connect (OSTI)

The present work was aimed at identification of alloys which might combine low tritium permeation with other properties desired in fusion reactor vessels, heat exchangers, lithium-handling plumbing and other components likely to contain tritium. These properties include low radiation damage, low magnetic permeability, high temperature strength, and compatibility with potential heat transfer and blanket materials. The work consisted of two tasks: problem definition, and literature search and analysis. Task I was complicated by the incomplete status of fusion reactor development, particularly with respect to selection of coolant and blanket materials and temperatures. The approach taken was to establish a probable range of requirements.

None

1980-07-01T23:59:59.000Z

322

RMOTCTrainingFacilityNEW.doc  

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

* Field Laboratory with surface outcrops of Cretaceous fluvial and marine units * Gas Processing Facilities * Production Facilities * Tanks & Pipelines * Aquaculture &...

323

ARM - Facility News Article  

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

July 31, 2009 [Facility News] July 31, 2009 [Facility News] President of the Regional Government Speaks at Opening Ceremony for Mobile Facility in the Azores Bookmark and Share Highlighting the opening ceremony for the ARM Mobile Facility on Graciosa Island, Carlos César, President of the Regional Government of the Azores, signs a weather balloon while local media record the event. Photo by Mike Alsop. Highlighting the opening ceremony for the ARM Mobile Facility on Graciosa Island, Carlos César, President of the Regional Government of the Azores, signs a weather balloon while local media record the event. Photo by Mike Alsop. On June 30, officials from the Regional Government of the Azores recognized the deployment of the ARM Mobile Facility on Graciosa Island during an official opening ceremony held at the site. Notable among the participants

324

ARM - Facility News Article  

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

6, 2012 [Facility News] 6, 2012 [Facility News] News Tips from 2012 EGU General Assembly Bookmark and Share The ARM Facility is attending the 2012 European Geophysical Union General Assembly at the Austria Center in Vienna for the first time. The ARM Facility is attending the 2012 European Geophysical Union General Assembly at the Austria Center in Vienna for the first time. VIENNA - The U.S. Department of Energy's Atmospheric Radiation Measurement (ARM) Climate Research Facility is the world's most comprehensive outdoor laboratory and data archive for research related to atmospheric processes that affect Earth's climate. At the European Geophysical Union (EGU) General Assembly 2012 in Vienna, find out how scientists use the ARM Facility to study the interactions between clouds,

325

BNL | Accelerator Test Facility  

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

Accelerator Test Facility Accelerator Test Facility Home Core Capabilities Photoinjector S-Band Linac Laser Systems CO2 Laser Nd:Yag Laser Beamlines Beamline Simulation Data Beamline Parameters Beam Diagnostics Detectors Beam Schedule Operations Resources Fact Sheet (.pdf) Image Library Upgrade Proposal (.pdf) Publications ES&H Experiment Start-up ATF Handbook Laser Safety Collider-Accelerator Dept. C-AD ES&H Resources Staff Users' Place Apply for Access ATF photo ATF photo ATF photo ATF photo ATF photo A user facility for advanced accelerator research The Brookhaven Accelerator Test Facility (ATF) is a proposal driven, steering committee reviewed facility that provides users with high-brightness electron- and laser-beams. The ATF pioneered the concept of a user facility for studying complex properties of modern accelerators and

326

ARM - Facility News Article  

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

8, 2011 [Facility News, Publications] 8, 2011 [Facility News, Publications] Journal Special Issue Includes Mobile Facility Data from Germany Bookmark and Share The ARM Mobile Facility operated in Heselbach, Germany, as part of the COPS surface network. The ARM Mobile Facility operated in Heselbach, Germany, as part of the COPS surface network. In 2007, the ARM Mobile Facility participated in one of the most ambitious field studies ever conducted in Europe-the Convective and Orographically Induced Precipitation Study (COPS). Now, 21 papers published in a special issue of the Quarterly Journal of the Royal Meteorological Society demonstrate that the data collected during COPS are providing new insight into: the key chemical and physical processes leading to convection initiation and to the modification of precipitation by orography;

327

WIPP - Public Reading Facilities  

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

Public Reading Facilities/Electronic Reading Facilities The Freedom of Information Act (FOIA) and Electronic FOIA (E-FOIA) require that various specific types of records, as well as various other records, be maintained in public reading facilities. Before you submit a FOIA request, we recommend you contact or visit the appropriate public reading facility to determine if the records you are seeking have already been released. The U.S. Department of Energy (DOE), as well as other related DOE sites, have established home pages on the Internet with links to other web sites. If you determine a specific facility might have records in which you are interested, requests for those records can be made directly to the public reading rooms identified below. Copying of records located in the public reading rooms must be made by the staff of those facilities.

328

ARM - Facility News Article  

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

15, 2005 [Facility News] 15, 2005 [Facility News] Aging, Overworked Computer Network at SGP Gets Overhauled Bookmark and Share This aerial map of instruments deployed at the SGP Central Facility provides an indication of the computer resources needed to manage data at the site, let alone communicate with other ARM sites. This aerial map of instruments deployed at the SGP Central Facility provides an indication of the computer resources needed to manage data at the site, let alone communicate with other ARM sites. Established as the first ARM research facility in 1992, the Southern Great Plains (SGP) site in Oklahoma is the "old man on the block" when it comes to infrastructure. Though significant improvements have been made to facilities and equipment throughout the years, the computer network at the

329

ARM - Facility News Article  

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

April 7, 2011 [Facility News] April 7, 2011 [Facility News] Review Panel States ARM Facility "Without Peer" Bookmark and Share Every three years, DOE Office of Science user facilities undergo a review to evaluate their effectiveness in contributing to their respective science areas. The latest ARM Facility review was conducted in mid-February by a six-member review panel led by Minghua Zhang of Stony Brook University. Notably, in a debriefing following the review, the panel stated that ARM was a "world class facility without peer." The panel convened in Ponca City, Oklahoma, near ARM's Southern Great Plains site to conduct their review. Their first agenda item was an SGP site tour, which provided a realtime example of the scope and expertise of site operations and included a demonstration of the site's newly

330

ARM - Facility News Article  

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

8, 2010 [Facility News] 8, 2010 [Facility News] Europeans Keen to Hear About Effects of Dust Using Data from Africa Bookmark and Share In 2006, the ARM Mobile Facility joined the AMMA project to obtain data for scientists to study the impact that airborne Saharan dust has on incoming solar radiation. This photo shows the sun setting through a dusty atmosphere near Niamey, Niger, where the mobile facility was deployed for one year. In 2006, the ARM Mobile Facility joined the AMMA project to obtain data for scientists to study the impact that airborne Saharan dust has on incoming solar radiation. This photo shows the sun setting through a dusty atmosphere near Niamey, Niger, where the mobile facility was deployed for one year. Researcher Xiaohong Liu from Pacific Northwest National Laboratory was

331

ARM - Facility News Article  

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

April 30, 2008 [Facility News] April 30, 2008 [Facility News] Team Scouts Graciosa Island for 2009 Mobile Facility Deployment Site Bookmark and Share A location near the airport on the northern end of Graciosa Island was identified as an excellent location for operating the ARM Mobile Facility. Image source: Luis Miguens A location near the airport on the northern end of Graciosa Island was identified as an excellent location for operating the ARM Mobile Facility. Image source: Luis Miguens Indications from a scouting trip by the ARM Mobile Facility (AMF) science and operations management team are that an excellent site for the 2009 deployment may have been found. From April 8 through April 16, the team traveled to Graciosa Island in the Azores to scout sites for the Clouds, Aerosol, and Precipitation in the Marine Boundary Layer (CAP-MBL) field

332

340 Facility compliance assessment  

SciTech Connect (OSTI)

This study provides an environmental compliance evaluation of the RLWS and the RPS systems of the 340 Facility. The emphasis of the evaluation centers on compliance with WAC requirements for hazardous and mixed waste facilities, federal regulations, and Westinghouse Hanford Company (WHC) requirements pertinent to the operation of the 340 Facility. The 340 Facility is not covered under either an interim status Part A permit or a RCRA Part B permit. The detailed discussion of compliance deficiencies are summarized in Section 2.0. This includes items of significance that require action to ensure facility compliance with WAC, federal regulations, and WHC requirements. Outstanding issues exist for radioactive airborne effluent sampling and monitoring, radioactive liquid effluent sampling and monitoring, non-radioactive liquid effluent sampling and monitoring, less than 90 day waste storage tanks, and requirements for a permitted facility.

English, S.L. [Pacific Northwest Lab., Richland, WA (United States)

1993-10-01T23:59:59.000Z

333

Integrated Facilities Disposition Program  

Broader source: Energy.gov (indexed) [DOE]

Facilities Facilities Disposition Program Tank Waste Corporate Board Meeting at ORNL Sharon Robinson Dirk Van Hoesen Robert Jubin Brad Patton July 29, 2009 2 Managed by UT-Battelle for the U.S. Department of Energy The Integrated Facility Disposition Program (IFDP) addresses the remaining EM Scope at both ORNL and Y-12 Cost Range: $7 - $14B Schedule: 26 Years 3 Managed by UT-Battelle for the U.S. Department of Energy Scope of work * Treatment and disposition of legacy materials and waste * D&D 327 (1.5 M ft 2 ) excess facilities generating >2 M yd 3 debris * Soil and groundwater remedial actions generating >1 M yd 3 soils * Facilities surveillance and maintenance * Reconfiguration of waste management facilities * Ongoing waste management operations * Project management

334

ARM - Facility News Article  

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

4, 2013 [Facility News] 4, 2013 [Facility News] Work Cut Out for ARM Science Board Bookmark and Share With a new fixed site on the horizon in the Azores, a third ARM Mobile Facility gearing up for action in the Arctic, and more aircraft probes and sensors than scientists can shake a stick at, the ARM Facility continues to expand its considerable suite of assets for conducting climate research. Along with this impressive inventory comes the responsibility to ensure the Facility is supporting the highest-value science possible. Enter the ARM Science Board. This eleven-member group annually reviews complex proposals for use of the ARM mobile and aerial facilities. To maintain excellence and integrity in the review process, each member serves a renewable term of two years, with membership updated annually.

335

Mixed Waste Management Facility groundwater monitoring report, First quarter 1994  

SciTech Connect (OSTI)

During first quarter 1994, nine constituents exceeded final Primary Drinking Water Standards in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility, the Old Burial Ground, the E-Area Vaults, the proposed Hazardous Waste/Mixed Waste Disposal Vaults, and the F-Area Sewage Sludge Application Site. As in previous quarters, tritium and trichloroethylene were the most widespread elevated constituents. Chloroethene (vinyl chloride), copper, 1,1-dichloroethylene, lead, mercury, nonvolatile beta, or tetrachloroethylene also exceeded standards in one or more wells. Elevated constituents were found in numerous Aquifer Zone IIB{sub 2} (Water Table) and Aquifer Zone IIB{sub 1}, (Barnwell/McBean) wells and in one Aquifer Unit IIA (Congaree) well. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

Not Available

1994-06-01T23:59:59.000Z

336

Poultry Facility Biosecurity  

E-Print Network [OSTI]

of organic materials on tires and shoes. Design features should include a one-way traff_ic system for all poultry facilities. The system should route personnel, vehicles and poultry from youngest birds to oldest birds, from ?clean? areas to ?dirty? areas... from waterways used by migra - tory waterfowl. Locate new facilities as far as possible from roads handling high volumes of poultry vehicles such as feed trucks or live-haul vehicles. Poultry facilities also need adequate amounts of potable water...

Carey, John B.; Prochaska, J. Fred; Jeffrey, Joan S.

2005-12-21T23:59:59.000Z

337

ARM Climate Research Facility  

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

banner banner Home | People | Site Index Atmospheric Radiation Measurement Climate Research Facility US Department of Energy About Science Campaigns Sites Instruments Measurements Data News Publications Education Become a User Recovery Act Mission FAQ Outreach Displays History Organization Participants Facility Statistics Forms Contacts Research Themes Research Highlights Journal Articles Collaborations Atmospheric System Research (ASR) ARM Science Team Meetings Propose a Campaign Submitting Proposals: Guidelines Featured Campaigns Campaign Data List of Campaigns Aerial Facility Eastern North Atlantic Mobile Facilities North Slope of Alaska Southern Great Plains Tropical Western Pacific Location Table Contacts Instrument Datastreams Value-Added Products PI Data Products Field Campaign Data Related Data

338

ARM - Facility News Article  

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

20, 2008 Facility News ARM Scientists Lead International Radiation Symposium in Brazil Bookmark and Share The ARM Science Team showed up in force at the 2008 International...

339

Sandia National Laboratories: Facilities  

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

Facilities Sandian Presents on PV Failure Analysis at European PV Solar Energy Conference and Exhibition (EU PVSC) On December 15, 2014, in Computational Modeling & Simulation,...

340

Sandia National Laboratories: Facilities  

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

Production Method Could Lead to Better Lights, Lenses, Solar Cells On July 1, 2014, in Capabilities, CINT, Energy, Energy Efficiency, Facilities, Materials Science,...

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

ARM - Facility News Article  

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

June 30, 2007 Facility News New Radar Wind Profiler Joins AMF Instrument Suite in Germany Bookmark and Share The 1290 MHz wind profiler (foreground) joins the eddy correlation...

342

ARM Mobile Facilities  

ScienceCinema (OSTI)

This video provides an overview of the ARM Mobile Facilities, two portable climate laboratories that can deploy anywhere in the world for campaigns of at least six months.

Orr, Brad; Coulter, Rich

2014-09-15T23:59:59.000Z

343

AMF ARM Mobile FAcility  

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

AMF ARM Mobile FAcility Details on the AMF proposal process can be found at http:www.arm.govacrfsubmitproposals.stm. For more information, contact: Mark Miller Mary Jane...

344

ARM - Facility News Article  

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

2007 Facility News Field Campaigns Generate Interest from Aviation Aficionados in Oklahoma Bookmark and Share Dr. Pete Lamb On November 13, Dr. Pete Lamb attended a meeting of...

345

Lighting Test Facilities  

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

Custom Projects Lighting Test Facilities SSL Guidelines Industrial Federal Agriculture LED Street and Area Lighting Field Test of Exterior LED Down Lights Abstract Outdoor...

346

ARM Mobile Facilities  

SciTech Connect (OSTI)

This video provides an overview of the ARM Mobile Facilities, two portable climate laboratories that can deploy anywhere in the world for campaigns of at least six months.

Orr, Brad; Coulter, Rich

2010-12-13T23:59:59.000Z

347

Facility Survey & Transfer  

Broader source: Energy.gov [DOE]

As DOE facilities become excess, many that are radioactively and/or chemically contaminated will become candidate for transfer to DOE-EM for deactivation and decommissioning.

348

Neutron Scattering Facilities  

Science Journals Connector (OSTI)

The past history, present performance and future prospects for neutron scattering facilities will be discussed. Special features of neutron scattering techniques applicable to biological problems will be ... . Th...

D. L. Price

1996-01-01T23:59:59.000Z

349

Sandia National Laboratories: Facilities  

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

July 31, 2014, in DETL, Distribution Grid Integration, Energy, Energy Surety, Facilities, Grid Integration, Infrastructure Security, News, News & Events, Photovoltaic, Renewable...

350

Science and Technology Facility  

Office of Environmental Management (EM)

IBRF Project Lessons Learned Report Integrated Biorefinery Research Facility Lessons Learned - Stage I Acquisition through Stage II Construction Completion August 2011 This...

351

Supercomputing | Facilities | ORNL  

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

facilities, and authorization checks for physical access. An integrated cyber security plan encompasses all aspects of computing. Cyber security plans are risk-based....

352

ARM - Facility News Article  

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

the website still features the familiar faces of Professor Polar Bear, Teacher Turtle, and PI Prairie Dog (each representing an ARM Climate Research Facility site), but now...

353

ARM - Facility News Article  

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

(left) and 2-channel (right) NFOV radiometers are collocated with the infrared thermometer (green stripe) at the SGP Central Facility. Numerous other instruments are situated...

354

Mixed Waste Management Facility (MWMF) groundwater monitoring report. Second quarter 1993  

SciTech Connect (OSTI)

Groundwater monitoring continued at the Savannah River Plant. During second quarter 1993, nine constituents exceeded final Primary Drinking Water Standards in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility, the Old Burial Ground, the E-Area Vaults, and the proposed Hazardous Waste/Mixed Waste Disposal Vaults. As in previous quarters, tritium and trichloroethylene were the most widespread constituents. Chloroethene (vinyl chloride), dichloromethane (methylene chloride), 1,1-dichloroethylene, gross alpha, lead, nonvolatile beta, or tetrachloroethylene also exceeded standards in one or more wells. The groundwater flow directions and rates in the three hydrostratigraphic units were similar to those of previous quarters.

Not Available

1993-09-01T23:59:59.000Z

355

Evidence for Stratification of Deuterium-Tritium Fuel in Inertial Confinement Fusion Implosions  

E-Print Network [OSTI]

Measurements of the D(d,p)T (dd) and T(t,2n)[superscript 4]He (tt) reaction yields have been compared with those of the D(t,n)[superscript 4]He (dt) reaction yield, using deuterium-tritium gas-filled inertial confinement ...

Casey, Daniel Thomas

356

PPPL-3458 PPPL-3458 Visual Tritium Imaging Of In-Vessel Surfaces  

E-Print Network [OSTI]

on the U.S. Department of Energy's Princeton Plasma Physics Laboratory Publications and Reports web site and DOE Contractors can obtain copies of this report from: U.S. Department of Energy Office of Scientific Energy Research Institute, Tritium Engineering Laboratory, Tokai, Ibaraki 319-1195, Japan Abstract

357

Tritium Precipitation in European Cities and in Osaka, Japan Owing to the Chernobyl Nuclear Accident  

Science Journals Connector (OSTI)

......Japan Owing to the Chernobyl Nuclear Accident Taeko Koga Hiroshige...Takeo Niwa Hiroshi Kawai Atomic Energy Research Institute, Kinki...before and after the Chernobyl nuclear plant accident by the time...after the accident. Chernobyl nuclear plant accident|Tritium precipitation......

Taeko Koga; Hiroshige Morishima; Takeo Niwa; Hiroshi Kawai

1991-09-01T23:59:59.000Z

358

UNCLASSIFIED TPBAR RELEASES, INCLUDING TRITIUM TTQP-1-091 Rev 14  

SciTech Connect (OSTI)

This document provides a listing of unclassified tritium release values that should be assumed for unclassified analysis. Much of the information is brought forth from the related documents listed in Section 5.0 to provide a single-source listing of unclassified release values. This information has been updated based on current design analysis and available experimental data.

Gruel, Robert L.; Love, Edward F.; Thornhill, Cheryl K.

2012-07-01T23:59:59.000Z

359

PPPL3157 Preprint Date: March 1996, UC421, 423, 426 Investigations of the Tritium Recycling  

E-Print Network [OSTI]

1 PPPL­3157 ­ Preprint Date: March 1996, UC­421, 423, 426 Investigations of the Tritium Recycling material to be ejected into the plasma. This recycling of plasma fuel, which occurs primarily on the inner influx from the edge. Despite its importance, a full understanding of the factors influencing recycling

360

TRITIUM RECYCLING AND INVENTORY IN ERODED DEBRIS OF PLASMA-FACING MATERIALS*  

E-Print Network [OSTI]

.,, TRITIUM RECYCLING AND INVENTORY IN ERODED DEBRIS OF PLASMA-FACING MATERIALS* Ahmed Hassanein. Invited Paper at Advanced Research Workshop on HYDROGEN RECYCLE AT PLASMA FACING MATERIALS Sept. 15 RECYCLING AND INVENTORY IN ERODED DEBRIS OF PLASMA-FACING MATERIALS AmvlED H.ASSANEIN Argonne Mm

Harilal, S. S.

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

PPPL-3157 -Preprint Date: March 1996, UC-421, 423, 426 Investigations of the Tritium Recycling  

E-Print Network [OSTI]

1 PPPL-3157 - Preprint Date: March 1996, UC-421, 423, 426 Investigations of the Tritium Recycling material to be ejected into the plasma. This recycling of plasma fuel, which occurs primarily on the inner influx from the edge. Despite its importance, a full understanding of the factors influencing recycling

362

Effect of Nuclear Data Libraries on Tritium Breeding in a (D–T) Fusion Driven Reactor  

Science Journals Connector (OSTI)

In design a Deuterium–Tritium (D–T) fusion driven hybrid reactor, neutronics and nuclear data libraries have an...2O, LiH, Li2TiO3, Li2ZrO3 and Li4SiO4 in a (D–T) driven fusion–fission (hybrid) reactor is investi...

Adem Ac?r

2008-12-01T23:59:59.000Z

363

Fusion Nuclear Schience Facility-AT: A Material And Component Testing Device  

SciTech Connect (OSTI)

A Fusion Nuclear Science Facility (FNSF) is a necessary complement to ITER, especially in the area of materials and components testing, needed for DEMO design development. FNSF-AT, which takes advantage of advanced tokamak (AT) physics should have neutron wall loading of 1-2 MW/m2, continuous operation for periods of up to two weeks, a duty factor goal of 0.3 per year and an accumulated fluence of 3-6 MW-yr/m2 (~30-60 dpa) in ten years to enable the qualification of structural, blanket and functional materials, components and corresponding ancillary equipment necessary for the design and licensing of a DEMO. Base blankets with a ferritic steel structure and selected tritium blanket materials will be tested and used for the demonstration of tritium sufficiency. Additional test ports at the outboard mid-plane will be reserved for test blankets with advanced designs or exotic materials, and electricity production for integrated high fluence testing in a DT fusion spectrum. FNSF-AT will be designed using conservative implementations of all elements of AT physics to produce 150-300 MW fusion power with modest energy gain (Q<7) in a modest sized normal conducting coil device. It will demonstrate and help to select the DEMO plasma facing, structural, tritium breeding, functional materials and ancillary equipment including diagnostics. It will also demonstrate the necessary tritium fuel cycle, design and cooling of the first wall chamber and divertor components. It will contribute to the knowledge on material qualification, licensing, operational safety and remote maintenance necessary for DEMO design

Wong, C. P.; Chan, V. S.; Garofalo, A. M.; Stambaugh, Ron; Sawan, M.; Kurtz, Richard J.; Merrill, Brad

2012-07-01T23:59:59.000Z

364

Heat Exchanger Design Options and Tritium Transport Study for the VHTR System  

SciTech Connect (OSTI)

This report presents the results of a study conducted to consider heat exchanger options and tritium transport in a very high temperature reactor (VHTR) system for the Next Generation Nuclear Plant Project. The heat exchanger options include types, arrangements, channel patterns in printed circuit heat exchangers (PCHE), coolant flow direction, and pipe configuration in shell-and-tube designs. Study considerations include: three types of heat exchanger designs (PCHE, shell-and-tube, and helical coil); single- and two-stage unit arrangements; counter-current and cross flow configurations; and straight pipes and U-tube designs in shell-and-tube type heat exchangers. Thermal designs and simple stress analyses were performed to estimate the heat exchanger options, and the Finite Element Method was applied for more detailed calculations, especially for PCHE designs. Results of the options study show that the PCHE design has the smallest volume and heat transfer area, resulting in the least tritium permeation and greatest cost savings. It is theoretically the most reliable mechanically, leading to a longer lifetime. The two-stage heat exchanger arrangement appears to be safer and more cost effective. The recommended separation temperature between first and second stages in a serial configuration is 800oC, at which the high temperature unit is about one-half the size of the total heat exchanger core volume. Based on simplified stress analyses, the high temperature unit will need to be replaced two or three times during the plant’s lifetime. Stress analysis results recommend the off-set channel pattern configuration for the PCHE because stress reduction was estimated at up to 50% in this configuration, resulting in a longer lifetime. The tritium transport study resulted in the development of a tritium behavior analysis code using the MATLAB Simulink code. In parallel, the THYTAN code, previously performed by Ohashi and Sherman (2007) on the Peach Bottom data, was revived and verified. The 600 MWt VHTR core input file developed in preparation for the transient tritium analysis of VHTR systems was replaced with the original steady-state inputs for future calculations. A Finite Element Method analysis was performed using COMSOL Multiphysics software to accurately predict tritium permeation through the PCHE type heat exchanger walls. This effort was able to estimate the effective thickness for tritium permeations and develop a correlation for general channel configurations, which found the effective thickness to be much shorter than the average channel distance because of dead spots on the channel side.

Chang H. Oh; Eung S. Kim

2008-09-01T23:59:59.000Z

365

ANALYSIS OF THE TRITIUM-WATER (T-H20) SYSTEM FOR A FUSION MATERIAL TEST FACILITY  

E-Print Network [OSTI]

the best itvailable copy. Available lo I)()E and I)()E Ct)lllritclc)_"st"1"+,)111the ()rf ice of Scientific into a lithium target to produce

Harilal, S. S.

366

Science &Technology Facilities Council  

E-Print Network [OSTI]

and Science & Technology Facilities Council invite you to The ESA Technology Transfer Network SpaceTech2012Science &Technology Facilities Council Innovations Issue 31 October 2012 This issue: 1 STFC International prize for `no needles' breast cancer diagnosis technique 6 CEOI Challenge Workshop ­ Current

367

Nanotechnology User Facility for  

E-Print Network [OSTI]

A National Nanotechnology User Facility for Industry Academia Government #12;The National Institute of Commerce's nanotechnology user facility. The CNST enables innovation by providing rapid access to the tools new measurement and fabrication methods in response to national nanotechnology needs. www

368

Facilities Management CAD Standards  

E-Print Network [OSTI]

Facilities Management CAD Standards 2011 #12;Facilities Management CAD Standards Providing: Layering Standards 2.1 Layer Name Format 2.2 Layer Name Modifiers 2.3 Layer Attributes 2.4 Special Layer of PDF and DWG Files APPENDIX A: DAL FM CAD Standard Layers APPENDIX B: DAL FM CAD Special Layers

Brownstone, Rob

369

Cornell University Facilities Services  

E-Print Network [OSTI]

requirements, building code, and sustainability objectives. This plan takes a long- term view, projecting workCornell University Facilities Services Contract Colleges Facilities Fernow and Rice Hall in Fernow, Rice, Bruckner, Bradfield and Plant Science buildings. It includes a surging and phasing plan

Manning, Sturt

370

Emergency Facilities and Equipment  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This volume clarifies requirements of DOE O 151.1 to ensure that emergency facilities and equipment are considered as part of emergency management program and that activities conducted at these emergency facilities are fully integrated. Canceled by DOE G 151.1-4.

1997-08-21T23:59:59.000Z

371

Privacy Impact Assessment OFEO Facilities Management System Facilities Center  

E-Print Network [OSTI]

Privacy Impact Assessment OFEO Facilities Management System ­ Facilities Center I. System Identification 1. IT System Name: Facilities Management System - FacilityCenter 2. IT System Sponsor: Office. IT System Manager: Michelle T. Gooch, Facilities Management Systems Manager 5. PIA Author: Michelle T. Gooch

Mathis, Wayne N.

372

Tritium Transport at the Rulison Site, a Nuclear-stimulated Low-permeability Natural Gas Reservoir  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) and its predecessor agencies conducted a program in the 1960s and 1970s that evaluated technology for the nuclear stimulation of low-permeability natural gas reservoirs. The second project in the program, Project Rulison, was located in west-central Colorado. A 40-kiltoton nuclear device was detonated 2,568 m below the land surface in the Williams Fork Formation on September 10, 1969. The natural gas reservoirs in the Williams Fork Formation occur in low permeability, fractured sandstone lenses interbedded with shale. Radionuclides derived from residual fuel products, nuclear reactions, and activation products were generated as a result of the detonation. Most of the radionuclides are contained in a cooled, solidified melt glass phase created from vaporized and melted rock that re-condensed after the test. Of the mobile gas-phase radionuclides released, tritium ({sup 3}H or T) migration is of most concern. The other gas-phase radionuclides ({sup 85}Kr, {sup 14}C) were largely removed during production testing in 1969 and 1970 and are no longer present in appreciable amounts. Substantial tritium remained because it is part of the water molecule, which is present in both the gas and liquid (aqueous) phases. The objectives of this work are to calculate the nature and extent of tritium contamination in the subsurface from the Rulison test from the time of the test to present day (2007), and to evaluate tritium migration under natural-gas production conditions to a hypothetical gas production well in the most vulnerable location outside the DOE drilling restriction. The natural-gas production scenario involves a hypothetical production well located 258 m horizontally away from the detonation point, outside the edge of the current drilling exclusion area. The production interval in the hypothetical well is at the same elevation as the nuclear chimney created by the detonation, in order to evaluate the location most vulnerable to tritium migration.

C. Cooper; M. Ye; J. Chapman

2008-04-01T23:59:59.000Z

373

ARM - Facility News Article  

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

30, 2007 [Facility News] 30, 2007 [Facility News] High-Speed Internet Deflects Information Overload Bookmark and Share Covering approximately 143,000 square kilometers in Oklahoma and Kansas, instruments at the various facilities throughout the SGP site generate approximately 27 gigabytes of data every day. Covering approximately 143,000 square kilometers in Oklahoma and Kansas, instruments at the various facilities throughout the SGP site generate approximately 27 gigabytes of data every day. A little more room in the internet link at the ARM Southern Great Plains site is providing needed relief to the crowded lines that keep data flowing from the site. In July 2007, the internet service from the SGP Central Facility was switched to a higher speed (6 megabits) link, increasing the

374

ARM - Facility News Article  

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

, 2009 [Facility News] , 2009 [Facility News] Mobile Facility Begins Marine Cloud Study in the Azores Bookmark and Share Located next to the airport on Graciosa Island, the ARM Mobile Facility's comprehensive and sophisticated instrument suite will obtain atmospheric measurements from the marine boundary layer. Located next to the airport on Graciosa Island, the ARM Mobile Facility's comprehensive and sophisticated instrument suite will obtain atmospheric measurements from the marine boundary layer. Extended deployment will obtain seasonal statistics to improve climate models Today marks the beginning of a 20-month field campaign on Graciosa Island in the Azores to study the seasonal life cycle of marine clouds and how they modulate the global climate system. Sponsored by the U.S. Department

375

BNL | Research Facilities  

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

Brookhaven's Research Facilities Brookhaven's Research Facilities Tools of Discovery Brookhaven National Lab excels at the design, construction, and operation of large-scale, cutting-edge research facilities-some available nowhere else in the world. Each year, thousands of scientists from laboratories, universities, and industries around the world use these facilities to delve into the basic mysteries of physics, chemistry, biology, materials science, energy, and the environment-and develop innovative applications that arise, sometimes at the intersections of these disciplines. construction Brookhaven Lab is noted for the design, construction and operation of large-scale, cutting-edge research facilities that support thousands of scientists worldwide. RHIC tunnel Relativistic Heavy Ion Collider

376

ARM Aerial Facility  

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

govSitesAerial Facility govSitesAerial Facility AAF Information Proposal Process Science (PDF) Baseline Instruments Campaign Instruments Instrumentation Workshop 2008 AAF Fact Sheet G-1 Fact Sheet Images Field Campaigns AAF Campaigns 2007 - UAV Campaigns 1993 - 2006, 2015 Other Aircraft Campaigns 1993 - 2010 AAF Contacts Rickey Petty DOE AAF Program Director Beat Schmid Technical Director ARM Aerial Facility Numerous instrumented aircraft participated in CLASIC, a cross-disciplinary interagency research effort. Numerous instrumented aircraft participated in CLASIC, a cross-disciplinary interagency research effort. As an integral measurement capability of the ARM Climate Research Facility, the ARM Aerial Facility (AAF) provides airborne measurements required to answer science questions proposed by the ARM Science Team and the external

377

ARM - Facility News Article  

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

15, 2010 [Facility News] 15, 2010 [Facility News] Water Vapor Network at SGP Site Goes Offline Bookmark and Share Each of the 24 solar-powered GPS stations streamed data via a wireless network to the SGP Central Facility for data collection and storage. Each of the 24 solar-powered GPS stations streamed data via a wireless network to the SGP Central Facility for data collection and storage. After nearly eleven years, the Single Frequency GPS Water Vapor Network field campaign at the ARM Southern Great Plains (SGP) site came to a close on July 1, 2010. Installed between 1999 and 2000, this network consisted of 24 GPS stations operating within an 8-kilometer radius around the SGP Central Facility near Lamont, Oklahoma. Developed to function as a single instrument, the network simultaneously measured "slant water vapor" in

378

ARM - Facility News Article  

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

30, 2005 [Facility News] 30, 2005 [Facility News] Coastal Clouds Field Campaign Takes Off in July Bookmark and Share The 2-channel NFOV gets careful attention as it joins the suite of instruments collecting data for the ARM Mobile Facility field campaign at Point Reyes National Seashore. The 2-channel NFOV gets careful attention as it joins the suite of instruments collecting data for the ARM Mobile Facility field campaign at Point Reyes National Seashore. Since March 2005, the ARM Mobile Facility (AMF) has been at Point Reyes National Seashore in northern California for the Marine Stratus Radiation, Aerosol, and Drizzle Intensive Operational Period. The goals of this 6-month field campaign are to collect data from cloud/aerosol interactions and to improve understanding of cloud organization that is often associated

379

NSA Barrow Facility  

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

Barrow Facility Barrow Facility NSA Related Links Facilities and Instruments Barrow Atqasuk ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Images Information for Guest Scientists Contacts NSA Barrow Facility Location: 71° 19' 23.73" N, 156° 36' 56.70" W Altitude: 8 meters The Barrow facility was dedicated in July 1997 and chosen because the Arctic is particularly sensitive to climate changes. Barrow is located at the northernmost point in the United States, 330 miles north of the Arctic Circle. Also known as the Top of the World, Barrow is Alaska's largest Eskimo village (home to 4,581 people). Tax revenue from the Slope's oil fields pay for services borough wide, and natural gas is used to heat homes and generate electricity in Barrow. Many residents, however, maintain

380

ARM - Facility News Article  

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

25, 2013 [Education, Facility News] 25, 2013 [Education, Facility News] Junior Rangers Enjoy Science Education at ARM Facility on Cape Cod Bookmark and Share Children and adults join in the balloon launch countdown at the ARM Mobile Facility site at Cape Cod National Seashore. Weather balloons are launched at regular intervals four times per day throughout the one-year campaign. Children and adults join in the balloon launch countdown at the ARM Mobile Facility site at Cape Cod National Seashore. Weather balloons are launched at regular intervals four times per day throughout the one-year campaign. School break means vacation, and around Cape Cod, that often means a trip to the seashore. On April 17, families looking for fun and educational outdoor activities spent several hours at Cape Cod National Seashore's

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

ARM - NSA Barrow Facility  

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

Barrow Facility Barrow Facility NSA Related Links Facilities and Instruments Barrow Atqasuk ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Images Information for Guest Scientists Contacts NSA Barrow Facility Location: 71° 19' 23.73" N, 156° 36' 56.70" W Altitude: 8 meters The Barrow facility was dedicated in July 1997 and chosen because the Arctic is particularly sensitive to climate changes. Barrow is located at the northernmost point in the United States, 330 miles north of the Arctic Circle. Also known as the Top of the World, Barrow is Alaska's largest Eskimo village (home to 4,581 people). Tax revenue from the Slope's oil fields pay for services borough wide, and natural gas is used to heat homes and generate electricity in Barrow. Many residents, however, maintain

382

ARM - Facility News Article  

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

May 15, 2004 [Facility News] May 15, 2004 [Facility News] Mid-latitude Cirrus Cloud Experiment Underway Bookmark and Share NASA's WB-57F research aircraft can carry an instrument payload up to 6,000 lbs. NASA's WB-57F research aircraft can carry an instrument payload up to 6,000 lbs. In late April, scientific collaborators at the National Aeronautics and Space Administration (NASA) carried out two high-altitude flights over the ARM Climate Research Facility Southern Great Plains (SGP) central facility. The purpose of these flights was to use a new suite of cloud property probes on the WB-57F aircraft to more accurately characterize the properties of mid-latitude cirrus clouds-which are composed solely of ice crystals-than has previously been possible. Eight flights over the SGP central facility were originally planned, but the expected cirrus clouds

383

FACILITY SAFETY (FS)  

Broader source: Energy.gov (indexed) [DOE]

FACILITY SAFETY (FS) FACILITY SAFETY (FS) OBJECTIVE FS.1 - (Core Requirement 7) Facility safety documentation in support of SN process operations,is in place and has been implemented that describes the safety envelope of the facility. The, safety documentation should characterize the hazards/risks associated with the facility and should, identify preventive and mitigating measures (e.g., systems, procedures, and administrative, controls) that protect workers and the public from those hazards/risks. (Old Core Requirement 4) Criteria 1. A DSA has been prepared by FWENC, approved by DOE, and implemented to reflect the SN process operations in the WPF. (10 CFR 830.200, DOE-STD-3009-94) 2. A configuration control program is in place and functioning such that the DSA is

384

ARM - Facility News Article  

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

7, 2009 [Facility News] 7, 2009 [Facility News] Town Hall Meeting at AGU 2009 Fall Meeting Bookmark and Share ARM Climate Research Facility - New Measurement Capabilities for Climate Research Thursday, December 17, 6:15-7:15 pm, Moscone West Room 2002 American Recovery and Reinvestment Act American Recovery and Reinvestment Act Scientists from around the world use data from the ARM Climate Research Facility to study the interactions between clouds, aerosol and radiation. Through the American Recovery and Reinvestment Act of 2009, the DOE Office of Science received $1.2 billion, with $60 million allocated to the ARM Climate Research Facility. With these funds, ARM will purchase and deploy dual-frequency scanning cloud radars to all the ARM sites, enhance several sites with precipitation radars and energy flux measurement capabilities,

385

Thermal-hydraulic design of the target/blanket for the accelerator production of tritium conceptual design  

SciTech Connect (OSTI)

A conceptual design was developed for the target/blanket system of an accelerator-based system to produce tritium. The target/blanket system uses clad tungsten rods for a spallation target and clad lead rods as a neutron multiplier in a blanket surrounding the target. The neutrons produce tritium in {sup 3}He, which is contained in aluminum tubes located in the decoupler and blanket regions. This paper presents the thermal-hydraulic design of the target, decoupler, and blanket developed for the conceptual design of the Accelerator Production of Tritium Project, and demonstrates there is adequate margin in the design at full power operation.

Willcutt, G.J.E. Jr.; Kapernick, R.J.

1997-11-01T23:59:59.000Z

386

Calibration Facilities | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Calibration Facilities Calibration Facilities Calibration Facilities Calibration Facilities Calibration Facilities Calibration Facilities Calibration Facilities DOE supports the development, standardization, and maintenance of calibration facilities for environmental radiation sensors. Radiation standards at the facilities are primarily used to calibrate portable surface gamma-ray survey meters and borehole logging instruments used for uranium and other mineral exploration and remedial action measurements. Standards for calibrating borehole fission neutron devices are also available, but are used infrequently. Radiation standards are constructed of concrete with elevated, uniform concentrations of naturally occurring potassium, uranium, and/or thorium. Pad standards have large, flat surfaces suitable for calibration

387

RCRA facility assessments  

SciTech Connect (OSTI)

The Hazardous and Solid Waste Amendments of 1984 (HSWA) broadened the authorities of the Resource Conservation and Recovery Act (RCRA) by requiring corrective action for releases of hazardous wastes and hazardous constituents at treatment, storage, and disposal (TSD) facilities. The goal of the corrective action process is to ensure the remediation of hazardous waste and hazardous constituent releases associated with TSD facilities. Under Section 3004(u) of RCRA, operating permits issued to TSD facilities must address corrective actions for all releases of hazardous waste and hazardous constituents from any solid waste management unit (SWMU) regardless of when the waste was placed in such unit. Under RCRA Section 3008(h), the Environmental Protection Agency (EPA) may issue administrative orders to compel corrective action at facilities authorized to operate under RCRA Section 3005(e) (i.e., interim status facilities). The process of implementing the Corrective Action program involves the following, in order of implementation; (1) RCRA Facility Assessment (RFA); (2) RCRA Facility Investigation (RFI); (3) the Corrective Measures Study (CMS); and (4) Corrective Measures Implementation (CMI). The RFA serves to identify and evaluate SWMUs with respect to releases of hazardous wastes and hazardous constituents, and to eliminate from further consideration SWMUs that do not pose a threat to human health or the environment. This Information Brief will discuss issues concerning the RFA process.

NONE

1994-07-01T23:59:59.000Z

388

Supercomputing | Facilities | ORNL  

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

Facilities and Capabilities Facilities and Capabilities Primary Systems Infrastructure High Performance Storage Supercomputing and Computation Home | Science & Discovery | Supercomputing and Computation | Facilities and Capabilities | High Performance Storage SHARE High Performance Storage and Archival Systems To meet the needs of ORNL's diverse computational platforms, a shared parallel file system capable of meeting the performance and scalability require-ments of these platforms has been successfully deployed. This shared file system, based on Lustre, Data Direct Networks (DDN), and Infini-Band technologies, is known as Spider and provides centralized access to petascale datasets from all major on-site computational platforms. Delivering more than 240 GB/s of aggregate performance,

389

ARM - Facility News Article  

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

July 10, 2012 [Facility News] July 10, 2012 [Facility News] Collaborations in Atmospheric Science and Observations Discussed in Germany Bookmark and Share Susanne Crewell (center) is flanked by Jimmy Voyles (left) and Shaocheng Xie (right) during a tour of the Research Center Juelich and the university's Jülich ObservatorY for Cloud Evolution (JOYCE) site. Crewell explained that JOYCE, like ARM facilities, was designed for long-term continuous measurements of cloud, radiation, boundary humidity, and precipitation, using active and passive remote sensing instruments. Susanne Crewell (center) is flanked by Jimmy Voyles (left) and Shaocheng Xie (right) during a tour of the Research Center Juelich and the

390

Test Facility Daniil Stolyarov, Accelerator Test Facility User...  

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

Development of the Solid-State Laser System for the Accelerator Test Facility Daniil Stolyarov, Accelerator Test Facility User's Meeting April 3, 2009 Outline Motivation for...

391

NREL: Research Facilities - Laboratories and Facilities by Technology  

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

Laboratories and Facilities by Technology The following NREL research programs have laboratory, andor test and user facility capabilities for researching, developing, and testing...

392

NREL: Research Facilities Home Page  

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

NREL Research Facilities Here you'll find information about the National Renewable Energy Laboratory's R&D facility and laboratory capabilities. These state-of-the-art facilities...

393

Tritium production analysis and management strategies for a Fluoride-salt-cooled high-temperature test reactor (FHTR)  

E-Print Network [OSTI]

The Fluoride-salt-cooled High-temperature Test Reactor (FHTR) is a test reactor concept that aims to demonstrate the neutronics, thermal-hydraulics, materials, tritium management, and to address other reactor operational ...

Rodriguez, Judy N

2013-01-01T23:59:59.000Z

394

ARM - Facility News Article  

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

27, 2009 [Facility News] 27, 2009 [Facility News] Arrival of Recovery Act Funds Sets Wheels In Motion Bookmark and Share So that people can easily recognize the effects of the American Recovery and Reinvestment Act, all projects will be stamped with the Recovery Act logo. So that people can easily recognize the effects of the American Recovery and Reinvestment Act, all projects will be stamped with the Recovery Act logo. Through the American Recovery and Reinvestment Act of 2009 (aka stimulus), the Department of Energy's Office of Science received $1.2 billion. In late May, DOE released approximately $54 million-90 percent-of the $60 million allocated to the ARM Climate Research Facility. During the next 18 months, the ARM Climate Research Facility will purchase and deploy dual-frequency scanning cloud radars to all the ARM sites, enhance several

395

ARM - Facility News Article  

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

28, 2005 [Facility News] 28, 2005 [Facility News] Readiness of New Lidar Evaluated at Southern Great Plains Site Bookmark and Share Aircraft for the Boundary Layer CO2 Intensive Operational Period will fly over the SGP Central Facility using both spirals and racetrack patterns. Data will be collected under a variety of cloud and meteorological conditions. Aircraft for the Boundary Layer CO2 Intensive Operational Period will fly over the SGP Central Facility using both spirals and racetrack patterns. Data will be collected under a variety of cloud and meteorological conditions. As the focus of the Boundary Layer Carbon Dioxide (CO2) Intensive Operational Period (IOP) starting in March, science collaborators at ITT Industries and the National Aeronautics and Space Administration (NASA)

396

ARM - Facility News Article  

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

Annual Quality Improvement Inspections Take Place Annual Quality Improvement Inspections Take Place Bookmark and Share During the SGP site audit conducted in April 2005, a member of the Continuous Quality Improvement Program team is accompanied by a local jackrabbit at the Ringwood Extended Facility. During the SGP site audit conducted in April 2005, a member of the Continuous Quality Improvement Program team is accompanied by a local jackrabbit at the Ringwood Extended Facility. The Continuous Quality Improvement Program (CQIP) implemented by the ARM Program in 1998 requires annual audits and inspection visits to each of the ARM Climate Research Facility Southern Great Plains (SGP) site's 27 field facilities located in Oklahoma and Kansas. A small team of scientists and engineers conduct the inspections each year to evaluate the field

397

PNNL: About PNNL - Facilities  

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

Scientific Facilities Scientific Facilities At PNNL, we offer scientific researchers access to unique equipment housed in state-of-the-art facilities as well as onsite experts to help visiting researchers take advantage of and make best use of the capabilities. You also have the opportunity to collaborate with our world-renowned scientists and engineers who can help you advance your scientific research and publish your results. Take a virtual tour of some of our laboratories. William R. Wiley Environmental Molecular Sciences Laboratory (EMSL) EMSL EMSL is a U.S. Department of Energy (DOE) national user facility currently shared and used by researchers from around the world. Research at EMSL focuses principally on developing a molecular-level understanding of the physical, chemical, and biological processes that underlie the most

398

ARM - Facility News Article  

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

New Backup Software Improves Processing, Reliability at Data Management New Backup Software Improves Processing, Reliability at Data Management Facility Bookmark and Share Real-time data from all three of the ARM Climate Research Facility sites (North Slope of Alaska, Southern Great Plains, and Tropical Western Pacific) are collected and processed at the ARM Climate Research Facility Data Management Facility (DMF) each day. Processing involves the application of algorithms for performing simple averaging routines, qualitative comparisons, or more complicated experimental calculations. With continual advances in computer technology, keeping up with the volume and pace of incoming data is a daunting challenge. And because the remote sites do not provide backups, reliable backups of these data at the DMF are critical. In addition, significant numbers of value-added datasets are

399

ARM - Facility News Article  

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

Mobile Facility Beta Testing Complete; System Headed to California Seashore Mobile Facility Beta Testing Complete; System Headed to California Seashore Bookmark and Share A key addition to the ARM Climate Research Facility scientific infrastructure is ready to roll...literally. In February, the ARM Mobile Facility (AMF) is being packed up and shipped from Richland, Washington, to the Point Reyes National Seashore north of San Francisco, California. There, it will be reassembled in preparation for its first deployment as part of a 6-month experiment to study the microphysical characteristics of marine stratus clouds, and in particular, marine stratus drizzle processes. Throughout the deployment, the AMF will accommodate aerosol observing equipment for National Oceanic and Atmospheric Administration (NOAA) researchers co-sponsored by ARM and the DOE Aerosol Science Program.

400

ARM - Facility News Article  

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

Review of ARM Infrastructure Completed Review of ARM Infrastructure Completed Bookmark and Share In May, the Department of Energy's Biological and Environmental Research Advisory Committee (BERAC) published findings and recommendations from their assessment of the effectiveness of ARM Climate Research Facility as a national scientific user facility. Based on a review of total user requests, the BERAC concluded that ARM was being effectively used by the broader scientific community, not just the ARM Program. They also stated that cost cutting measures had achieved the desired efficiency goals, but further cuts could impair the Facility's operations. The subcommittee reinforced the importance of the scientific impacts of this facility (including publications), and the value it has had for the international

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

ARM - Facility News Article  

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

March 1, 2012 [Facility News] March 1, 2012 [Facility News] Arctic Storm Samples Show Relationship Between Sea Ice and Precipitation Over Land Bookmark and Share Walter Brower, Barrow site facilities manager for ARM, cleans the sampling surface in preparation for the next snow storm. Visible in the background is the site's automated weather balloon launcher. Walter Brower, Barrow site facilities manager for ARM, cleans the sampling surface in preparation for the next snow storm. Visible in the background is the site's automated weather balloon launcher. As an important component of Earth's climate system, sea ice has a particularly strong influence on the Arctic sea surface temperature, evaporation, and reflectivity, or "albedo." The critical relationship among sea ice, evaporation, and precipitation is linked to a number of

402

ARM - Facility News Article  

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

April 30, 2008 [Facility News] April 30, 2008 [Facility News] ARM Outreach Materials Chosen for Earth Day Display in Washington DC Bookmark and Share Posters for the ARM Mobile Facility and ARM Education and Outreach were selected for the 2008 Earth Day display at DOE Headquarters. Posters for the ARM Mobile Facility and ARM Education and Outreach were selected for the 2008 Earth Day display at DOE Headquarters. Earth Day is officially honored each year on April 22, however, many groups sponsor activities throughout the entire month of April. At DOE Headquarters in Washington DC, two ARM posters were selected to join a poster display representing programs from numerous DOE offices. The display was featured in the Forrestal Building's ground-level and first floor lobby areas throughout the week of April 21. The posters were then displayed at

403

ARM - Facility News Article  

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

15, 2007 [Facility News] 15, 2007 [Facility News] Microwave Radiometers Put to the Test in Germany Bookmark and Share A 2-channel microwave radiometer (left) and a 12-channel microwave radiometer profiler (right) are part of a larger collection of instruments deployed at the ARM Mobile Facility site in Heselbach, Germany, in 2007. A 2-channel microwave radiometer (left) and a 12-channel microwave radiometer profiler (right) are part of a larger collection of instruments deployed at the ARM Mobile Facility site in Heselbach, Germany, in 2007. Microwave radiometers (MWRs) are instruments used to measure emissions of water vapor and liquid water molecules in the atmosphere at specific microwave frequencies. Different MWRs are used to measure various frequencies, but the accuracy of all their retrievals is somewhat suspect,

404

MAX Fluid Dynamics facility  

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

MAX Fluid Dynamics facility MAX Fluid Dynamics facility Capabilities Engineering Experimentation Reactor Safety Testing and Analysis Overview Nuclear Reactor Severe Accident Experiments MAX NSTF SNAKE Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr MAX Fluid Dynamics facility Providing high resolution data for development of computational tools that model fluid flow and heat transfer within complex systems such as the core of a nuclear reactor. 1 2 3 4 5 Hot and cold air jets are mixed within a glass tank while laser-based anemometers and a high-speed infrared camera characterize fluid flow and heat transfer behavior. Click on image to view larger size image.

405

ARM - Facility News Article  

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

15, 2007 [Facility News] 15, 2007 [Facility News] Commercial Infrared Sky Imagers Compared Bookmark and Share Three of the four instruments used in the sky imager intercomparison are visible in this photo taken on the Guest Instrument Facility platform at the SGP site. They are the Solmirus All Sky Infrared Visible Analyzer (foreground); Heitronics Nubiscope (top right); and Atmos Cloud Infrared Radiometer-4 (far left). Three of the four instruments used in the sky imager intercomparison are visible in this photo taken on the Guest Instrument Facility platform at the SGP site. They are the Solmirus All Sky Infrared Visible Analyzer (foreground); Heitronics Nubiscope (top right); and Atmos Cloud Infrared Radiometer-4 (far left). Four infrared imaging instruments were installed and operated at the ARM

406

ARM - Facility News Article  

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

1, 2011 [Facility News] 1, 2011 [Facility News] Data from Field Campaign in Black Forest, Germany, are Red Hot Bookmark and Share During COPS, the ARM Mobile Facility operated in Heselbach, Germany, obtaining measurements encompassing the entire life cycle of precipitation. The AMF site also hosted a number of guest instruments for supplemental field campaigns throughout the deployment. During COPS, the ARM Mobile Facility operated in Heselbach, Germany, obtaining measurements encompassing the entire life cycle of precipitation. The AMF site also hosted a number of guest instruments for supplemental field campaigns throughout the deployment. A paper published in a special issue of the Quarterly Journal of the Royal Meteorological Society describing the scientific strategy, field phase, and

407

ARM - Facility News Article  

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

15, 2006 [Facility News] 15, 2006 [Facility News] Radar Wind Profiler Joins ARM Mobile Facility Instrument Suite Bookmark and Share This spring, a 915 MHz radar wind profiler (RWP) was successfully installed at the ARM Mobile Facility (AMF) site in Niamey, Niger, West Africa, for the remainder of the 1-year RADAGAST field campaign which started in January. The RWP will provide information about wind speed, wind direction, and wind shear, and also enable measurements of the turbulence in the lower part of the troposphere. This may be a key variable in determining the vertical distribution of dust in the experimental domain. Gradients in the radar's reflectivity spectrum may also help to provide continuous identification of the depth of the boundary layer in the summer months, when refractive gradients are likely to be maximized by low-level moisture.

408

ARM - Facility News Article  

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

April 30, 2006 [Facility News] April 30, 2006 [Facility News] Disdrometer Joins Tipping Bucket to Improve Precipitation Measurements Bookmark and Share At the SGP site, the disdrometer is installed near the site's main instrument cluster, approximately 50 feet east of the Central Facility. To avoid secondary splash contamination, the disdrometer's sensor cone is surrounded by splash-resistant material. At the SGP site, the disdrometer is installed near the site's main instrument cluster, approximately 50 feet east of the Central Facility. To avoid secondary splash contamination, the disdrometer's sensor cone is surrounded by splash-resistant material. This spring, a pair of new distrometers began collecting data at the ARM Southern Great Plains (SGP) site and the ARM Darwin site in the Tropical

409

ARM - Facility News Article  

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

December 3, 2004 [Facility News] December 3, 2004 [Facility News] First Deployment of ARM Mobile Facility to Occur on California Coast Bookmark and Share Image - Point Reyes Beach Image - Point Reyes Beach Point Reyes National Seashore, on the California coast north of San Francisco, has been identified as the official location for the first deployment of the DOE's Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF). As part of a 6-month field campaign beginning in March 2005 to study the microphysical characteristics of marine stratus and, in particular, marine stratus drizzle processes, the AMF will provide a mature instrument system to help fill information gaps in the existing limited surveys of marine stratus microphysical structure. Marine stratus clouds are known to be susceptible to the byproducts of fossil fuel consumption, a

410

ARM - Facility News Article  

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

9, 2013 [Facility News] 9, 2013 [Facility News] ARM Facility Shares Return on Science Investments Bookmark and Share The Bolger Center-a former U.S. Postal Service training center-hosted the fourth annual ASR Science Team Meeting in March. The Bolger Center-a former U.S. Postal Service training center-hosted the fourth annual ASR Science Team Meeting in March. To quote Ben Franklin, "If a man empties his purse into his head, no man can take it away from him. An investment in knowledge always pays the best interest." ARM Climate Research Facility staff who attended the fourth annual Atmospheric System Research (ASR) Science Team Meeting in April received a healthy dose of interest in March! With over 350 attendees presenting nearly 250 posters, the wealth of atmospheric climate science knowledge

411

ARM - Facility News Article  

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

May 20, 2011 [Facility News] May 20, 2011 [Facility News] From Snow to Sand; Mobile Facility Headed to the Maldives Bookmark and Share AMF2 operations team members pack up the 3-channel microwave radiometer at the STORMVEX valley floor site in Steamboat Springs, Colorado. AMF2 operations team members pack up the 3-channel microwave radiometer at the STORMVEX valley floor site in Steamboat Springs, Colorado. After spending six very snowy months at Steamboat Springs, Colorado, the second ARM Mobile Facility (AMF2) is switching gears and heading to the tropical climes of the Maldives in the Indian Ocean. In mid-April, the Storm Peak Lab Cloud Property Validation Experiment (STORMVEX) came to a close, ending the final chapter of the AMF2's maiden deployment. After packing up the instruments and data systems, the AMF2 team is now preparing

412

ARM - Facility News Article  

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

Satellite Service Conserves Cash Satellite Service Conserves Cash Bookmark and Share In April, operations personnel completed a series of cost-saving data communication changes at the ARM Climate Research Facility Southern Great Plains (SGP) locale. The T-1 telephone lines at the four SGP boundary facilities were replaced with satellite dish technology. This change still allows large data sets to be transferred at acceptable bandwidth but at substantial savings. Inexpensive satellite services now meet data transmission needs at the SGP boundary facilities. Inexpensive satellite services now meet data transmission needs at the SGP boundary facilities. Huge amounts of data are collected daily by SGP site instruments. These data must be transmitted rapidly and reliably from remote measurement

413

ARM - Facility News Article  

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

2, 2012 [Data Announcements, Facility News] 2, 2012 [Data Announcements, Facility News] Toolkit for ARM Radar Data Previewed at Workshop Bookmark and Share This data plot shows the height and north/south displacement of rain relative to the ARM Southern Great Plains site's Central Facility in Oklahoma. This retrieval used information from all three X-band scanning ARM precipitation radars at the SGP site and was performed using tools in the Python-ARM radar toolkit. Click on image to enlarge. This data plot shows the height and north/south displacement of rain relative to the ARM Southern Great Plains site's Central Facility in Oklahoma. This retrieval used information from all three X-band scanning ARM precipitation radars at the SGP site and was performed using tools in the Python-ARM radar toolkit. Click on image to enlarge.

414

ARM - Facility News Article  

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

March 31, 2009 [Facility News] March 31, 2009 [Facility News] New Sensors Installed for Cloud Radar Calibration at North Slope Bookmark and Share Located on the roof of the Guest Instrument Facility at the ARM Barrow site are the PARSIVEL (left) and POSS (right) instruments. Located on the roof of the Guest Instrument Facility at the ARM Barrow site are the PARSIVEL (left) and POSS (right) instruments. Cloud radars at the ARM sites provide important information about cloud properties and continue to evolve in providing climate researchers more complex data. This creates a greater need to know the absolute calibration of the radar reflectivity measurement. However, the large and immobile antenna for the millimeter wavelength cloud radar (MMCR) is impossible to point directly at a calibration target. At the ARM North Slope of Alaska

415

ARM - Facility News Article  

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

May 15, 2006 [Facility News] May 15, 2006 [Facility News] New Micropulse Lidars to Replace Old Ones; Deployments Begin at SGP Bookmark and Share A representative from Sigma Space Corporation demonstrates the operation of the new micropulse lidar to ARM instrument mentors and site operations technicians. A representative from Sigma Space Corporation demonstrates the operation of the new micropulse lidar to ARM instrument mentors and site operations technicians. On May 3, the first of seven new and upgraded micropulse lidars (MPLs) was deployed at the ARM Southern Great Plains (SGP) site's Central Facility. These seven identical systems (including one spare) will replace the existing MPLs deployed at facilities throughout the SGP site and include new polarization capability. The MPLs provide critical backscatter

416

Nuclear Facility Design  

Broader source: Energy.gov (indexed) [DOE]

Design Design FUNCTIONAL AREA GOAL: Headquarters and Field organizations and their contractors ensure that nuclear facilities are designed to assure adequate protection for the public, workers, and the environment from nuclear hazards. REQUIREMENTS: ï‚· 10 CFR 830.120 ï‚· 10 CFR 830 subpart B ï‚· DOE O 413.3 ï‚· DOE O 420.1B ï‚· DOE O 414.1C ï‚· DOE O 226.1 ï‚· DOE M 426.1 ï‚· DEAR 970-5404-2 Guidance: ï‚· DOE G 420.1-1 ï‚· Project Management Practices, Integrated Quality ( Rev E, June 2003) ï‚· DOE Implementation Plan for DNSB Recommendation 2004-2 Performance Objective 1: Contractor Program Documentation Contracts between and the contractors who operate nuclear facilities contain adequate requirements concerning the conduct of nuclear facility safety design for nuclear facility capital projects and major modifications and the

417

ARM - Facility News Article  

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

field campaign are now open. GOAMAZON is a deployment of the ARM Mobile Facility to Brazil beginning in 2014. The three calls are being issued in coordination by the U.S....

418

ARM - Facility News Article  

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

August 16, 2008 Facility News 21st Century "Paper Boy" Begins Delivering ARM News Bookmark and Share A reorganized ARM News Center now offers RSS feeds-subscription services...

419

ARM - Facility News Article  

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

Preparations Underway for 2007 ARM Mobile Facility Deployment in Germany Bookmark and Share In the Black Forest region of Germany, the COPS field campaign will cover an area of...

420

ARM - Facility News Article  

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

April 15, 2008 Facility News CLASIC Discussed at Workshop in Oklahoma Bookmark and Share Participants at the CLASIC workshop in March 2008 listen intently to one of the many...

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

NEW RENEWABLE FACILITIES PROGRAM  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION ` NEW RENEWABLE FACILITIES PROGRAM GUIDEBOOK March 2007 CEC-300 Executive Director Heather Raitt Technical Director RENEWABLE ENERGY OFFICE CALIFORNIA ENERGY COMMISSION Jeffrey D. Byron B.B. Executive Director Heather Raitt Technical Director RENEWABLE ENERGY OFFICE Mark

422

NEW RENEWABLE FACILITIES PROGRAM  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION NEW RENEWABLE FACILITIES PROGRAM GUIDEBOOK APRIL 2006 CEC-300 Director Heather Raitt Technical Director Renewable Energy Program Drake Johnson Office Manager Renewable Energy Office Valerie Hall Deputy Director Efficiency, Renewables, and Demand Analysis Division #12;These

423

ARM - Facility News Article  

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

and Share Researchers installed a continuous 222Rn monitor at the base of the 60-meter tower at the SGP Central Facility. A sampling tube connected to the tower supplies air...

424

NETL - Fuel Reforming Facilities  

ScienceCinema (OSTI)

Research using NETL's Fuel Reforming Facilities explores catalytic issues inherent in fossil-energy related applications, including catalyst synthesis and characterization, reaction kinetics, catalyst activity and selectivity, catalyst deactivation, and stability.

None

2014-06-27T23:59:59.000Z

425

ARM - Facility News Article  

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

3, 2014 Facility News New 3D Tour Brings Users to the Southern Great Plains Site...Virtually Bookmark and Share The virtual tour home page illustrates the full magnitude of the...

426

B Plant facility description  

SciTech Connect (OSTI)

Buildings 225B, 272B, 282B, 282BA, and 294B were removed from the B Plant facility description. Minor corrections were made for tank sizes and hazardous and toxic inventories.

Chalk, S.E.

1996-10-04T23:59:59.000Z

427

Photovoltaic Research Facilities  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy (DOE) funds photovoltaic (PV) research and development (R&D) at its national laboratory facilities located throughout the country. To encourage further innovation,...

428

ARM - Facility News Article  

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

at the SGP Central Facility. Radar wind profilers (RWPs) provide hourly measurements of wind speed and direction from 100 m to 5 km above the ground. Between 1992 and 1996, four...

429

ARM - Facility News Article  

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

October 15, 2007 Facility News Kelle Smith Replaces Jan Gunter as ExtraView Administrator Bookmark and Share Kelle Smith assumed the duties of ExtraView administrator after Jan...

430

ARM - Facility News Article  

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

January 15, 2006 [Facility News] January 15, 2006 [Facility News] ARM Mobile Facility Begins Year-Long Deployment in Africa Bookmark and Share Beginning on January 9, the ARM Mobile Facility began officially collecting atmospheric data from a location at the airport in Niamey, Niger, Africa. As part of the RADAGAST field campaign, the AMF will measure the effects of absorbing aerosols from desert dust in the dry season, and the effects of deep convective clouds and associated moisture loadings on the transmission of atmospheric radiation during the summer monsoon. These measurements will be combined with associated satellite data to provide the first well-sampled direct estimates of the energy balance across the atmosphere. This dataset will provide valuable information to an ongoing effort called

431

ARM - Facility News Article  

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

5, 2009 [Facility News] 5, 2009 [Facility News] Turning a New Page with Facebook; Are You a Fan? Bookmark and Share Keep up with the ARM Climate Research Facilty via Facebook! Keep up with the ARM Climate Research Facilty via Facebook! As a scientific user facility for the global change research community, the ARM Climate Research Facility strives to provide data and share its climate observation capabilities with researchers around the world. In a continuing effort to reach new users, ARM is turning another page in its outreach strategy with a presence on Facebook. (You must have a Facebook account to access the page; if you don't have one, it is free and easy to create one.) Savvy Internet users of all ages increasingly use these types of communication tools to track topics of interest and share information with

432

ARM - Facility News Article  

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

February 28, 2006 [Facility News] February 28, 2006 [Facility News] Network of Infrared Thermometers Nearly Complete at SGP Bookmark and Share Red dots indicate extended facilities at SGP with the new IRTs installed; green dots indicate future installations. Red dots indicate extended facilities at SGP with the new IRTs installed; green dots indicate future installations. As reported in April 2005, a network of infrared thermometers (IRT) is being installed throughout the ARM Southern Great Plains (SGP) site for the purpose of measuring cloud base temperature and inferring cloud base height across the domain. These measurements will enhance existing SGP surface and satellite cloud measurements to help scientists improve their calculations of heating rate profiles on the scale of global climate models. The first

433

Light-Source Facilities  

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

Facility, P.R. China CANDLE, Armenia HSRC - Hiroshima Synchrotron Radiation Center, Japan iFEL - Institute of Free Electron Laser, Japan INDUS 1 INDUS 2, India IR FEL...

434

CRAD, Facility Safety - Nuclear Facility Safety Basis | Department of  

Broader source: Energy.gov (indexed) [DOE]

CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Nuclear Facility Safety Basis More Documents & Publications CRAD, Facility Safety - Unreviewed Safety Question Requirements Site Visit Report, Livermore Site Office - February 2011 FAQS Job Task Analyses - Nuclear Safety Specialist

435

Nuclear Power Facilities (2008) | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) More Documents & Publications Financial Institution Partnership Program - Commercial...

436

Personnel Support Facility (PSF)  

High Performance Buildings Database

Virginia Beach, VA The Personnel Support Facility (PSF) provides space for a library, the Navy Marine Corps Relief Society, the Substance Abuse Rehabilitation Program, St. Leo College, and the Navy College Program. A design-build project of brick, masonry, and steel, PSF is part of a post-occupancy evaluation study run by Naval Facilities Engineering Command. The study is being used to determine the benefits of green design.

437

High current metal ion implantation facility  

SciTech Connect (OSTI)

A vacuum arc ion source based metal ion implantation facility has been established at Dokuz Eylul University, Izmir, Turkey and a surface modification research and development program is underway. The system is similar to the one in Lawrence Berkeley Laboratory which was first built and developed by Brown et al. The broad-beam ion source is repetitively pulsed at rates up to {approximately}10 pulses per second (can be increased to 50 pulses per second) and the extracted ion beam current can be up to {approximately}1 Amp. peak or {approximately}10 mA time averaged. The ion source extraction voltage was increased to 60 kV corresponding to mean beam energies of up to 150 keV or more because of the ion charge state multiplicity (extraction voltage can be increased to 100 kV if desired). Commissioning of the facility is in progress. Initial emphasis of the R and D programs that will be carried out will be in forming tribologically enhanced materials for industrial applications. In this paper they describe the design and operation of the implanter, summarize the preliminary performance parameters that have been obtained, and outline some of the programs they anticipate doing.

Oztarhan, A. [Dokuz Eylul Univ., Izmir (Turkey); Brown, I.G. [Lawrence Berkeley Lab., CA (United States); Evans, P.; Watt, G. [ANSTO, Lucas Heights (Australia). Physics Div.; Bakkaloglu, C.; Eltas, A.S. [Ataturk Organyze San., Izmir (Turkey); Oks, E. [Russian Academy of Sciences, Tomsk (Russian Federation). High Current Electronics Inst.

1998-12-31T23:59:59.000Z

438

Ultrafast Laser Facility | Photosynthetic Antenna Research Center  

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

Ultrafast Laser Facility Ultrafast Laser Facility Click for an Overview of the Ultrafast Laser Facility The PARC Ultrafast Laser Facility, under the direction of Associate Director...

439

Wheelabrator Saugus Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Saugus Biomass Facility Jump to: navigation, search Name Wheelabrator Saugus Biomass Facility Facility Wheelabrator Saugus Sector Biomass Facility Type Municipal Solid Waste...

440

Santa Clara Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Biomass Facility Jump to: navigation, search Name Santa Clara Biomass Facility Facility Santa Clara Sector Biomass Facility Type Landfill Gas Location Santa Clara County,...

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Hutchins LFG Biomass Facility | Open Energy Information  

Open Energy Info (EERE)

Hutchins LFG Biomass Facility Jump to: navigation, search Name Hutchins LFG Biomass Facility Facility Hutchins LFG Sector Biomass Facility Type Landfill Gas Location Dallas County,...

442

Cold Vacuum Drying Facility - Hanford Site  

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

Disposal Facility U Plant Vitrification Plant Waste Encapsulation and Storage Facility Waste Receiving and Processing Facility Waste Sampling and Characterization Facility Waste...

443

IG-0560.pub  

Broader source: Energy.gov (indexed) [DOE]

0 0 AUDIT REPORT U.S. DEPARTMENT OF ENERGY OFFICE OF INSPECTOR GENERAL OFFICE OF AUDIT SERVICES THE DEPARTMENT OF ENERGY'S TRITIUM EXTRACTION FACILITY JUNE 2002 MEMORANDUM FOR THE ADMINISTRATOR, NATIONAL NUCLEAR SECURITY ADMINISTRATION FROM: Gregory H. Friedman (Signed) Inspector General SUBJECT: INFORMATION: Audit Report on "The Department of Energy's Tritium Extraction Facility" BACKGROUND On March 19, 2002, you asked the Office of Inspector General to conduct an expedited review of efforts to construct the Tritium Extraction Facility (TEF) at the Department of Energy's Savannah River Site. Specifically, you expressed concerns about information you had received indicating

444

DOE-HDBK-1079-94; Primer on Tritium Safe Handling Practices  

Broader source: Energy.gov (indexed) [DOE]

METRIC DOE-HDBK-1079-94 December 1994 DOE HANDBOOK PRIMER ON TRITIUM SAFE HANDLING PRACTICES U.S. Department of Energy FSC-6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information. P.O. Box 62, Oak Ridge, TN 37831; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161. (703)487-4650. Order No. DE95003577 DOE-HDBK-1079-94 TRITIUM SAFE HANDLING PRACTICES

445

Celebrating the 20th anniversary of the tritium shot heard around the world  

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

Celebrating the 20th anniversary of the tritium shot heard around the world Celebrating the 20th anniversary of the tritium shot heard around the world By John Greenwald December 9, 2013 Tweet Widget Facebook Like Google Plus One PPPL staffers monitor a closed-circuit screen during the historic 1993 experiment. PPPL staffers monitor a closed-circuit screen during the historic 1993 experiment. Gallery: Some 1993 D-T shot staffers in today's control room. Front row from left: Marilee Thompson; Steve Sabbagh; PPPL Deputy Director for Research Michael Zarnstorff. Rear row from left: Ken Hill; Dave Johnson; Eric Fredrickson; Charles Skinner; Brent Stratton; Lane Roquemore. (Photo by Elle Starkman, PPPL Offfice of Communications) Some 1993 D-T shot staffers in today's control room. Front row from left: Marilee Thompson; Steve Sabbagh; PPPL Deputy Director for Research Michael

446

Oxidation of zirconium alloys in 2.5 kPa water vapor for tritium readiness.  

SciTech Connect (OSTI)

A more reactive liner material is needed for use as liner and cruciform material in tritium producing burnable absorber rods (TPBAR) in commercial light water nuclear reactors (CLWR). The function of these components is to convert any water that is released from the Li-6 enriched lithium aluminate breeder material to oxide and hydrogen that can be gettered, thus minimizing the permeation of tritium into the reactor coolant. Fourteen zirconium alloys were exposed to 2.5 kPa water vapor in a helium stream at 300 C over a period of up to 35 days. Experimental alloys with aluminum, yttrium, vanadium, titanium, and scandium, some of which also included ternaries with nickel, were included along with a high nitrogen impurity alloy and the commercial alloy Zircaloy-2. They displayed a reactivity range of almost 500, with Zircaloy-2 being the least reactive.

Mills, Bernice E.

2007-11-01T23:59:59.000Z

447

Titanium tritide radioisotope heat source development : palladium-coated titanium hydriding kinetics and tritium loading tests.  

SciTech Connect (OSTI)

We have found that a 180 nm palladium coating enables titanium to be loaded with hydrogen isotopes without the typical 400-500 C vacuum activation step. The hydriding kinetics of Pd coated Ti can be described by the Mintz-Bloch adherent film model, where the rate of hydrogen absorption is controlled by diffusion through an adherent metal-hydride layer. Hydriding rate constants of Pd coated and vacuum activated Ti were found to be very similar. In addition, deuterium/tritium loading experiments were done on stacks of Pd coated Ti foil in a representative-size radioisotope heat source vessel. The experiments demonstrated that such a vessel could be loaded completely, at temperatures below 300 C, in less than 10 hours, using existing department-of-energy tritium handling infrastructure.

Van Blarigan, Peter; Shugard, Andrew D.; Walters, R. Tom (Savannah River National Labs, Aiken, SC)

2012-01-01T23:59:59.000Z

448

ACHIEVING THE REQUIRED COOLANT FLOW DISTRIBUTION FOR THE ACCELERATOR PRODUCTION OF TRITIUM (APT) TUNGSTEN NEUTRON SOURCE  

SciTech Connect (OSTI)

The Accelerator Production of Tritium neutron source consists of clad tungsten targets, which are concentric cylinders with a center rod. These targets are arranged in a matrix of tubes, producing a large number of parallel coolant paths. The coolant flow required to meet thermal-hydraulic design criteria varies with location. This paper describes the work performed to ensure an adequate coolant flow for each target for normal operation and residual heat-removal conditions.

D. SIEBE; K. PASAMEHMETOGLU

2000-11-01T23:59:59.000Z

449

PNNL OS3700 Tritium Monitoring System Software and Hardware Operations Manual, Revision 0  

SciTech Connect (OSTI)

The PNNL OS3700 Tritium Monitoring System Software and Hardware Operations Manual describes herein how to install and operate the software and hardware on a personal computer in conjunction with the Berthold LB110 flow-through proportional counter detector system. Included are operational details for the software functions, how to read and use the drop-down menus, how to understand readings and calculations, and how to access the database tables.

Barnett, J M.; Duchsherer, Cheryl J.; Sisk, Daniel R.; Carrell, Dorothy M.; Douglas, David D.; Carter, Gregory L.

2005-11-09T23:59:59.000Z

450

EIS-0271: Final Environmental Impact Statement | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Final Environmental Impact Statement Final Environmental Impact Statement EIS-0271: Final Environmental Impact Statement Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site DOE proposes to construct and operate a Tritium Extraction Facility (TEF) at H Area on the Savannah River Site (SRS) to provide the capability to extract tritium from commercial light water reactor (CLWR) targets and from targets of similar design. The proposed action is also DOE's preferred alternative. An action alternative is to construct and operate TEF at the Allied General Nuclear Services facility, which is adjacent to the eastern side of the SRS. Under the no-action alternative DOE could incorporate tritium extraction capabilities in the accelerator for production of tritium. This EIS is linked to the Final Programmatic Environmental Impact

451

EIS-0271: Final Environmental Impact Statement | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

1: Final Environmental Impact Statement 1: Final Environmental Impact Statement EIS-0271: Final Environmental Impact Statement Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site DOE proposes to construct and operate a Tritium Extraction Facility (TEF) at H Area on the Savannah River Site (SRS) to provide the capability to extract tritium from commercial light water reactor (CLWR) targets and from targets of similar design. The proposed action is also DOE's preferred alternative. An action alternative is to construct and operate TEF at the Allied General Nuclear Services facility, which is adjacent to the eastern side of the SRS. Under the no-action alternative DOE could incorporate tritium extraction capabilities in the accelerator for production of tritium. This EIS is linked to the Final Programmatic Environmental Impact

452

Facility Operations 1993 fiscal year work plan: WBS 1.3.1  

SciTech Connect (OSTI)

The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO{sub 3}) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP).

Not Available

1992-11-01T23:59:59.000Z

453

DESIGN OF A CONTAINMENT VESSEL CLOSURE FOR SHIPMENT OF TRITIUM GAS  

SciTech Connect (OSTI)

This paper presents a design summary of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This new package is a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The new design is based on changes in the regulatory requirements. The BTSP design incorporates many improvements over its predecessor by implementing improved testing, handling, and maintenance capabilities, while improving manufacturability and incorporating new engineered materials that enhance the package's ability to withstand dynamic loading and thermal effects. This paper will specifically summarize the design philosophy and engineered features of the BTSP containment vessel closure. The closure design incorporates a concave closure lid, metallic C-Ring seals for containing tritium gas, a metal bellows valve and an elastomer O-Ring for leak testing. The efficient design minimizes the overall vessel height and protects the valve housing from damage during postulated drop and crush scenarios. Design features will be discussed.

Eberl, K; Paul Blanton, P

2007-07-03T23:59:59.000Z

454

Search for an admixture of sterile neutrino in the electron spectrum from tritium $?$-decay  

E-Print Network [OSTI]

We propose an experiment intended for search for an admixture of sterile neutrino with mass m$_s$ in the range of 1-8 keV that may be detected as specific distortion of the electron energy spectrum during tritium decay. The distortion is spread over large part of the spectrum so to reveal it one can use a detector with relatively poor (near 10-15%) energy resolution. A classic proportional counter is a simple natural choice for a tritium $\\beta$-decay detector. The method we are proposing is original in two respects. First, the counter is produced as a whole from fully-fused quartz tube allowing to measure current pulse directly from anode while providing high stability for a long time. Second, a modern digital acquisition technique can be used in measurements at ultrahigh count rate - up to 10$^6$ Hz. As a result an energy spectrum of tritium electrons containing up to 10$^{12}$ counts may be collected in a month of live time measurements. Due to high statistics an upper limit down to 10$^{-3}$..10$^{-5}$ can be put on sterile neutrino mixing at 95% CL for m$_s$ in the range of 1-8 keV, that will be 1..2 orders of magnitude better then bounds published up to now.

D. Abdurashitov; A. Berlev; N. Likhovid; A. Lokhov; I. Tkachev; V. Yants

2014-03-12T23:59:59.000Z

455

Hanford facility contingency plan  

SciTech Connect (OSTI)

The Hanford Facility Contingency Plan, together with each TSD unit- specific contingency plan, meets the WAC 173-303 requirements for a contingency plan. Applicability of this plan to Hanford Facility activities is described in the Hanford Facility RCRA Permit, Dangerous Waste Portion, General Condition II.A. General Condition II.A applies to Part III TSD units, Part V TSD units, and to releases of hazardous substances which threaten human health or the environment. Additional information about the applicability of this document may also be found in the Hanford Facility RCRA Permit Handbook (DOE/RL-96-10). This plan includes descriptions of responses to a nonradiological hazardous substance spill or release at Hanford Facility locations not covered by TSD unit-specific contingency plans or building emergency plans. The term hazardous substances is defined in WAC 173-303-040 as: ``any liquid, solid, gas, or sludge, including any material, substance, product, commodity, or waste, regardless of quantity, that exhibits any of the physical, chemical or biological properties described in WAC 173-303-090 or 173-303-100.`` Whenever the term hazardous substances is used in this document, it will be used in the context of this definition. This plan includes descriptions of responses for spills or releases of hazardous substances occurring at areas between TSD units that may, or may not, threaten human health or the environment.

Sutton, L.N.

1996-07-01T23:59:59.000Z

456

HFIR Experiment Facilities | ORNL Neutron Sciences  

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

Experiment Facilities Experiment Facilities HFIR Experiment Facilities Neutron Scattering Facilities Target Positions Experiment Facilities in the Beryllium Reflector Large Removable Beryllium Facilities Small Removable Beryllium Facilities Control-Rod Access Plug Facilities Small Vertical Experiment Facilities Large Vertical Experiment Facilities Hydraulic Tube Facility Peripheral Target Positions Neutron Activation Analysis (NAA) Laboratory and Pneumatic Tube Facilities Slant Engineering Facilities Gamma Irradiation Facility Quality Assurance Requirements Contact Information Neutron Scattering Facilities The fully instrumented HFIR will eventually include 15 state-of-the-art neutron scattering instruments, seven of which will be designed exclusively for cold neutron experiments, located in a guide hall south of the reactor

457

Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2008  

SciTech Connect (OSTI)

Near-facility environmental monitoring is defined as monitoring near facilities that have the potential to discharge or have discharged, stored, or disposed of radioactive or hazardous materials. Monitoring locations are associated with nuclear facilities such as the Plutonium Finishing Plant, Canister Storage Building, and the K Basins; inactive nuclear facilities such as N Reactor and the Plutonium-Uranium Extraction (PUREX) Facility; and waste storage or disposal facilities such as burial grounds, cribs, ditches, ponds, tank farms, and trenches. Much of the monitoring consists of collecting and analyzing environmental samples and methodically surveying areas near facilities. The program is also designed to evaluate acquired analytical data, determine the effectiveness of facility effluent monitoring and controls, assess the adequacy of containment at waste disposal units, and detect and monitor unusual conditions.

Perkins, Craig J.; Dorsey, Michael C.; Mckinney, Stephen M.; Wilde, Justin W.; Poston, Ted M.

2009-09-15T23:59:59.000Z

458

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Inertial Confinement Fusion Inertial Confinement Fusion Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement Fusion > Facilities Facilities Office of Inertial Confinement Fusion, Facilities ICF operates a set of world-class experimental facilities to create HEDP conditions and to obtain quantitative data in support of its numerous stockpile stewardship-related activities. To learn about three high energy experimental facilities and two small lasers that provide ICF capabilities, select the links below. National Ignition Facility, Lawrence Livermore National Laboratory OMEGA and OMEGA EP, University of Rochester Laboratory for Laser Energetics Z Machine, Sandia National Laboratories

459

ARM - Facility News Article  

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

User Facility Improvements Continue at North Slope of Alaska Locale User Facility Improvements Continue at North Slope of Alaska Locale Bookmark and Share The "skydeck" at Barrow shows how the instrument platforms can get very crowded during peak experimental periods. The "skydeck" at Barrow shows how the instrument platforms can get very crowded during peak experimental periods. Two things are critical for conducting scientific research: adequate equipment and power. This is especially true in the Arctic, where average winter temperatures hover around -30 degrees Celsius, and access to additional resources is limited. After experiencing crowded working conditions during complex field campaigns last year, followed by several power outages this past winter, operations staff at the ARM Climate Research Facility's North Slope of Alaska (NSA) locale began implementing

460

Nuclear Facility Safety Basis  

Broader source: Energy.gov (indexed) [DOE]

Safety Basis Safety Basis FUNCTIONAL AREA GOAL: A fully compliant Nuclear Facility Safety Basis. Program is implemented and maintained across the site. REQUIREMENTS: ï‚· 10 CFR 830 Subpart B Guidance: ï‚· DOE STD 3009 ï‚· DOE STD 1104 ï‚· DOE STD ï‚· DOE G 421.1-2 Implementation Guide For Use in Developing Documented Safety Analyses To Meet Subpart B Of 10 CFR 830 ï‚· DOE G 423.1-1 Implementation Guide For Use In Developing Technical Safety Requirements ï‚· DOE G 424.1-1 Implementation Guide For Use In Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation The site contractor has developed an up-to-date, comprehensive, compliant, documented nuclear facility safety basis and associated implementing mechanisms and procedures for all required nuclear facilities and activities (10 CFR

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461

ARM - Facility News Article  

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

5, 2011 [Facility News] 5, 2011 [Facility News] Atmospheric System Research Announces Funding Opportunity Bookmark and Share The U.S. Department of Energy's Office of Science is now accepting applications for Office of Biological and Environmental Research (BER) research grants for the development of innovative laboratory and observational data analyses. The resulting knowledge from such analyses will be used to improve cloud and aerosol formulations in global climate models. Successful applications will be part of the Atmospheric System Research (ASR) Program in the Climate and Environmental Sciences Division (CESD). The mission of ASR, in partnership with the ARM Climate Research Facility, is to quantify the interactions among aerosols, clouds, precipitation, radiation, dynamics, and thermodynamics to improve fundamental

462

ARM - Facility News Article  

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

August 15, 2010 [Facility News] August 15, 2010 [Facility News] Micropulse Lidars Get Boost from Recovery Act Bookmark and Share Shown here during installation on the aft deck of the RV Connecticut, the upgraded MPL includes a sleek new computer that can fit into smaller spaces. The laser window at the top is covered by a cone until the instrument is turned on. Shown here during installation on the aft deck of the RV Connecticut, the upgraded MPL includes a sleek new computer that can fit into smaller spaces. The laser window at the top is covered by a cone until the instrument is turned on. Through funding from the American Recovery and Reinvestment Act of 2009, ARM is upgrading the micropulse lidars (MPL) throughout the user facility. Similar to a radar, the MPL sends pulses of energy into the atmosphere.

463

SEU Test Facility  

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

Logo The SEU Test Facility Logo The SEU Test Facility 1. Introduction The uninterrupted and progressive miniaturization of microelectronic devices while resulting in more powerful computers, has also made these computers more susceptible to the effects of ionizing radiation. This is of particular concern for space applications due to the radiation fields encountered outside the protective terrestrial atmosphere and magnetosphere. Starting in 1987, a coalition of US government agencies (NSA, NASA, NRL and USASSDC ) collaborated with BNL to develop a powerful and user-friendly test facility for investigating space-radiation effects on micro-electronic devices[1]. The main type of effects studied are the so called Single Event Upsets (SEUs) where ionization caused by the passage of

464

ARM - Facility News Article  

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

January 11, 2007 [Facility News] January 11, 2007 [Facility News] ARM Mobile Facility Moves to China in 2008 for Study of Aerosol Impacts on Climate Bookmark and Share Onshore winds and a mountain range to the west of Shanghai form a natural basin which traps particulates in the air above the Yangtze River delta region. (Illustration courtesy of Patricia Ebrey, University of Washington) Onshore winds and a mountain range to the west of Shanghai form a natural basin which traps particulates in the air above the Yangtze River delta region. (Illustration courtesy of Patricia Ebrey, University of Washington) China generates exceptionally high amounts of aerosol particles whose influence on the atmosphere has been detected across the Pacific Rim. In the Yangtze River delta in southeast China, these high aerosol loadings

465

AWA Facility Expansion  

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

Facility Upgrade Facility Upgrade Wei Gai High Energy Physics Division June 16, 2009 Background * AWA Group has been receiving very positive DOE Review evaluations in the last several years. * DOE funding has been constant or increasing, even in years with general budget cuts. * Outstanding scientific results have been achieved in recent years using the unique AWA electron beam capabilities (100 MV/m accelerating gradient). * General infrastructure in building 366 has improved in recent years (air-conditioner, better lighting, new laboratory space), creating a much better environment for conducting the AWA research program. * Additional RF power station (a second klystron) is being commissioned and it will improve the capabilities of the facility. Recent Budget Increase * Very positive DOE review (Dec. 2008) and

466

ARM - Facility News Article  

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

The Tale of the Tapes-No More Boxes of Data! The Tale of the Tapes-No More Boxes of Data! Bookmark and Share In October 1997, the ARM Program entered into a contract with the University of Alaska-Fairbanks to obtain image data covering the ARM Climate Research Facility's North Slope of Alaska (NSA) locale. Image data taken by an advanced very high resolution radiometer (AVHRR) are collected by a satellite receiver at Fairbanks and, up until February 2004, were stored on 4mm tapes. These boxes were then shipped by the boxful to the ARM Climate Research Facility External Data Center every six months. Once at the External Data Center, the data was processed into standard "hierarchical data format" or HDF files and transferred to the ARM Climate Research Facility Data Archive for use by ARM researchers. All data from

467

ARM - Facility News Article  

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

More Storage Space, Better Reliability Now at the ARM Data Management More Storage Space, Better Reliability Now at the ARM Data Management Facility Bookmark and Share To support the ever-increasing file storage needs of the ARM Data Management Facility (DMF) and ARM Engineering computers, a Network Appliance (NetApp®) file server with 2.68 terabytes, or 2.95 trillion bytes, of highly-reliable and extremely-fast, usable disk storage joined the DMF servers. The NetApp system performs nearly four times faster than the previous file server and is engineered for a higher degree of reliability-critical improvements needed to maintain uptime for ARM data availability at the DMF. A NetApp server increases ARM storage capacity and keeps the data flowing at the Data Management Facility. A NetApp server increases ARM storage capacity and keeps the data flowing

468

ARM - Facility News Article  

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

October 8, 2012 [Facility News] October 8, 2012 [Facility News] Near Miss at Barrow Due to Beach Erosion Bookmark and Share With a little help from his friends, Walter Brower (hidden by the ECOR) moves the system away from the ocean's edge as an early September storm pounds away at the beach. With a little help from his friends, Walter Brower (hidden by the ECOR) moves the system away from the ocean's edge as an early September storm pounds away at the beach. On a stormy Friday evening in early September, Walter Brower received an urgent message: "Beach erosion very close to ECOR Point." Brower is the local facility manager for ARM's North Slope of Alaska site in Barrow. His duties extend to Point Barrow at the coastline of the Arctic Ocean, where ARM operates an eddy correlation flux measurement system, or

469

ARM - Facility News Article  

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

31, 2005 [Facility News] 31, 2005 [Facility News] Ancillary Site to Provide Key Data from Africa Bookmark and Share In January 2006, the ARM Mobile Facility (AMF) begins a year-long field campaign in Africa as part of a multi-year international experiment called the African Monsoon Multidisciplinary Analysis (AMMA). The AMF will be placed at the airport in Niamey, Niger, well within view of the Global Earth Radiation Budget (GERB) geostationary satellite. Cloud and radiative property measurements collected by the AMF will be used in conjunction with GERB data for a greater understanding of the atmosphere than could be gained from either dataset alone. While preparing for the campaign, the science team identified the need for instrumentation at an off-site location to compare radiative measurements from the natural environment of

470

ARM - Facility News Article  

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

April 15, 2010 [Facility News] April 15, 2010 [Facility News] Second Phase of African Scientific Exchange Underway Bookmark and Share Left to right: Dr. Zewdu Segele and Hama Hamidou examine reflectivity measurements made by the W-band ARM cloud radar in Niamey during July 2006. Left to right: Dr. Zewdu Segele and Hama Hamidou examine reflectivity measurements made by the W-band ARM cloud radar in Niamey during July 2006. Continuing an international collaboration that began with the ARM Mobile Facility deployment to Niamey, Niger, in 2006, meteorologist Hama Hamidou from the University of Niamey recently arrived at the Cooperative Institute for Mesoscale Meteorological Studies at the University of Oklahoma for a six-month scientific exchange. Under the guidance of Dr. Zewdu Segele, a

471

ARM - Facility News Article  

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

Guest Instruments to Collect Aerosol Data During Coastal Field Campaign Guest Instruments to Collect Aerosol Data During Coastal Field Campaign Bookmark and Share The counter-flow virtual impactor (inset), which can characterize aerosol particles in cloud droplets, joins a number of other guest instruments at the ARM Mobile Facility deployment site at Point Reyes National Seashore in California. The counter-flow virtual impactor (inset), which can characterize aerosol particles in cloud droplets, joins a number of other guest instruments at the ARM Mobile Facility deployment site at Point Reyes National Seashore in California. The ARM Mobile Facility's (AMF's) inaugural field campaign, the Marine Stratus Radiation Aerosol and Drizzle (MASRAD) Intensive Operational Period, is well underway at Point Reyes National Seashore on the northern

472

Lighting Research Group: Facilities  

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

Facilities Facilities Lighting Research Facilities at LBNL gonio-photometer Gonio-photometer We use this device to measure the intensity and direction of the light from a lamp or fixture. integrating sphere Integrating sphere This instrument allows us to get a fast and accurate measurement of the total light output of a lamp. We are not able to determine the direction of the light, only the intensity. power analyzer Power analyzer We use our power analyzer with the lamps in the gonio-photometer to measure input power, harmonic distortion, power factor, and many other signals that tell us how well a lamp is performing. spectro-radiometer Spectro-radiometer This device measures not only the intensity of a light source but also the intensity of the light at each wavelength.

473

ARM - Facility News Article  

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

April 24, 2013 [Education, Facility News] April 24, 2013 [Education, Facility News] A Twist on TwisterTM: ARM Educational Outreach Participates in Community Science Nights Bookmark and Share This week, the U.S. Department of Energy begins its National Science Bowl competition, a nationwide academic competition that tests students' knowledge in all areas of science. Created 22 years ago in 1991, the DOE National Science Bowl strives to encourage students to excel in mathematics and science and to pursue careers in these fields and is an important part of DOE's STEM (science, technology, engineering and math) education efforts today. The ARM Climate Research Facility supports STEM by participating in public science nights and developing climate related lesson plans to share at these events and via the ARM website.

474

ARM - Facility News Article  

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

March 10, 2010 [Facility News] March 10, 2010 [Facility News] Atmospheric System Research Funding Opportunity Announced Bookmark and Share The U.S. Department of Energy's Office of Science is now accepting applications for Office of Biological and Environmental Research (BER) research grants for the development of innovative laboratory and observational data analyses. The resulting knowledge from such analyses will be used to improve cloud and aerosol formulations in global climate models. If the application is successful, the research will be part of the Atmospheric System Research (ASR) Program in the Climate and Environmental Sciences Division (CESD). The mission of ASR, in partnership with the ARM Climate Research Facility, is to quantify the interactions among aerosols, clouds, precipitation, radiation, dynamics, and thermodynamics to improve

475

Advanced Windows Test Facility  

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

Exterior of Advanced Windows Test Facility Exterior of Advanced Windows Test Facility Advanced Windows Test Facility This multi-room laboratory's purpose is to test the performance and properties of advanced windows and window systems such as electrochromic windows, and automatically controlled shutters and blinds. The lab simulates real-world office spaces. Embedded instrumentation throughout the lab records solar gains and losses for specified time periods, weather conditions, energy use, and human comfort indicators. Electrochromic glazings promise to be a major advance in energy-efficient window technology, helping to achieve the goal of transforming windows and skylights from an energy liability in buildings to an energy source. The glazing can be reversibly switched from a clear to a transparent, colored

476

ARM - Facility News Article  

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

July 23, 2008 [Data Announcements, Facility News] July 23, 2008 [Data Announcements, Facility News] Second Version of Long-Term Climate Modeling Best Estimate Data Released Bookmark and Share Version 2 of the Climate Modeling Best Estimate includes the data source information for cloud fraction, as depicted in this data plot. Version 2 of the Climate Modeling Best Estimate includes the data source information for cloud fraction, as depicted in this data plot. With major improvements in the cloud fraction, cloud liquid water path (LWP), precipitable water vapor (PWV), and surface radiative fluxes, a new version of the "Climate Modeling Best Estimate" (CMBE) is now available from the ARM Climate Research Facility Archive. This data set, specifically tailored for use in evaluating global climate models, includes long-term

477

ARM - Facility News Article  

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

October 15, 2007 [Facility News] October 15, 2007 [Facility News] ARM Joins National Science Foundation Remote Sensing Collaboration Bookmark and Share In September, the ARM Climate Research Facility became an official member of the National Science Foundation's Center for Collaborative Adaptive Sensing of the Atmosphere, or CASA. Initial discussions for partnering began nearly a year ago. After a series of informative visits and presentations, the decision was made to move forward with membership process. The transfer of interagency funds was completed on September 18, 2007, solidifying the partnership. In the meantime, CASA dedicated a significant effort to support the CLASIC field campaign in June 2007 by providing a network of four scanning X-band radars. CASA is a multi-sector partnership among academia, industry, and government

478

ARM - Facility News Article  

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

CIMEL Sunphotometer Helps Researchers See the Light in Australia CIMEL Sunphotometer Helps Researchers See the Light in Australia Bookmark and Share A CIMEL sunphotometer, similar to this one in Tinga Tingana, Australia, will be installed at the ARM Climate Research Facility Darwin site. Photo courtesy of NASA Goddard Space Flight Center. A CIMEL sunphotometer, similar to this one in Tinga Tingana, Australia, will be installed at the ARM Climate Research Facility Darwin site. Photo courtesy of NASA Goddard Space Flight Center. Science collaborators at the Australian Bureau of Meteorology (BOM) and the Australian Commonwealth Scientific and Industry Research Organization (CSIRO) are using the ARM Climate Research Facility Darwin site in Australia to evaluate aerosol optical properties during the tropical dry season. As part of the Darwin Aerosol Intensive Operational Period (IOP), a

479

ARM - Facility News Article  

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

June 15, 2006 [Facility News] June 15, 2006 [Facility News] Data From Rotating Shadowband Spectroradiometer Now Available in Data Archive Bookmark and Share The Rotating Shadowband Spectroradiometer (RSS) is calibrated bi-weekly with external lamp calibrators for accuracy. The Rotating Shadowband Spectroradiometer (RSS) is calibrated bi-weekly with external lamp calibrators for accuracy. After refinements based on a series of successful field trials, the latest Rotating Shadowband Spectroradiometer (RSS) joins the collection of permanent ARM instruments at the ARM Southern Great Plains (SGP) site. The current RSS-known as the RSS105-is deployed at the SGP Central Facility and is the first commercially built RSS manufactured by Yankee Environmental Systems, Inc. Since its deployment in May 2003, the RSS has

480

ARM - Facility News Article  

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

October 11, 2011 [Facility News] October 11, 2011 [Facility News] Final Recovery Act Milestone Complete! Bookmark and Share To support all the new instruments from the Recovery Act, infrastructure upgrades ranging from power and platforms to communications and data systems required a focused team effort. To support all the new instruments from the Recovery Act, infrastructure upgrades ranging from power and platforms to communications and data systems required a focused team effort. For the past year and a half, ARM scientists, engineers, operations, and data systems staff have been working tirelessly to support the installation and operation of nearly 150 new and upgraded instruments throughout the user facility. In September, ARM received its final three instruments - a radar wind profiler; a micropulse lidar for the Darwin, Australia site; and

Note: This page contains sample records for the topic "tritium extraction facility" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


481

ARM - Facility News Article  

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

April 30, 2013 [Facility News] April 30, 2013 [Facility News] Gearing Up for Science in Amazon Rainforest Bookmark and Share In March 2013, an initial instrument suite began operating near Manacupuru, in the Brazilian state of Amazonas, as part of the GOAMAZON field campaign. In March 2013, an initial instrument suite began operating near Manacupuru, in the Brazilian state of Amazonas, as part of the GOAMAZON field campaign. Preparing for the biggest and most complex deployment of field resources to date, the ARM Mobile Facility operations team from Los Alamos National Laboratory spent three weeks in Brazil in early March tackling a range of protocol and logistics tasks for next year's GOAMAZON field campaign. Between ARM and Brazilian collaborators, about 80 instruments will obtain

482

ARM - Facility News Article  

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

May 15, 2008 [Data Announcements, Facility News] May 15, 2008 [Data Announcements, Facility News] Announcing the Release of the Radiative Flux Analysis PI Product Bookmark and Share Developed by Dr. Chuck Long, Radiative Flux Analysis PI Product data are now available from the ARM Climate Research Facility Archive. The current release includes data for all of the ARM fixed sites (except Darwin, which requires manual processing because of the monsoon season) plus data for the AMF deployments at Pt. Reyes and the COPS Black Forest site. Future releases will include data for Darwin, the COPS Hornisgrinde and Rhine Valley sites, and the AMF Niamey deployment. The Radiative Flux Analysis is a technique for using surface shortwave (SW) and longwave (LW) broadband radiation measurements for detecting periods of

483

ARM - Facility News Article  

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

W-Band Cloud Radar Added to ARM Mobile Facility in Africa W-Band Cloud Radar Added to ARM Mobile Facility in Africa Bookmark and Share Most of the WACR is mounted on top of one of the AMF shelters. The WACR computer and chiller (used to keep the WACR cool in temperatures up to 47 degrees C) are located in the shelter below the radar. Most of the WACR is mounted on top of one of the AMF shelters. The WACR computer and chiller (used to keep the WACR cool in temperatures up to 47 degrees C) are located in the shelter below the radar. A W-band ARM Cloud Radar (WACR) recently joined the suite of baseline capabilities offered by the ARM Mobile Facility (AMF). The term "W-band" refers to the specific radio frequency range of this radar, which is a 95 gigahertz pulse Doppler zenith pointing radar, providing profiles of cloud