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Note: This page contains sample records for the topic "nuclear test prepared" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Test Preparation Options Free Test Prep Websites  

E-Print Network (OSTI)

Test Preparation Options Free Test Prep Websites ACT: http: http://www.collegeboard.com/student/testing/sat/prep_one/test.html http://www.number2.com://testprep.princetonreview.com/CourseSearch/Search.aspx?itemCode=17&productType=F&rid=1&zip=803 02 Test Prep Classes Front Range Community College: Classes

Stowell, Michael

2

Nuclear Weapons Testing Resumes | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

> Nuclear Weapons Testing Resumes Nuclear Weapons Testing Resumes September 01, 1961 Washington, DC Nuclear Weapons Testing Resumes The Soviet Union breaks the nuclear test...

3

ORISE: Preparing Nations to Fight Nuclear Smuggling  

NLE Websites -- All DOE Office Websites (Extended Search)

Prepares Nations to Fight Nuclear Smuggling With the knowledge needed to incorporate radiological materials in an explosive device now widely available and unsecured stockpiles...

4

ORISE: Preparing Nations to Fight Nuclear Smuggling  

NLE Websites -- All DOE Office Websites (Extended Search)

Prepares Nations to Fight Nuclear Smuggling Prepares Nations to Fight Nuclear Smuggling With the knowledge needed to incorporate radiological materials in an explosive device now widely available and unsecured stockpiles still a reality, nuclear smuggling remains a global security threat. Recent seizures of weapon-grade nuclear materials suggest such materials remain in illegal circulation and could be used to kill tens or hundreds of thousands of people. ORISE has extended its national security expertise to assist government leaders and law enforcement in many countries as they unite in efforts to apprehend and prosecute nuclear materials smugglers. ORISE is working with the U.S. Department of State's Preventing Nuclear Smuggling Program (PNSP) to prevent nuclear smuggling abroad and in conjunction with the U.S. Department of Homeland Security and other

5

Semipalatinsk Nuclear Tests - Springer  

Science Conference Proceedings (OSTI)

3.1 Tower used for measurements of nuclear weapon effects near ground zero. 3.1 A Brief ... atomic bomb. This output is 6% of all the nuclear explosions in.

6

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security...  

NLE Websites -- All DOE Office Websites (Extended Search)

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

7

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security Eisenhower Halts Nuclear Weapons Testing | 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 > About Us > Our History > NNSA Timeline > Eisenhower Halts Nuclear Weapons Testing Eisenhower Halts Nuclear Weapons Testing August 22, 1958 Washington, DC Eisenhower Halts Nuclear Weapons Testing

8

Safe testing nuclear rockets economically  

DOE Green Energy (OSTI)

Several studies over the past few decades have recognized the need for advanced propulsion to explore the solar system. As early as the 1960s, Werner Von Braun and others recognized the need for a nuclear rocket for sending humans to Mars. The great distances, the intense radiation levels, and the physiological response to zero-gravity all supported the concept of using a nuclear rocket to decrease mission time. These same needs have been recognized in later studies, especially in the Space Exploration Initiative in 1989. One of the key questions that has arisen in later studies, however, is the ability to test a nuclear rocket engine in the current societal environment. Unlike the RoverMERVA programs in the 1960s, the rocket exhaust can no longer be vented to the open atmosphere. As a consequence, previous studies have examined the feasibility of building a large-scale version of the Nuclear Furnace Scrubber that was demonstrated in 1971. We have investigated an alternative that would deposit the rocket exhaust along with any entrained fission products directly into the ground. The Subsurface Active Filtering of Exhaust, or SAFE, concept would allow variable sized engines to be tested for long times at a modest expense. A system overview, results of preliminary calculations, and cost estimates of proof of concept demonstrations are presented. The results indicate that a nuclear rocket could be tested at the Nevada Test Site for under $20 M.

Howe, S. D. (Steven D.); Travis, B. J. (Bryan J.); Zerkle, D. K. (David K.)

2002-01-01T23:59:59.000Z

9

Report on PV Test Sites and Test Prepared for the  

E-Print Network (OSTI)

Report on PV Test Sites and Test Protocols Prepared for the U.S. Department of Energy Office of Electricity Delivery and Energy Reliability Under Cooperative Agreement No. DE-FC26-06NT42847 Hawai`i Distributed Energy Resource Technologies for Energy Security Revised Task 8 Deliverable PV Test Sites and Test

10

Nuclear Weapons Testing Resumes | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

Testing Resumes | National Nuclear Security Administration Testing Resumes | 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 > About Us > Our History > NNSA Timeline > Nuclear Weapons Testing Resumes Nuclear Weapons Testing Resumes September 01, 1961 Washington, DC Nuclear Weapons Testing Resumes The Soviet Union breaks the nuclear test moratorium and the United States

11

Sodium Reaction Experimental Test Facility (SRETF) - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Form Modeling Departments Engineering Analysis Nuclear Systems Analysis Research & Test Reactor Nonproliferation and National Security Detection & Diagnostic Systems...

12

Reducing emissions to improve nuclear test detection | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Reducing emissions to improve nuclear test detection | National Nuclear Reducing emissions to improve nuclear test detection | 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 > Reducing emissions to improve nuclear test detection Reducing emissions to improve nuclear test detection Posted By Office of Public Affairs In early November, medical isotope producers met with nuclear explosion

13

Clinton Extends Moratorium on Nuclear Weapons Testing | National Nuclear  

National Nuclear Security Administration (NNSA)

Clinton Extends Moratorium on Nuclear Weapons Testing | National Nuclear Clinton Extends Moratorium on Nuclear Weapons Testing | 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 > About Us > Our History > NNSA Timeline > Clinton Extends Moratorium on Nuclear Weapons Testing Clinton Extends Moratorium on Nuclear Weapons Testing July 03, 1993 Washington, DC

14

Ground test facility for nuclear testing of space reactor subsystems  

SciTech Connect

Two major reactor facilities at the INEL have been identified as easily adaptable for supporting the nuclear testing of the SP-100 reactor subsystem. They are the Engineering Test Reactor (ETR) and the Loss of Fluid Test Reactor (LOFT). In addition, there are machine shops, analytical laboratories, hot cells, and the supporting services (fire protection, safety, security, medical, waste management, etc.) necessary to conducting a nuclear test program. This paper presents the conceptual approach for modifying these reactor facilities for the ground engineering test facility for the SP-100 nuclear subsystem. 4 figs.

Quapp, W.J.; Watts, K.D.

1985-01-01T23:59:59.000Z

15

Finding of No Significant Impact Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

RADIOLOGICAL/NUCLEAR COUNTERMEASURES TEST AND EVALUATION COMPLEX, NEVADA TEST SITE The U.S. Department of Homeland Security (DHS) is the Federal organization charged with defending the borders of the United States under the authority the Homeland Security Act of 2002 (Public Law 107-296). The DHS requested the National Nuclear Security Administration (NNSA) to develop at the Nevada Test Site (NTS) a complex for testing and evaluating countermeasures for interdicting potential terrorist attacks using radiological and/or nuclear weapons of mass destruction. In response to that request, NNSA proposes to construct, operate, and maintain the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC). NNSA has prepared an Environmental Assessment (DOE/EA-1499) (EA) which analyzes the potential

16

Preparing for the 2012 Nuclear Security Summit | National Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

it was really impressive to see the progress piled up: over 400 kg of highly enriched uranium removed from over 10 countries - enough for 16 nuclear bombs. A dozen new...

17

Preparing for the 2012 Nuclear Security Summit | National Nuclear...  

National Nuclear Security Administration (NNSA)

about prepreations for the 2012 Nuclear Security Summit to be held in Seoul, South Korea. She writes: "Even though I'd been aware of many of these events as they happened, it...

18

Clinton Extends Moratorium on Nuclear Weapons Testing | National...  

National Nuclear Security Administration (NNSA)

Weapons Testing Clinton Extends Moratorium on Nuclear Weapons Testing July 03, 1993 Washington, DC Clinton Extends Moratorium on Nuclear Weapons Testing President Clinton...

19

Nuclear Supersymmetry: New Tests and Extensions  

E-Print Network (OSTI)

Extensions of nuclear supersymmetry are discussed, together with a proposal for new, more stringent and precise tests that probe the susy classification and specific two-particle correlations among supersymmetric partners. The combination of these theoretical and experimental studies may play a unifying role in nuclear phenomena.

A. Frank; J. Barea; R. Bijker

2003-05-13T23:59:59.000Z

20

Testing of coatings for the nuclear industry  

SciTech Connect

Coatings for commercial nuclear power plants need to withstand humidity, radiation exposure, and LOC accident conditions; they also must be decontaminable. Tests for decontaminability, radiation stability, and design-basis-accident (DBA) resistance are described. An irradiation test facility using spent fuel assemblies and a spray loop for simulating a DBA are described. A sample test report sheet is presented. (DLC)

Goldberg, G.

1975-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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

Reducing emissions to improve nuclear test detection | National...  

National Nuclear Security Administration (NNSA)

Reducing emissions to improve nuclear test detection | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear...

22

Clinton Extends Moratorium on Nuclear Weapons Testing | National...  

NLE Websites -- All DOE Office Websites (Extended Search)

Clinton Extends Moratorium on Nuclear Weapons Testing | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear...

23

Testing quantum correlations with nuclear probes  

E-Print Network (OSTI)

We investigated the feasibility of quantum-correlation measurements in nuclear physics experiments. In a first approach, we measured spin correlations of singlet-spin (1S0) proton pairs, which were generated in 1H(d,2He) and 12C(d,2He) nuclear charge-exchange reactions. The experiment was optimized for a clean preparation of the 2He singlet state and offered a 2pi detection geometry for both protons in the exit channel. Our results confirm the effectiveness of the setup for theses studies, despite limitations of a small data sample recorded during the feasibility studies.

S. Hamieh; H. J. Woertche; C. Baeumer; A. M. van den Berg; D. Frekers; M. N. Harakeh; J. Heyse; M. Hunyadi; M. A. de Huu; C. Polachic; S. Rakers; C. Rangacharyulu

2003-10-17T23:59:59.000Z

24

EA-1954: Resumption of Transient Testing of Nuclear Fuels and...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National...

25

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear...

26

Y-12 builds capacity to meet nuclear testing schedule - Or: ...  

NLE Websites -- All DOE Office Websites (Extended Search)

builds capacity to meet nuclear testing schedule - Or: Increasing capacity to meet nuclear testing schedule (title as it appeared in The Oak Ridger) The continuing high volume...

27

Preparation of nuclear fuel spheres by flotation-internal gelation  

DOE Patents (OSTI)

A simplified internal gelation process is claimed for the preparation of gel spheres of nuclear fuels. The process utilizes perchloroethylene as a gelation medium. Gelation is accomplished by directing droplets of a nuclear fuel broth into a moving volume of hot perchloroethylene (about 85/sup 0/C) in a trough. Gelation takes place as the droplets float on the surface of the perchloroethylene and the resultant gel spheres are carried directly into an ager column which is attached to the trough. The aged spheres are disengaged from the perchloroethylene on a moving screen and are deposited in an aqueous wash column. 3 figs.

Haas, P.A.; Fowler, V.L.; Lloyd, M.H.

1984-12-21T23:59:59.000Z

28

Preparation of nuclear fuel spheres by flotation-internal gelation  

DOE Patents (OSTI)

A simplified internal gelation process for the preparation of gel spheres of nuclear fuels. The process utilizes perchloroethylene as a gelation medium. Gelation is accomplished by directing droplets of a nuclear fuel broth into a moving volume of hot perchloroethylene (about 85.degree. C.) in a trough. Gelation takes place as the droplets float on the surface of the perchloroethylene and the resultant gel spheres are carried directly into an ager column which is attached to the trough. The aged spheres are disengaged from the perchloroethylene on a moving screen and are deposited in an aqueous wash column.

Haas, Paul A. (Knoxville, TN); Fowler, Victor L. (Oak Ridge, TN); Lloyd, Milton H. (Oak Ridge, TN)

1987-01-01T23:59:59.000Z

29

Correlation Testing in Nuclear Density Functional Theory  

E-Print Network (OSTI)

Correlation testing provides a quick method of discriminating amongst potential terms to include in a nuclear mass formula or functional and is a necessary tool for further nuclear mass models; however a firm mathematical foundation of the method has not been previously set forth. Here, the necessary justification for correlation testing is developed and more detail of the motivation behind its use is give. Examples are provided to clarify the method analytically and for computational benchmarking. We provide a quantitative demonstration of the method's performance and short-comings, highlighting also potential issues a user may encounter. In concluding we suggest some possible future developments to improve the limitations of the method.

M. G. Bertolli

2012-08-07T23:59:59.000Z

30

A thousand suns : political motivations for nuclear weapons testing  

E-Print Network (OSTI)

Nuclear weapon testing is the final step in the nuclear development process, an announcement of ability and strength. The consequences of a nuclear test are far from easy to bear, however: economic sanctions can be crippling ...

Raas, Whitney

2006-01-01T23:59:59.000Z

31

Guidelines for inservice testing at nuclear power plants  

Science Conference Proceedings (OSTI)

The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

Campbell, P.

1995-04-01T23:59:59.000Z

32

Method of preparing nuclear wastes for tansportation and interim storage  

SciTech Connect

Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

1984-01-01T23:59:59.000Z

33

Limited Test Ban Treaty Signed | National Nuclear Security Administrat...  

NLE Websites -- All DOE Office Websites (Extended Search)

Limited Test Ban Treaty Signed | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

34

Senate Rejects Test Ban Treaty | National Nuclear Security Administrat...  

NLE Websites -- All DOE Office Websites (Extended Search)

Senate Rejects Test Ban Treaty | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

35

EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4: Resumption of Transient Testing of Nuclear Fuels and 4: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho SUMMARY This Environmental Assessment (EA) evaluates U.S. Department of Energy (DOE) activities associated with its proposal to resume testing of nuclear fuels and materials under transient high-power test conditions at the Transient Reactor Test (TREAT) Facility at the Idaho National Laboratory. The State of Idaho and Shoshone-Bannock Tribes are cooperating agencies. PUBLIC COMMENT OPPORTUNITIES DOE invites the public to read and comment on a draft environmental assessment it has prepared for a proposal to resume transient testing of nuclear fuels and materials at either Idaho National Laboratory or Sandia

36

Correlations Tests in Nuclear Mass Model Development  

E-Print Network (OSTI)

Correlation testing provides a quick method of discriminating amongst potential terms to include in a nuclear mass formula or functional; however a firm mathematical foundation of the method has not been previously set forth. Here, the necessary justification for correlation testing is developed and more detail of the motivation behind its use is given. We provide a quantitative demonstration of the method's performance and short-comings, highlighting also potential issues a user may encounter. In concluding we suggestion some possible future developments to improve the limitations of the method.

Bertolli, M G

2012-01-01T23:59:59.000Z

37

Announced United States nuclear tests, July 1945--December 1990  

SciTech Connect

This document lists chronologically and alphabetically by event name all nuclear tests conducted and announced by the United States from July 1945 to December 1990 with the exception of the GMX experiments. Discussion is included on test dates, test series, test yields, test locations, test types and purposes, test totals for Nevada Test Site (NTS) detection of radioactivity from NTS events, and categorization of NTS nuclear tests. Briefly discussed are agreements between the US and the Soviet Union regarding test banning. (MB)

Not Available

1991-01-01T23:59:59.000Z

38

Preparing the Nuclear Security Science Minds of Tomorrow | National...  

National Nuclear Security Administration (NNSA)

the Nuclear Security Science Minds of Tomorrow | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

39

Nuclear reactor containment spray testing system. [PWR  

SciTech Connect

Disclosed is a method for periodic testing of a spray system in a nuclear reactor containment. The method includes injecting a gas into the spray system such that a temperature differential exists between the gas and the containment atmosphere. Scanning the gas jet discharged from the spray nozzles with infrared apparatus then provides a real-time thermal image on a monitor, such as a cathode ray tube, and detects any partially or completely blocked nozzles in the spray system. The scanning may be performed from the containment operating deck. 1 claim, 4 figures.

Rubin, K.

1978-01-10T23:59:59.000Z

40

Office of Research, Development, Test, and Evaluation | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Research, Development, Test, and Evaluation | National Nuclear Research, Development, Test, and Evaluation | 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 The National Nuclear Security Administration Office of Research, Development, Test, and Evaluation Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation

Note: This page contains sample records for the topic "nuclear test prepared" 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

Last U.S. Underground Nuclear Test Conducted | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

U.S. Underground Nuclear Test Conducted | National Nuclear Security U.S. Underground Nuclear Test Conducted | 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 > About Us > Our History > NNSA Timeline > Last U.S. Underground Nuclear Test Conducted Last U.S. Underground Nuclear Test Conducted September 23, 1992 USA Last U.S. Underground Nuclear Test Conducted

42

Last U.S. Underground Nuclear Test Conducted | National Nuclear Security  

National Nuclear Security Administration (NNSA)

U.S. Underground Nuclear Test Conducted | National Nuclear Security U.S. Underground Nuclear Test Conducted | 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 > About Us > Our History > NNSA Timeline > Last U.S. Underground Nuclear Test Conducted Last U.S. Underground Nuclear Test Conducted September 23, 1992 USA Last U.S. Underground Nuclear Test Conducted

43

Fehner and Gosling, Atmospheric Nuclear Weapons Testing, 1951...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Test Site, Volume I Terrence R. Fehner and F.G. Gosling. Atmospheric Nuclear Weapons Testing, 1951-1963. Battlefield of the Cold War: The Nevada Test Site, Volume I (pdf)....

44

First Thermonuclear Device Successfully Tested | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Thermonuclear Device Successfully Tested | National Nuclear Security Thermonuclear Device Successfully Tested | 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 > About Us > Our History > NNSA Timeline > First Thermonuclear Device Successfully Tested First Thermonuclear Device Successfully Tested December 31, 1952 Enewetak Atoll First Thermonuclear Device Successfully Tested

45

First Plutonium Bomb Successfully Tested | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Plutonium Bomb Successfully Tested | National Nuclear Security Plutonium Bomb Successfully Tested | 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 > About Us > Our History > NNSA Timeline > First Plutonium Bomb Successfully Tested First Plutonium Bomb Successfully Tested July 16, 1945 Los Alamos, NM First Plutonium Bomb Successfully Tested

46

First Plutonium Bomb Successfully Tested | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Plutonium Bomb Successfully Tested | National Nuclear Security Plutonium Bomb Successfully Tested | 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 > About Us > Our History > NNSA Timeline > First Plutonium Bomb Successfully Tested First Plutonium Bomb Successfully Tested July 16, 1945 Los Alamos, NM First Plutonium Bomb Successfully Tested

47

Office of Test and Evaluation | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Office of Test and Evaluation Home > About Us > Our Programs >...

48

Contaminant Boundary at the Faultless Underground Nuclear Test  

SciTech Connect

The U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP) have reached agreement on a corrective action strategy applicable to address the extent and potential impact of radionuclide contamination of groundwater at underground nuclear test locations. This strategy is described in detail in the Federal Facility Agreement and Consent Order (FFACO, 2000). As part of the corrective action strategy, the nuclear detonations that occurred underground were identified as geographically distinct corrective action units (CAUs). The strategic objective for each CAU is to estimate over a 1,000-yr time period, with uncertainty quantified, the three-dimensional extent of groundwater contamination that would be considered unsafe for domestic and municipal use. Two types of boundaries (contaminant and compliance) are discussed in the FFACO that will map the three-dimensional extent of radionuclide contamination. The contaminant boundary will identify the region wi th 95 percent certainty that contaminants do not exist above a threshold value. It will be prepared by the DOE and presented to NDEP. The compliance boundary will be produced as a result of negotiation between the DOE and NDEP, and can be coincident with, or differ from, the contaminant boundary. Two different thresholds are considered for the contaminant boundary. One is based on the enforceable National Primary Drinking Water Regulations for radionuclides, which were developed as a requirement of the Safe Drinking Water Act. The other is a risk-based threshold considering applicable lifetime excess cancer-risk-based criteria The contaminant boundary for the Faultless underground nuclear test at the Central Nevada Test Area (CNTA) is calculated using a newly developed groundwater flow and radionuclide transport model that incorporates aspects of both the original three-dimensional model (Pohlmann et al., 1999) and the two-dimensional model developed for the Faultless data decision analysis (DDA) (Pohll and Mihevc, 2000). This new model includes the uncertainty in the three-dimensional spatial distribution of lithology and hydraulic conductivity from the 1999 model as well as the uncertainty in the other flow and transport parameters from the 2000 DDA model. Additionally, the new model focuses on a much smaller region than was included in the earlier models, that is, the subsurface within the UC-1 land withdrawal area where the 1999 model predicted radionuclide transport will occur over the next 1,000 years. The purpose of this unclassified document is to present the modifications to the CNTA groundwater flow and transport model, to present the methodology used to calculate contaminant boundaries, and to present the Safe Drinking Water Act and risk-derived contaminant boundaries for the Faultless underground nuclear test CAU.

Greg Pohll; Karl Pohlmann; Jeff Daniels; Ahmed Hassan; Jenny Chapman

2003-04-01T23:59:59.000Z

49

United States nuclear tests, July 1945 through September 1992  

Science Conference Proceedings (OSTI)

This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Several tests conducted during Operation Dominic involved missile launches from Johnston Atoll. Several of these missile launches were aborted, resulting in the destruction of the missile and nuclear device either on the pad or in the air.

Not Available

1994-12-01T23:59:59.000Z

50

TECHNICAL NOTE Testing avian, squamate, and mammalian nuclear markers for  

E-Print Network (OSTI)

TECHNICAL NOTE Testing avian, squamate, and mammalian nuclear markers for cross amplification amplifications to assess 120 previously described nuclear markers for phylogeographic and phylogenetic analysis. marmorata or P. castaneus, and a subset of eight markers amplified single products across a test panel of 11

Grether, Gregory

51

First Thermonuclear Device Successfully Tested | National Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Y-12 Earn 11 R&D 100 Awards Jul 2, 2013 US, International Partners Remove Last Remaining HEU from Vietnam, Set Nuclear Security Milestone View All > Timeline Curious about NNSA...

52

Testing the Physics of Nuclear Isomers  

SciTech Connect

For much of the past century, physicists have searched for methods to control the release of energy stored in an atom's nucleus. Nuclear fission reactors have been one successful approach, but finding other methods to capitalize on this potential energy source have been elusive. One possible source being explored is nuclear isomers. An isomer is a long-lived excited state of an atom's nucleus--a state in which decay back to the nuclear ground state is inhibited. The nucleus of an isomer thus holds an enormous amount of energy. If scientists could develop a method to release that energy instantaneously in a gamma-ray burst, rather than slowly over time, they could use it in a nuclear battery. Research in the late 1990s indicated that scientists were closer to developing such a method--using x rays to trigger the release of energy from the nuclear isomer hafnium-178m ({sup 178m}Hf). To further investigate these claims, the Department of Energy (DOE) funded a collaborative project involving Lawrence Livermore, Los Alamos, and Argonne national laboratories that was designed to reproduce those earlier results.

Hazi, A

2006-01-25T23:59:59.000Z

53

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts associated with the U.S. Department of Energy proposed action to conduct a lead test assembly program to confirm the viability of using a commercial light water reactor to produce tritium. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 22, 1997 EA-1210: Finding of No Significant Impact Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington July 22, 1997 EA-1210: Final Environmental Assessment

54

Nuclear Detection and Sensor Testing Center | Y-12 National Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Detection and ... Detection and ... Nuclear Detection and Sensor Testing Center As part of our increased global nuclear nonproliferation efforts, Y-12 commissioned the Nuclear Detection and Sensor Testing Center, which offers dedicated facilities for the testing of radiation detection capabilities using enriched and highly enriched uranium. In addition to supporting measurements of instrumentation for detecting ionizing radiation, non-destructive measurements of both fissile and non-fissile materials may be deployed at NDSTC. The NDSTC supports proliferation detection, nuclear safeguards, emergency response, treaty verification, and university research. We can test devices with various forms and quantities of HEU, and the Center offers subject matter experts to assist in planning measurements, safely deploy material,

55

Material Testing - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Departments involved: Engineering Development and Applications Irradiated Materials Two hot-cell test facilities are used to develop experimental data on the irradiation-assisted...

56

Life beyond nuclear testing the Nevada Test Site.  

E-Print Network (OSTI)

??The Nevada Test Site (NTS) has served a crucial role in protecting the nation's security over the last 50 years. Changing national budgets and fiscal… (more)

Martinez-Myers, Fina

1999-01-01T23:59:59.000Z

57

CONTROL ROD FOR A NUCLEAR REACTOR AND METHOD OF PREPARATION  

DOE Patents (OSTI)

BS>An improved control rod is presented for a nuclear reactor. This control rod is comprised of a rare earth metal oxide or rare earth metal carbide such as gadolinium oxide or gadolinium carbide, uniformly distributed in a metal matrix having a low cross sectional area of absorption for thermal neutrons, such as aluminum, beryllium, and zirconium.

Hausner, H.H.

1958-12-30T23:59:59.000Z

58

Detailed Burnup Calculations for Testing Nuclear Data  

Science Conference Proceedings (OSTI)

A general method (MCQ) has been developed by introducing a microscopic burnup scheme that uses the Monte Carlo calculated fluxes and microscopic reaction rates of a complex system and a depletion code for burnup calculations as a basis for solving nuclide material balance equations for each spatial region in which the system is divided. Continuous energy-dependent cross-section libraries and full 3D geometry of the system can be input for the calculations. The resulting predictions for the system at successive burnup time steps are thus based on a calculation route where both geometry and cross sections are accurately represented, without geometry simplifications and with continuous energy data, providing an independent approach for benchmarking other methods and nuclear data of actinides, fission products, and other burnable absorbers. The main advantage of this method over the classical deterministic methods currently used is that the MCQ System is a direct 3D method without the limitations and errors introduced on the homogenization of geometry and condensation of energy of deterministic methods. The Monte Carlo and burnup codes adopted until now are the widely used MCNP and ORIGEN codes, but other codes can be used also. For using this method, there is need of a well-known set of nuclear data for isotopes involved in burnup chains, including burnable poisons, fission products, and actinides. For fixing the data to be included in this set, a study of the present status of nuclear data is performed, as part of the development of the MCQ method. This study begins with a review of the available cross-section data of isotopes involved in burnup chains for power and research nuclear reactors. The main data needs for burnup calculations are neutron cross sections, decay constants, branching ratios, fission energy, and yields. The present work includes results of selected experimental benchmarks and conclusions about the sensitivity of different sets of cross-section data for burnup calculations, using some of the main available evaluated nuclear data files (ENDF-B-VI-Rel.8, JEFF-3.0, JENDL-3.3), on an isotope-by-isotope basis as much as possible. The selected experimental burnup benchmarks are reference cases for LWR and HWR reactors, with analysis of isotopic composition as a function of burnup. For LWR (H2O-moderated uranium oxide lattices) four benchmarks are included: ATM-104 NEA Burnup credit criticality benchmark; Yankee-Rowe Core V; H.B.Robinson Unit 2 and Turkey Point Unit 3. For HWR (D2O-moderated uranium oxide cluster lattices), three benchmarks were selected: NPD-19-rod Fuel Clusters; Pickering-28-rod Fuel Clusters; and Bruce-37-rod Fuel Clusters. The isotopes with experimental concentration data included in these benchmarks are: Se-79, Sr90, Tc99, Ru106, Sn126, Sb125,1129, Cs133-137, Nd143, 145, Sm149-150, 152, Eul53-155, U234-235, 238, Np237, Pu238-242, Am241-243, and Cm242-248. Results and analysis of differences between calculated and measured absolute and/or relative concentrations of these isotopes for the seven benchmarks are included in this work.

Leszczynski, F. [Centro Atomico Bariloche (CNEA), 8400 S.C.de Bariloche (Argentina)

2005-05-24T23:59:59.000Z

59

Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report  

Science Conference Proceedings (OSTI)

Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA.

Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic, R.; Shirley, C.

1998-07-01T23:59:59.000Z

60

Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities  

E-Print Network (OSTI)

1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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

Goethite Bench-scale and Large-scale Preparation Tests  

SciTech Connect

The Hanford Waste Treatment and Immobilization Plant (WTP) is the keystone for cleanup of high-level radioactive waste from our nation's nuclear defense program. The WTP will process high-level waste from the Hanford tanks and produce immobilized high-level waste glass for disposal at a national repository, low activity waste (LAW) glass, and liquid effluent from the vitrification off-gas scrubbers. The liquid effluent will be stabilized into a secondary waste form (e.g. grout-like material) and disposed on the Hanford site in the Integrated Disposal Facility (IDF) along with the low-activity waste glass. The major long-term environmental impact at Hanford results from technetium that volatilizes from the WTP melters and finally resides in the secondary waste. Laboratory studies have indicated that pertechnetate ({sup 99}TcO{sub 4}{sup -}) can be reduced and captured into a solid solution of {alpha}-FeOOH, goethite (Um 2010). Goethite is a stable mineral and can significantly retard the release of technetium to the environment from the IDF. The laboratory studies were conducted using reaction times of many days, which is typical of environmental subsurface reactions that were the genesis of this new process. This study was the first step in considering adaptation of the slow laboratory steps to a larger-scale and faster process that could be conducted either within the WTP or within the effluent treatment facility (ETF). Two levels of scale-up tests were conducted (25x and 400x). The largest scale-up produced slurries of Fe-rich precipitates that contained rhenium as a nonradioactive surrogate for {sup 99}Tc. The slurries were used in melter tests at Vitreous State Laboratory (VSL) to determine whether captured rhenium was less volatile in the vitrification process than rhenium in an unmodified feed. A critical step in the technetium immobilization process is to chemically reduce Tc(VII) in the pertechnetate (TcO{sub 4}{sup -}) to Tc(Iv)by reaction with the ferrous ion, Fe{sup 2+}-Fe{sup 2+} is oxidized to Fe{sup 3+} - in the presence of goethite seed particles. Rhenium does not mimic that process; it is not a strong enough reducing agent to duplicate the TcO{sub 4}{sup -}/Fe{sup 2+} redox reactions. Laboratory tests conducted in parallel with these scaled tests identified modifications to the liquid chemistry necessary to reduce ReO{sub 4}{sup -} and capture rhenium in the solids at levels similar to those achieved by Um (2010) for inclusion of Tc into goethite. By implementing these changes, Re was incorporated into Fe-rich solids for testing at VSL. The changes also changed the phase of iron that was in the slurry product: rather than forming goethite ({alpha}-FeOOH), the process produced magnetite (Fe{sub 3}O{sub 4}). Magnetite was considered by Pacific Northwest National Laboratory (PNNL) and VSL to probably be a better product to improve Re retention in the melter because it decomposes at a higher temperature than goethite (1538 C vs. 136 C). The feasibility tests at VSL were conducted using Re-rich magnetite. The tests did not indicate an improved retention of Re in the glass during vitrification, but they did indicate an improved melting rate (+60%), which could have significant impact on HLW processing. It is still to be shown whether the Re is a solid solution in the magnetite as {sup 99}Tc was determined to be in goethite.

Josephson, Gary B.; Westsik, Joseph H.

2011-10-23T23:59:59.000Z

62

Nuclear Test-Experimental Science: Annual report, fiscal year 1988  

Science Conference Proceedings (OSTI)

Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B. (eds.)

1988-01-01T23:59:59.000Z

63

Reactor Safety Testing and Analysis - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

64

Microsoft Word - Remarks as Prepared for Delivery for Assistant Secretary for Nuclear Energy Dennis R. Spurgeon  

NLE Websites -- All DOE Office Websites (Extended Search)

FOR IMMEDIATE RELEASE FOR IMMEDIATE RELEASE Angela Hill, (202) 586-4940 Wednesday, July 23, 2008 Remarks as Prepared for Delivery for Assistant Secretary for Nuclear Energy Dennis R. Spurgeon Second Annual Nuclear Fuel Cycle Monitor Global Nuclear Renaissance Summit Alexandria, VA Thank you for inviting me to address the Second Annual Global Nuclear Renaissance Summit. My topic is the Department of Energy's role in developing our nation's nuclear energy policy: technologically robust, economically sound, and publically acceptable. Although it's last in the title, public acceptability is where we need to start, because without public acceptance, we are fighting an up hill battle. For us in nuclear power to make things publically acceptable means making them

65

Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Vogtle Nuclear Power Plant -- As Vogtle Nuclear Power Plant -- As Prepared for Delivery Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for Delivery February 15, 2012 - 12:27pm Addthis It's great to be with all of you today. I want to acknowledge the many people who are playing a role here: Tom Fanning, President of Southern Company Paul Bowers, President and Chief Executive Officer of Georgia Power Tom Smith, Chief Executive Officer of Oglethorpe Power Bob Johnston, Chief Executive Officer of MEAG (Me-ag) Power Jim Bernhard, President and Chief Executive Officer of The Shaw Group Ric Perez, President of Westinghouse Operations Marv Fertel, President and Chief Executive Officer of the Nuclear Energy Institute; and Finally, all of the workers here, whose skill and expertise are

66

Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Chu's Remarks at Vogtle Nuclear Power Plant -- As Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for Delivery Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for Delivery February 15, 2012 - 12:27pm Addthis It's great to be with all of you today. I want to acknowledge the many people who are playing a role here: Tom Fanning, President of Southern Company Paul Bowers, President and Chief Executive Officer of Georgia Power Tom Smith, Chief Executive Officer of Oglethorpe Power Bob Johnston, Chief Executive Officer of MEAG (Me-ag) Power Jim Bernhard, President and Chief Executive Officer of The Shaw Group Ric Perez, President of Westinghouse Operations Marv Fertel, President and Chief Executive Officer of the Nuclear Energy Institute; and Finally, all of the workers here, whose skill and expertise are

67

Export control guide: Spent nuclear fuel reprocessing and preparation of plutonium metal  

Science Conference Proceedings (OSTI)

The international Treaty on the Non-Proliferation of Nuclear Weapons, also referred to as the Non-Proliferation Treaty (NPT), states in Article III, paragraph 2(b) that {open_quotes}Each State Party to the Treaty undertakes not to provide . . . equipment or material especially designed or prepared for the processing, use or production of special fissionable material to any non-nuclear-weapon State for peaceful purposes, unless the source or special fissionable material shall be subject to the safeguards required by this Article.{close_quotes} This guide was prepared to assist export control officials in the interpretation, understanding, and implementation of export laws and controls relating to the international Trigger List for irradiated nuclear fuel reprocessing equipment, components, and materials. The guide also contains information related to the production of plutonium metal. Reprocessing and its place in the nuclear fuel cycle are described briefly; the standard procedure to prepare metallic plutonium is discussed; steps used to prepare Trigger List controls are cited; descriptions of controlled items are given; and special materials of construction are noted. This is followed by a comprehensive description of especially designed or prepared equipment, materials, and components of reprocessing and plutonium metal processes and includes photographs and/or pictorial representations. The nomenclature of the Trigger List has been retained in the numbered sections of this document for clarity.

NONE

1993-10-01T23:59:59.000Z

68

Handling effluent from nuclear thermal propulsion system ground tests  

SciTech Connect

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the different methods to handle effluent from nuclear thermal propulsion system ground tests.

Shipers, L.R.; Allen, G.C.

1992-09-09T23:59:59.000Z

69

Effluent treatment options for nuclear thermal propulsion system ground tests  

DOE Green Energy (OSTI)

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the strengths and weaknesses of different methods to handle effluent from nuclear thermal propulsion system ground tests.

Shipers, L.R.; Brockmann, J.E.

1992-10-16T23:59:59.000Z

70

Parity- and Time-Reversal Tests in Nuclear Physics  

E-Print Network (OSTI)

Nuclear physics tests of parity- and time-reversal invariance have both shaped the development of the Standard Model and provided key tests of its predictions. These studies now provide vital input in the search for physics beyond the Standard Model. We give a brief review of a few key experimental and theoretical developments in the history of this sub-field of nuclear physics as well as a short outlook, focusing on weak decays, parity-violation in electron scattering, and searches for permanent electric dipole moments of the neutron and neutral atoms.

Hertzog, David

2013-01-01T23:59:59.000Z

71

HALLAM NUCLEAR POWER FACILITY PREOPERATIONAL TEST COMPLETION REPORT, HOT SODIUM CIRCULATION TEST  

SciTech Connect

Tests were conducted to verify the adequacy of the design, construction, and components of the main heat transfer system of the Hallam Nuclear Power Facility (HNPF) for elevated-temperature and low-power operation. Tests revealed piping interferences, inoperative hangars, and valve difficulties. These discrepancies were rectified and rechecked. Detailed information concerning test results is included. (J.R.D.)

Shaw, P.F.; Johnson, L.L.

1962-07-01T23:59:59.000Z

72

CERCLA Preliminary Assessment of DOE'S Nevada Operations Office Nuclear Weapons Testing  

Office of Legacy Management (LM)

tudies/B ackground tudies/B ackground Book 1 CERCLA Preliminary Assessment of DOE'S Nevada Operations Office Nuclear Weapons Testing Areas Vol. 11, April 1988 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. CERCLA PRELIMINARY ASSESSMENT OF DOE'S NEVADA OPERATIONS OFFICE WCILEAR WEAPONS T E S r n G AREAS Prepared by Water Resources Center Desert Research Institute University of Nevada System ,Prepared for U . S . Department of Energy Nevada Operations Office Las Vegas, Nevada under contract DE-AC08-85NV10384 A p r i l 1988 CONTENTS VOLUME I I. INTRODUCTION 1.1 11. NEVADA TEST SITE TESTING AREAS 2.1 Frenchman Flat (Area 5) 2.1.1 2.2 Yucca Flat (Areas 1, 2, 3, 4, 6, 7, 8, 9, 10, 11, and 15)

73

Results from Nevada Nuclear Waste Storage Investigations (NNWSI) Series 3 spent fuel dissolution tests  

SciTech Connect

The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Yucca Mountain Project (YMP), formerly the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Specimens prepared from pressurized water reactor fuel rod segments were tested in sealed stainless steel vessels in Nevada Test Site J-13 well water at 85{degree}C and 25{degree}C. The test matrix included three specimens of bare-fuel particles plus cladding hulls, two fuel rod segments with artificially defected cladding and water-tight end fittings, and an undefected fuel rod section with watertight end fittings. Periodic solution samples were taken during test cycles with the sample volumes replenished with fresh J-13 water. Test cycles were periodically terminated and the specimens restarted in fresh J-13 water. The specimens were run for three cycles for a total test duration of 15 months. 22 refs., 32 figs., 26 tabs.

Wilson, C.N.

1990-06-01T23:59:59.000Z

74

Special Nuclear Material Portal Monitoring at the Nevada Test Site  

SciTech Connect

Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program.

DeAnn Long; Michael Murphy

2008-07-01T23:59:59.000Z

75

Nuclear waste repository transparency technology test bed demonstrations at WIPP  

SciTech Connect

Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ``The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic repository, the Waste Isolation Pilot Plant (WIPP) offers a unique opportunity to serve as an international cooperative test bed for developing and demonstrating technologies and processes in a fully operational repository system setting. To address the substantial national security implications for the US resulting from the lack of integrated, transparent management and disposition of nuclear materials at the back-end of the nuclear fuel and weapons cycles, it is proposed that WIPP be used as a test bed to develop and demonstrate technologies that will enable the transparent and proliferation-resistant geologic isolation of nuclear materials. The objectives of this initiative are to: (1) enhance public confidence in safe, secure geologic isolation of nuclear materials; (2) develop, test, and demonstrate transparency measures and technologies for the back-end of nuclear fuel cycle; and (3) foster international collaborations leading to workable, effective, globally-accepted standards for the transparent monitoring of geological repositories for nuclear materials. Test-bed activities include: development and testing of monitoring measures and technologies; international demonstration experiments; transparency workshops; visiting scientist exchanges; and educational outreach. These activities are proposed to be managed by the Department of Energy/Carlsbad Area Office (DOE/CAO) as part of The Center for Applied Repository and Underground Studies (CARUS).

BETSILL,J. DAVID; ELKINS,NED Z.; WU,CHUAN-FU; MEWHINNEY,JAMES D.; AAMODT,PAUL

2000-01-27T23:59:59.000Z

76

Nuclear Maintenance Applications Center: Effective Refueling Outage Preparation and Execution Guidance--Revision to 1014480  

Science Conference Proceedings (OSTI)

This report provides updated, current guidance to assist outage managers and teams during preparation and execution phases of a nuclear refueling outage. Included is guidance on how the outage activities support long-range and strategic plans developed by the site or fleet of units.

2011-12-13T23:59:59.000Z

77

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities  

SciTech Connect

This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24.

1993-11-01T23:59:59.000Z

78

Gamma-Ray Bursts Nuclear Test Ban Treaty, 1963  

E-Print Network (OSTI)

Lecture 18 Gamma-Ray Bursts #12;Nuclear Test Ban Treaty, 1963 First Vela satellite pair launched and their predecessors, Vela 4, discovered the first gamma-ray bursts. The discovery was announced by Klebesadel, Strong, and Olson (ApJ, 182, 85) in 1973. #12;First Gamma-Ray Burst The Vela 5 satellites functioned from July, 1969

Harrison, Thomas

79

Accelerated Testing of Neutron-Absorbing Alloys for Nuclear Criticality Control  

Science Conference Proceedings (OSTI)

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems

R. E. Mizia; T. E. Lister

80

Testing of Small Graphite Samples for Nuclear Qualification  

Science Conference Proceedings (OSTI)

Accurately determining the mechanical properties of small irradiated samples is crucial to predicting the behavior of the overal irradiated graphite components within a Very High Temperature Reactor. The sample size allowed in a material test reactor, however, is limited, and this poses some difficulties with respect to mechanical testing. In the case of graphite with a larger grain size, a small sample may exhibit characteristics not representative of the bulk material, leading to inaccuracies in the data. A study to determine a potential size effect on the tensile strength was pursued under the Next Generation Nuclear Plant program. It focuses first on optimizing the tensile testing procedure identified in the American Society for Testing and Materials (ASTM) Standard C 781-08. Once the testing procedure was verified, a size effect was assessed by gradually reducing the diameter of the specimens. By monitoring the material response, a size effect was successfully identified.

Julie Chapman

2010-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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

Advanced Nuclear Technology: Final Test Results on 80% Service Test and Implementation Plans  

Science Conference Proceedings (OSTI)

Current practice within the nuclear power industry is to use performance discharge tests for condition monitoring to determine when a battery has reached 80% of its rated capacity, which is considered the end of its service life. A service test is now used every refueling outage to verify that a battery can satisfy its design basis function as defined by the battery duty cycle. A modified performance test is used at ...

2013-04-03T23:59:59.000Z

82

Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3009-94 3009-94 July 1994 CHANGE NOTICE NO.1 January 2000 CHANGE NOTICE NO. 2 April 2002 CHANGE NOTICE NO. 3 March 2006 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-3009-94 Page ii This document has been reproduced directly 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. DOE-STD-3009-94 Page iii Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses Table of Changes

83

Sodium Plugging Test Loop - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Sodium Plugging Test Loop Sodium Plugging Test Loop Sodium Plugging Test Loop Overview Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sodium Plugging Test Loop This experimental setup is part of the Global Nuclear Energy Partnership (GNEP) Advanced Fuel Cycle R&D work carried out at Argonne on advanced sodium component technology. Bookmark and Share For long range sodium technology research and development, employing supercritical CO2 Brayton cycle power conversion technology as an advanced balance of plant technology is being considered. The component that provides the interface between the sodium and supercritical CO2 is a compact heat exchanger known as a printed circuit heat exchanger (PCHE). This heat exchanger has very small coolant flow passages that may foul or

84

Non-Destructive Evaluation (NDE) and Testing Facilities - Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Facilities > Non-Destructive Facilities > Non-Destructive Evaluation (NDE) and Testing Facilities Non-Destructive Evaluation (NDE) and Testing Facilities Overview MTS Table Top Load Frame X-ray Inspection Systems Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Non-Destructive Evaluation (NDE) and Testing Facilities The Non-Destructive Evaluation (NDE) and Testing Facilities contain state-of-the-art NDE laboratories including microwave/millimeter wave, acoustic/ultrasonic, X-ray, thermal imaging, optics, and eddy current for health monitoring of materials and components used in aerospace, defense, and power generation (fossil and nuclear) industries as well as for medical and scientific research. Bookmark and Share

85

Preparing for Mira: experience with FLASH multiphysics simulations - Petascale Simulations of Turbulent Nuclear Combustion  

NLE Websites -- All DOE Office Websites (Extended Search)

Code Code changes Optimization Performance Conclusion Preparing for Mira: experience with FLASH multiphysics simulations Petascale Simulations of Turbulent Nuclear Combustion Christopher Daley 1 2 1 The Flash Center for Computational Science at the University of Chicago 2 Argonne National Laboratory March 7, 2013 1 / 30 Outline Introduction Code changes Optimization Performance Conclusion 1 Introduction 2 Code changes Updating FLASH for BG/Q 3 Optimization Initialization Evolution 4 Performance Best FLASH configuration Scaling and hardware counter data 5 Conclusion 2 / 30 Outline Introduction Code changes Optimization Performance Conclusion Science objectives To improve our understanding of the explosion mechanism of Type Ia Supernova Simulate two key physical processes with the FLASH code: 1 Buoyancy-driven turbulent nuclear combustion Determines the amount of nuclear

86

Tests of time independence of the electron and nuclear masses with ultracold molecules S. Schiller  

E-Print Network (OSTI)

Tests of time independence of the electron and nuclear masses with ultracold molecules S. Schiller. Korobov Joint Institute for Nuclear Research, 141980, Dubna, Russia Received 18 June 2004; published 17 on the time independence of electron-to-nuclear and nuclear-nuclear mass ratios by comparing, via an optical

Schiller, Stephan

87

Status of Centralized Environmental Creep Testing Facility Preparation and Upgrade  

SciTech Connect

Because the ASME Codes do not cover environmental issues that are crucial in the design and construction of VHTR system, investigation of long-term impure helium effects on metallurgical stability and properties becomes very important. The present report describes the development of centralized environmental creep testing facility, its close collaborations with the experiments in low velocity helium recirculation loop, important lessons learned, upgrades in system design in FY06, and current status of the development.

Ren, Weiju [ORNL; Battiste, Rick [ORNL

2006-10-01T23:59:59.000Z

88

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride  

E-Print Network (OSTI)

1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride UF6. Most of these test methods are in routine use to determine conformance to UF6 specifications in the Enrichment and Conversion Facilities. 1.2 The analytical procedures in this document appear in the following order: Note 1—Subcommittee C26.05 will confer with C26.02 concerning the renumbered section in Test Methods C761 to determine how concerns with renumbering these sections, as analytical methods are replaced with stand-alone analytical methods, are best addressed in subsequent publications. Sections Subsampling of Uranium Hexafluoride 7 - 10 Gravimetric Determination of Uranium 11 - 19 Titrimetric Determination of Uranium 20 Preparation of High-Purity U3O 8 21 Isotopic Analysis 22 Isotopic Analysis by Double-Standard Mass-Spectrometer Method 23 - 29 Determination of Hydrocarbons, Chlorocarbons, and Partially Substitut...

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

89

INDUSTRIAL HYGIENE ASPECTS OF UNDERGROUND NUCLEAR WEAPON TEST DEBRIS RECOVERY  

SciTech Connect

The formation of a collapse crater by underground nuclear explosions is described. Safety problems associated with the re-entry of underground nuclear explosion areas include cavity collapse, toxic gases, explosive gases, radioactive gases, radioactive core, and hazards from the movement of heavy equipment on unstable ground. Data irom television, geophones, and telemetered radiation detectors determine when radiation and toxic material surveys of the area can be made and drills can be used to obtain samples of the bubble crust for analysis. Hazards to persornel engaged in obtaining weapon debris samples are reviewed. Data are presented on the radiation dose received by personnel at the Nevada Test Site engaged in this work during 1962. (C.H.)

Wilcox, F.W.

1963-03-27T23:59:59.000Z

90

Pyroprocessing of Fast Flux Test Facility Nuclear Fuel  

SciTech Connect

Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.

B.R. Westphal; G.L. Fredrickson; G.G. Galbreth; D. Vaden; M.D. Elliott; J.C. Price; E.M. Honeyfield; M.N. Patterson; L. A. Wurth

2013-10-01T23:59:59.000Z

91

Azimuthal Anisotropies as Stringent Test for Nuclear Transport Models  

E-Print Network (OSTI)

Azimuthal distributions of charged particles and intermediate mass fragments emitted in Au+Au collisions at 600AMeV have been measured using the FOPI facility at GSI-Darmstadt. Data show a strong increase of the in-plane azimuthal anisotropy ratio with the charge of the detected fragment. Intermediate mass fragments are found to exhibit a strong momentum-space alignment with respect of the reaction plane. The experimental results are presented as a function of the polar center-of-mass angle and over a broad range of impact parameters. They are compared to the predictions of the Isospin Quantum Molecular Dynamics model using three different parametrisations of the equation of state. We show that such highly accurate data provide stringent test for microscopic transport models and can potentially constrain separately the stiffness of the nuclear equation of state and the momentum dependence of the nuclear interaction.

P. Crochet; F. Rami; R. Dona; the FOPI Collaboration

1997-09-15T23:59:59.000Z

92

Special Nuclear Material Portal Monitoring at the Nevada Test Site  

SciTech Connect

In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC&A) Manager at the time decided that the program needed to be strengthened and MC&A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program.

Mike Murphy

2008-03-01T23:59:59.000Z

93

Admission Test Preparation Admission test scores help professional and graduate programs determine who to admit (and, in some cases, to award merit-  

E-Print Network (OSTI)

Admission Test Preparation Admission test scores help professional and graduate programs determine-prepared for these tests. Some are tests of aptitude in quantitative skills, verbal and analytical reasoning and/or writing ability (e.g., GRE, LSAT, GMAT), while others are tests of content knowledge (e.g., GRE Subject Tests

Hampton, Randy

94

High-precision location and yield of North Korea's 2013 nuclear test Miao Zhang1  

E-Print Network (OSTI)

High-precision location and yield of North Korea's 2013 nuclear test Miao Zhang1 and Lianxing Wen2 Korea's 2009 nuclear test as reference and satellite imagery, we show that the location and yield of North Korea's 2013 nuclear test can be quickly and accurately determined based on seismic data. North

Wen, Lianxing

95

Background Radiation Survey of the Radiological/Nuclear Countermeasures Test and Evaluation Center  

SciTech Connect

In preparation for operations at the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC), the Department of Homeland Security Domestic Nuclear Detection Office (DHS/DNDO) requested that personnel from the Remote Sensing Laboratory (RSL) conduct a survey of the present radiological conditions at the facility. The measurements consist of the exposure rate from a high-pressure ion chamber (HPIC), high-resolution spectra from a high-purity germanium (HPGe) system in an in situ configuration, and low-resolution spectra from a sodium iodide (NaI) detector in a radiation detection backpack. Measurements with these systems were collected at discrete locations within the facility. Measurements were also collected by carrying the VECTOR backpack throughout the complex to generate a map of the entire area. The area was also to be surveyed with the Kiwi (an array of eight-2-inch x 4-inch x 16-inch NaI detectors) from the Aerial Measuring Systems; however, conflicts with test preparation activities at the site prevented this from being accomplished.

Colin Okada

2010-09-16T23:59:59.000Z

96

Experimental Test of Complementarity by Nuclear Magnetic Resonance Techniques  

E-Print Network (OSTI)

We have tested complementarity for the ensemble-averaged spin states of nuclei $^{13}$C in the molecule of $^{13}$CHCl$_{3}$ by the use of the spin states of another nuclei $^{1}$H as the path marker. It turns out that the wave-particle duality holds when one merely measures the probability density of quantum states, and that the wave- and particle-like behavior is simultaneously observed with the help of measuring populations and coherence in a single nuclear magnetic resonance(NMR) experiment. Effects of path-marking schemes and causes of the appearance and disappearance of the wave behavior are analysed.

Xiwen Zhu; Ximing Fang; Xinhua Peng; Mang Feng; Kelin Gao; Fei Du

2000-11-22T23:59:59.000Z

97

An assessment of testing requirement impacts on nuclear thermal propulsion ground test facility design  

SciTech Connect

Programs to develop solid core nuclear thermal propulsion (NTP) systems have been under way at the Department of Defense (DoD), the National Aeronautics and Space Administration (NASA), and the Department of Energy (DOE). These programs have recognized the need for a new ground test facility to support development of NTP systems. However, the different military and civilian applications have led to different ground test facility requirements. The Department of Energy (DOE) in its role as landlord and operator of the proposed research reactor test facilities has initiated an effort to explore opportunities for a common ground test facility to meet both DoD and NASA needs. The baseline design and operating limits of the proposed DoD NTP ground test facility are described. The NASA ground test facility requirements are reviewed and their potential impact on the DoD facility baseline is discussed.

Shipers, L.R.; Ottinger, C.A.; Sanchez, L.C.

1993-10-25T23:59:59.000Z

98

Assessment of a hot hydrogen nuclear propulsion fuel test facility  

DOE Green Energy (OSTI)

Subsequent to the announcement of the Space Exploration Initiative (SEI), several studies and review groups have identified nuclear thermal propulsion as a high priority technology for development. To achieve the goals of SEI to place man on Mars, a nuclear rocket will operate at near 2700K and in a hydrogen environment at near 60 atmospheres. Under these conditions, the operational lifetime of the rocket will be limited by the corrosion rate at the hydrogen/fuel interface. Consequently, the Los Alamos National Laboratory has been evaluating requirements and design issues for a test facility. The facility will be able to directly heat fuel samples by electrical resistance, microwave deposition, or radio frequency induction heating to temperatures near 3000K. Hydrogen gas at variable pressure and temperatures will flow through the samples. The thermal gradients, power density, and operating times envisioned for nuclear rockets will be duplicated as close as reasonable. The post-sample flow stream will then be scrubbed and cooled before reprocessing. The baseline design and timetable for the facility will be discussed. 7 refs.

Watanabe, H.H.; Howe, S.D.; Wantuck, P.J.

1991-01-01T23:59:59.000Z

99

HIGH SODIUM SIMULANT TESTING TO SUPPORT SB8 SLUDGE PREPARATION  

Science Conference Proceedings (OSTI)

Scoping studies were completed for high sodium simulant SRAT/SME cycles to determine any impact to CPC processing. Two SRAT/SME cycles were performed with simulant having sodium supernate concentration of 1.9M at 130% and 100% of the Koopman Minimum Acid requirement. Both of these failed to meet DWPF processing objectives related to nitrite destruction and hydrogen generation. Another set of SRAT/SME cycles were performed with simulant having a sodium supernate concentration of 1.6M at 130%, 125%, 110%, and 100% of the Koopman Minimum Acid requirement. Only the run at 110% met DWPF processing objectives. Neither simulant had a stoichiometric factor window of 30% between nitrite destruction and excessive hydrogen generation. Based on the 2M-110 results it was anticipated that the 2.5M stoichiometric window for processing would likely be smaller than from 110-130%, since it appeared that it would be necessary to increase the KMA factor by at least 10% above the minimum calculated requirement to achieve nitrite destruction due to the high oxalate content. The 2.5M-130 run exceeded the DWPF hydrogen limits in both the SRAT and SME cycle. Therefore, testing of this wash endpoint was halted. This wash endpoint with this minimum acid requirement and mercury-noble metal concentration profile appears to be something DWPF should not process due to an overly narrow window of stoichiometry. The 2M case was potentially processable in DWPF, but modifications would likely be needed in DWPF such as occasionally accepting SRAT batches with undestroyed nitrite for further acid addition and reprocessing, running near the bottom of the as yet ill-defined window of allowable stoichiometric factors, potentially extending the SRAT cycle to burn off unreacted formic acid before transferring to the SME cycle, and eliminating formic acid additions in the frit slurry.

Newell, J.

2012-09-19T23:59:59.000Z

100

Thermally Induced Groundwater Flow Resulting from an Underground Nuclear Test  

SciTech Connect

The authors examine the transient residual thermal signal resulting from an underground nuclear test (buried below the water table) and its potential to affect local groundwater flow and radionuclide migration in a saturated, fractured, volcanic aquifer system. Thermal profiles measured in a drillback hole between 154 days and 6.5 years after the test have been used to calibrate a non-isothermal model of fluid flow. In this process, they have estimated the magnitude and relative changes in permeability, porosity and fracture density between different portions of the disturbed and undisturbed geologic medium surrounding the test location. The relative impacts of buoyancy forces (arising from the thermal residual of the test and the background geothermal gradient) and horizontal pressure gradients on the post-test flow system are better understood. A transient particle/streamline model of contaminant transport is used to visualize streamlines and streaklines of the flow field and to examine the migration of non-reactive radionuclides. Sensitivity analyses are performed to understand the effects of local and sub-regional geologic features, and the effects of fractured zones on the movement of groundwater and thermal energy. Conclusions regarding the overall effect of the thermal regime on the residence times and fluxes of radionuclides out of the system are drawn, and implications for more complicated, reactive contaminant transport are discussed.

Maxwell, R.M.; Tompson, A.F.B.; Rambo, J.T.; Carle, S.F.; Pawloski, G.A.

2000-12-16T23:59:59.000Z

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101

Evaluating the Effects of Underground Nuclear Testing Below the Water Table on Groundwater and Radionuclide Migration in the  

E-Print Network (OSTI)

Evaluating the Effects of Underground Nuclear Testing Below the Water Table on Groundwater, using FEHM, evaluate perturbed groundwater behavior associated with underground nuclear tests to an instantaneous pressurization event caused by a nuclear test when different permeability and porosity

102

Prepared  

Office of Legacy Management (LM)

Prepared Prepared by Oak Ridge Associated Universities Prepared for Division of Remedial Action Projects U.S. Department of Energy COMPREHENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTYM NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK B.P. ROCCO Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT May 1983 B.P. Rocco FINAL REPORT Prepared for A.M. pitt T.J. Sowell C.F. Weaver T.S. Yoo Project Staff Prepared by J.D. Berger R.D. Condra R.C. Gosslee J.A. Mattina OFF-SITE PROPERTY M NIAGARA FALLS STORAGE SITE LEWISTON, NEW YORK CO~WREHENSIVE RADIOLOGICAL SURVEY Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 U.S. Department of Energy as part of the Formerly Utilized Sites -- Remedial Action Program May 1983 -- til - This

103

Laser-Triggered Lightning Laboratory Tests: Preparation for Testing at Mississippi State University High-Voltage Laboratory  

Science Conference Proceedings (OSTI)

Lightning diversion using laser technology could be operationally used in the power industry to protect sensitive facilities such as nuclear power plants and critical substations, control centers, and customer facilities. This report provides results to date and plans for large-scale, high-voltage laboratory testing of laser-triggered lightning technology.

1998-01-15T23:59:59.000Z

104

Evolution of the N = 28 shell closure: a test bench for nuclear forces  

E-Print Network (OSTI)

Evolution of the N = 28 shell closure: a test bench for nuclear forces O. Sorlin1 and M.-G. Porquet;The N = 28 shell closure: a test bench for nuclear forces 2 reach a value of 4.8 MeV. This effect has and 90). More generally, questions related to the evolution of nuclear forces towards the drip

Paris-Sud XI, Université de

105

Top UN officials call on hold-out States to ratify treaty banning nuclear tests  

E-Print Network (OSTI)

Top UN officials call on hold-out States to ratify treaty banning nuclear tests 29 August 2011 in Kurchatov, Kazakhstan. (June 2010) 29 August 2011 ­ Warning that voluntary moratoriums on nuclear weapon War, hundreds of nuclear weapon tests left behind a devastating legacy for local citizens

106

Colour transparency: a novel test of QCD in nuclear interactions  

E-Print Network (OSTI)

Colour transparency is a cute and indispensable property of QCD as the gauge theory of strong interaction. CT tests of QCD consist of production of the perturbative small-sized hadronic state and measuring the strngth of its non-perturbative diffraction nteraction in a nuclear matter. The energy depenednce of the final- state interaction in a nuclear matter probes a dynamical evolution from the perturbative small-sized state to the full-sized nonperturbative hadron. QCD observables of CT experiments correspond to a novel mechanism of scanning of hadronic wave functions from the large nonperturbative to the small perturbative size. In these lectures, which are addressed to experimentalists and theorists, I discuss the principle ideas of CT physics and the physics potential of the hadron and electron facilities in the > 10 GeV energy range. The special effort was made to present the material in the pedagigical and self-consistent way, with an emphasis on the underlying rich quantum-mechanical interference phenomena.

N. N. Nikolaev

1993-04-20T23:59:59.000Z

107

Transient Testing of Nuclear Fuels and Materials in United States  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) has been engaged in an effort to develop and qualify next generation LWR fuel with enhanced performance and safety and reduced waste generation since 2010. This program, which has emphasized collaboration between the DOE, U.S. national laboratories and nuclear industry, was refocused from enhanced performance to enhanced accident tolerance following the events at Fukushima in 2011. Accident tolerant fuels have been specifically described as fuels that, in comparison with standard UO2-Zircaloy, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, as well as design-basis and beyond design-basis events. The program maintains an ambitious goal to insert a lead test assembly (LTA) of the new design into a commercial power reactor by 2022 .

Daniel M. Wachs

2012-12-01T23:59:59.000Z

108

Radionuclide Partitioning in an Underground Nuclear Test Cavity  

Science Conference Proceedings (OSTI)

In 2004, a borehole was drilled into the 1983 Chancellor underground nuclear test cavity to investigate the distribution of radionuclides within the cavity. Sidewall core samples were collected from a range of depths within the re-entry hole and two sidetrack holes. Upon completion of drilling, casing was installed and a submersible pump was used to collect groundwater samples. Test debris and groundwater samples were analyzed for a variety of radionuclides including the fission products {sup 99}Tc, {sup 125}Sb, {sup 129}I, {sup 137}Cs, and {sup 155}Eu, the activation products {sup 60}Co, {sup 152}Eu, and {sup 154}Eu, and the actinides U, Pu, and Am. In addition, the physical and bulk chemical properties of the test debris were characterized using Scanning Electron Microscopy (SEM) and Electron Microprobe measurements. Analytical results were used to evaluate the partitioning of radionuclides between the melt glass, rubble, and groundwater phases in the Chancellor test cavity. Three comparative approaches were used to calculate partitioning values, though each method could not be applied to every nuclide. These approaches are based on: (1) the average Area 19 inventory from Bowen et al. (2001); (2) melt glass, rubble, and groundwater mass estimates from Zhao et al. (2008); and (3) fission product mass yield data from England and Rider (1994). The U and Pu analyses of the test debris are classified and partitioning estimates for these elements were calculated directly from the classified Miller et al. (2002) inventory for the Chancellor test. The partitioning results from this study were compared to partitioning data that were previously published by the IAEA (1998). Predictions of radionuclide distributions from the two studies are in agreement for a majority of the nuclides under consideration. Substantial differences were noted in the partitioning values for {sup 99}Tc, {sup 125}Sb, {sup 129}I, and uranium. These differences are attributable to two factors: chemical volatility effects that occur during the initial plasma condensation, and groundwater remobilization that occurs over a much longer time frame. Fission product partitioning is very sensitive to the early cooling history of the test cavity because the decay of short-lived (t{sub 1/2} data to update the range in partitioning values for contaminant transport models at the Nevada National Security Site (formerly known as the Nevada Test Site).

Rose, T P; Hu, Q; Zhao, P; Conrado, C L; Dickerson, R; Eaton, G F; Kersting, A B; Moran, J E; Nimz, G; Powell, B A; Ramon, E C; Ryerson, F J; Williams, R W; Wooddy, P T; Zavarin, M

2009-01-09T23:59:59.000Z

109

Interim report spent nuclear fuel retrieval system fuel handling development testing  

Science Conference Proceedings (OSTI)

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01T23:59:59.000Z

110

Three Successful Tests of Color Transparency and Nuclear Filtering  

E-Print Network (OSTI)

We review the theoretical formalism for hard exclusive processes in a nuclear medium. Theory suggests that these processes will show the very interesting phenomena of color transparency and nuclear filtering. The survival probability in nuclear media has also been predicted to show a scaling behavior at large momentum and large nuclear number. We show that all of these effects may have already been seen experimentally.

Pankaj Jain; John P. Ralston

1993-10-06T23:59:59.000Z

111

Experimental results from pressure testing a 1:6-scale nuclear power plant containment  

Science Conference Proceedings (OSTI)

This report discusses the testing of a 1:6-scale, reinforced-concrete containment building at Sandia National Laboratories, in Albuquerque, New Mexico. The scale-model, Light Water Reactor (LWR) containment building was designed and built to the American Society of Mechanical Engineers (ASME) code by United Engineers and Constructors, Inc., and was instrumented with over 1200 transducers to prepare for the test. The containment model was tested to failure to determine its response to static internal overpressurization. As part of the US Nuclear Regulatory Commission`s program on containment integrity, the test results will be used to assess the capability of analytical methods to predict the performance of containments under severe-accident loads. The scaled dimensions of the cylindrical wall and hemispherical dome were typical of a full-size containment. Other typical features included in the heavily reinforced model were equipment hatches, personnel air locks, several small piping penetrations, and a ihin steel liner that was attached to the concrete by headed studs. In addition to the transducers attached to the model, an acoustic detection system and several video and still cameras were used during testing to gather data and to aid in the conduct of the test. The model and its instrumentation are briefly discussed, and is followed by the testing procedures and measured response of the containment model. A summary discussion is included to aid in understanding the significance of the test as it applies to real world reinforced concrete containment structures. The data gathered during SIT and overpressure testing are included as an appendix.

Horschel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

1992-01-01T23:59:59.000Z

112

Isotropic and Nonisotropic Components of Earthquakes and Nuclear Explosions on the Lop Nor Test Site, China  

E-Print Network (OSTI)

Isotropic and Nonisotropic Components of Earthquakes and Nuclear Explosions on the Lop Nor Test and 1996 following events (seven nuclear explosions, three earthquakes) that occurred on the Lop Nor test Abstract Ð We test the hypothesis that the existence of an observable non-zero isotropic component

Ritzwolle, Mike

113

Mine seismicity and the Comprehensive Nuclear Test Ban Treaty  

SciTech Connect

Surface and underground mining operations generate seismic ground motions which are created by chemical explosions and ground failures. It may come as a surprise to some that the ground failures (coal bumps, first caves, pillar collapses, rockbursts, etc.) can send signals whose magnitudes are as strong or stronger than those from any mining blast. A verification system that includes seismic, infrasound, hydroacoustic and radionuclide sensors is being completed as part of the CTBT. The largest mine blasts and ground failures will be detected by this system and must be identified as distinct from signals generated by small nuclear explosions. Seismologists will analyze the seismic records and presumably should be able to separate them into earthquake-like and non earthquake-like categories, using a variety of so-called seismic discriminants. Non-earthquake essentially means explosion- or implosion-like. Such signals can be generated not only by mine blasts but also by a variety of ground failures. Because it is known that single-fired chemical explosions and nuclear explosion signals of the same yield give very similar seismic records, the non-earthquake signals will be of concern to the Treaty verification community. The magnitude of the mine-related events is in the range of seismicity created by smaller nuclear explosions or decoupled tests, which are of particular concern under the Treaty. It is conceivable that legitimate mining blasts or some mine-induced ground failures could occasionally be questioned. Information such as shot time, location and design parameters may be all that is necessary to resolve the event identity. In rare instances where the legitimate origin of the event could not be resolved by a consultation and clarification procedure, it might trigger on On-Site Inspection (OSI). Because there is uncertainty in the precise location of seismic event as determined by the International Monitoring System (IMS), the OSI can cover an area of up to 1,000 squared kilometers. In active mining districts this area could include several different mining operations. So, an OSI could be disruptive both to the mining community and to the US Government which must host the foreign inspection team. Accordingly, it is in the best interest of all US parties to try and eliminate the possible occurrence of false alarms. This can be achieved primarily by reducing the ambiguity of mine-induced seismic signals, so that even if these remain visible to the IMS they are clearly consistent with recognizable mining patterns.

Chiappetta, F. [Blasting Analysis International, Allentown, PA (United States); Heuze, F.; Walter, W. [Lawrence Livermore National Lab., CA (United States); Hopler, R. [Powderman Consulting Inc., Oxford, MD (United States); Hsu, V. [Air Force Technical Applications Center, Patrick AFB, FL (United States); Martin, B. [Thunder Basin Coal Co., Wright, WY (United States); Pearson, C. [Los Alamos National Lab., NM (United States); Stump, B. [Southern Methodist Univ., Dallas, TX (United States); Zipf, K. [Univ. of New South Wales (Australia)

1998-12-09T23:59:59.000Z

114

Recycle Waste Collection Tank (RWCT) simulant testing in the PVTD feed preparation system  

Science Conference Proceedings (OSTI)

(This is part of the radwaste vitrification program at Hanford.) RWCT was to routinely receive final canister decontamination sand blast frit and rinse water, Decontamination Waste Treatment Tank bottoms, and melter off-gas Submerged Bed Scrubber filter cake. In order to address the design needs of the RWCT system to meet performance levels, the PNL Vitrification Technology (PVTD) program used the Feed Preparation Test System (FPTS) to evaluate its equipment and performance for a simulant of RWCT slurry. (FPTS is an adaptation of the Defense Waste Processing Facility feed preparation system and represents the initially proposed Hanford Waste Vitrification Plant feed preparation system designed by Fluor-Daniel, Inc.) The following were determined: mixing performance, pump priming, pump performance, simulant flow characterization, evaporator and condenser performance, and ammonia dispersion. The RWCT test had two runs, one with and one without tank baffles.

Abrigo, G.P.; Daume, J.T.; Halstead, S.D.; Myers, R.L.; Beckette, M.R.; Freeman, C.J.; Hatchell, B.K.

1996-03-01T23:59:59.000Z

115

NNSA Commemorates the 20th Anniversary of the Last Underground Nuclear Test  

National Nuclear Security Administration (NNSA)

the 20th Anniversary of the Last Underground Nuclear Test the 20th Anniversary of the Last Underground Nuclear Test | 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 > Media Room > Video Gallery > NNSA Commemorates the 20th Anniversary of the ... NNSA Commemorates the 20th Anniversary of the Last Underground Nuclear Test NNSA Commemorates the 20th Anniversary of the Last Underground Nuclear Test

116

NNSA Commemorates the 20th Anniversary of the Last Underground Nuclear Test  

NLE Websites -- All DOE Office Websites (Extended Search)

the 20th Anniversary of the Last Underground Nuclear Test the 20th Anniversary of the Last Underground Nuclear Test | 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 > Media Room > Video Gallery > NNSA Commemorates the 20th Anniversary of the ... NNSA Commemorates the 20th Anniversary of the Last Underground Nuclear Test NNSA Commemorates the 20th Anniversary of the Last Underground Nuclear Test

117

Preparation Guide for U. S. Department of Energy Nonreator Nuclear Facility Document Safety Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SENSITIVE DOE-STD-3009-94 July 1994 CHANGE NOTICE NO. 1 January 2000 CHANGE NOTICE NO. 2 April 2002 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS TS This document has been reproduced directly 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;

118

Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-3009-94 July 1994 CHANGE NOTICE NO. 12 January 2000 5 December 24 April 20021 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSISANALYSES REPORTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced directly 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;

119

Radionuclide Partitioning in an Underground Nuclear Test Cavity  

SciTech Connect

In 2004, a borehole was drilled into the 1983 Chancellor underground nuclear test cavity to investigate the distribution of radionuclides within the cavity. Sidewall core samples were collected from a range of depths within the re-entry hole and two sidetrack holes. Upon completion of drilling, casing was installed and a submersible pump was used to collect groundwater samples. Test debris and groundwater samples were analyzed for a variety of radionuclides including the fission products {sup 99}Tc, {sup 125}Sb, {sup 129}I, {sup 137}Cs, and {sup 155}Eu, the activation products {sup 60}Co, {sup 152}Eu, and {sup 154}Eu, and the actinides U, Pu, and Am. In addition, the physical and bulk chemical properties of the test debris were characterized using Scanning Electron Microscopy (SEM) and Electron Microprobe measurements. Analytical results were used to evaluate the partitioning of radionuclides between the melt glass, rubble, and groundwater phases in the Chancellor test cavity. Three comparative approaches were used to calculate partitioning values, though each method could not be applied to every nuclide. These approaches are based on: (1) the average Area 19 inventory from Bowen et al. (2001); (2) melt glass, rubble, and groundwater mass estimates from Zhao et al. (2008); and (3) fission product mass yield data from England and Rider (1994). The U and Pu analyses of the test debris are classified and partitioning estimates for these elements were calculated directly from the classified Miller et al. (2002) inventory for the Chancellor test. The partitioning results from this study were compared to partitioning data that were previously published by the IAEA (1998). Predictions of radionuclide distributions from the two studies are in agreement for a majority of the nuclides under consideration. Substantial differences were noted in the partitioning values for {sup 99}Tc, {sup 125}Sb, {sup 129}I, and uranium. These differences are attributable to two factors: chemical volatility effects that occur during the initial plasma condensation, and groundwater remobilization that occurs over a much longer time frame. Fission product partitioning is very sensitive to the early cooling history of the test cavity because the decay of short-lived (t{sub 1/2} < 1 hour) fission-chain precursors occurs on the same time scale as melt glass condensation. Fission product chains that include both volatile and refractory elements, like the mass 99, 125, and 129 chains, can show large variations in partitioning behavior depending on the cooling history of the cavity. Uranium exhibits similar behavior, though the chemical processes are poorly understood. The water temperature within the Chancellor cavity remains elevated (75 C) more than two decades after the test. Under hydrothermal conditions, high solubility chemical species such as {sup 125}Sb and {sup 129}I are readily dissolved and transported in solution. SEM analyses of melt glass samples show clear evidence of glass dissolution and secondary hydrothermal mineral deposition. Remobilization of {sup 99}Tc is also expected during hydrothermal activity, but moderately reducing conditions within the Chancellor cavity appear to limit the transport of {sup 99}Tc. It is recommended that the results from this study should be used together with the IAEA data to update the range in partitioning values for contaminant transport models at the Nevada National Security Site (formerly known as the Nevada Test Site).

Rose, T P; Hu, Q; Zhao, P; Conrado, C L; Dickerson, R; Eaton, G F; Kersting, A B; Moran, J E; Nimz, G; Powell, B A; Ramon, E C; Ryerson, F J; Williams, R W; Wooddy, P T; Zavarin, M

2009-01-09T23:59:59.000Z

120

Instrumented, Shielded Test Canister System for Evaluation of Spent Nuclear Fuel in Dry Storage  

SciTech Connect

This document describes the development of an instrumented, shielded test canister system to store and monitor aluminum-based spent nuclear duel under dry storage conditions.

Sindelar, R.L.

1999-10-21T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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

Mini-Proceedings ECT*: Speakable in quantum mechanics: atomic, nuclear and subnuclear physics tests  

E-Print Network (OSTI)

Mini-Proceedings ECT*: Speakable in quantum mechanics: atomic, nuclear and subnuclear physics tests, ECT*-Trento, 29 August - 2 September, 2011

Curceanu, C; Milotti, E

2011-01-01T23:59:59.000Z

122

Mini-Proceedings ECT*: Speakable in quantum mechanics: atomic, nuclear and subnuclear physics tests  

E-Print Network (OSTI)

Mini-Proceedings ECT*: Speakable in quantum mechanics: atomic, nuclear and subnuclear physics tests, ECT*-Trento, 29 August - 2 September, 2011

C. Curceanu; J. Marton; E. Milotti

2011-12-06T23:59:59.000Z

123

Modeling and analysis of a heat transport transient test facility for space nuclear systems.  

E-Print Network (OSTI)

??The purpose of this thesis is to design a robust test facility for a small space nuclear power system and model its physical behavior under… (more)

[No author

2013-01-01T23:59:59.000Z

124

Proceedings of the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear Test-Ban Treaty  

Science Conference Proceedings (OSTI)

These proceedings contain papers prepared for the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear-Test-Ban Treaty, held 21-24 September 1999 in Las Vegas, Nevada. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Technical Applications Center (AFTAC), Department of Defense (DoD), the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Warren, N. Jill [Editor

1999-09-21T23:59:59.000Z

125

Limited Test Ban Treaty Signed | National Nuclear Security Administrat...  

National Nuclear Security Administration (NNSA)

Timeline > Limited Test Ban Treaty Signed Limited Test Ban Treaty Signed August 05, 1963 Washington, DC Limited Test Ban Treaty Signed The United States, Great Britain, and the...

126

Investigation of CTBT OSI Radionuclide Techniques at the DILUTED WATERS Nuclear Test Site  

SciTech Connect

Under the Comprehensive Nuclear-Test-Ban Treaty (CTBT), a verification regime that includes the ability to conduct an On-Site Inspection (OSI) will be established. The Treaty allows for an OSI to include many techniques, including the radionuclide techniques of gamma radiation surveying and spectrometry and environmental sampling and analysis. Such radioactivity detection techniques can provide the “smoking gun” evidence that a nuclear test has occurred through the detection and quantification of indicative recent fission products. An OSI faces restrictions in time and manpower, as dictated by the Treaty; not to mention possible logistics difficulties due to the location and climate of the suspected explosion site. It is thus necessary to have a good understanding of the possible source term an OSI will encounter and the proper techniques that will be necessary for an effective OSI regime. One of the challenges during an OSI is to locate radioactive debris that has escaped an underground nuclear explosion (UNE) and settled on the surface near and downwind of ground zero. To support the understanding and selection of sampling and survey techniques for use in an OSI, we are currently designing an experiment, the Particulate Release Experiment (PRex), to simulate a small-scale vent from an underground nuclear explosion. PRex will occur at the Nevada National Security Site (NNSS). The project is conducted under the National Center for Nuclear Security (NCNS) funded by the National Nuclear Security Agency (NNSA). Prior to the release experiment, scheduled for Spring of 2013, the project scheduled a number of activities at the NNSS to prepare for the release experiment as well as to utilize the nuclear testing past of the NNSS for the development of OSI techniques for CTBT. One such activity—the focus of this report—was a survey and sampling campaign at the site of an old UNE that vented: DILUTED WATERS. Activities at DILUTED WATERS included vehicle-based survey, in situ measurements with high-purity germanium (HPGe) and hand-held LaBr3 systems, soil sampling with a variety of tools, and laboratory gamma spectrometric analysis of those samples. A further benefit of the measurement campaign was to gain familiarity with the many logistical aspects of performing radiological field work at NNSS ahead of the PRex. Many practical lessons concerning the proper methodologies and logistics of using the surveying and sampling equipment were noted. These Lessons Learned are compiled together in Appendix A. The vehicle-based survey was successful in that it found a previously unknown hotspot (determined to be 232Th) while it demonstrated that a better method for keeping a serpentine track without staking was needed. Some of the soil sampling equipment was found to be impractical for the application, though core sampling would not be the correct way to take soil samples for a fresh vent deposit (as opposed to an old site like DILUTED WATERS). Due to the site’s age, 137Cs was the only fission radioisotope identified, though others were searched for. While not enough samples were taken and analyzed to definitively link the 137Cs to DILUTED WATERS as opposed to other NNSS activities, results were consistent with the historical DILUTED WATERS plume. MDAs were compared for soil sampling and in situ measurements.

Baciak, James E.; Milbrath, Brian D.; Detwiler, Rebecca S.; Kirkham, Randy R.; Keillor, Martin E.; Lepel, Elwood A.; Seifert, Allen; Emer, Dudley; Floyd, Michael

2012-11-01T23:59:59.000Z

127

Advanced Nuclear Technology: 1E Battery 80% Service Test  

Science Conference Proceedings (OSTI)

The purpose of this test program was to verify that the proposed 80% service test could be used to deliver percent capacity results comparable with the current performance tests for capacity trending at various end voltages encountered in Class 1E applications. The general test methodology followed the service and performance test processes described in Section 7 of Institute of Electrical and Electronics Engineers Standard 450-2002. The test sequence is located in Section 1 of this report. The testing w...

2011-09-09T23:59:59.000Z

128

G-Tunnel pressurized slot-testing preparations; Yucca Mountain Site Characterization Project  

Science Conference Proceedings (OSTI)

Designers and analysts of radioactive waste repositories must be able to predict the mechanical behavior of the host rock. Sandia National laboratories elected to conduct a development program on pressurized slot testing and featured (1) development of an improved method to cut slots using a chain saw with diamond-tipped cutters, (2) measurements useful for determining in situ stresses normal to slots, (3) measurements applicable for determining the in situ modulus of deformation parallel to a drift surface, and (4) evaluations of the potentials of pressurized slot strength testing. This report describes the preparations leading to the measurements and evaluations.

Zimmerman, R.M.; Sifre-Soto, C. [Sandia National Labs., Albuquerque, NM (United States); Mann, K.L.; Bellman, R.A. Jr.; Luker, S. [Science Applications International Corp., Las Vegas, NV (United States); Dodds, D.J. [North Pacific Research, Portland, OR (United States)

1992-04-01T23:59:59.000Z

129

Senate Rejects Test Ban Treaty | National Nuclear Security Administrat...  

National Nuclear Security Administration (NNSA)

Timeline > Senate Rejects Test Ban Treaty Senate Rejects Test Ban Treaty October 13, 1999 Washington, DC Senate Rejects Test Ban Treaty The Senate votes 48-51 to reject the...

130

A perspective on atmospheric nuclear tests in Nevada: Fact Book, Revision 2  

SciTech Connect

This fact book provides historical background and perspective on the nuclear testing program at the Nevada Test Site (NTS). Nuclear tests contributing to the off-site deposition of radioactive fallout are identified, and the concept of cumulative estimated exposure is explained. The difficulty of associating health effects with radiation is presented also. The status of litigation against the government and legislation as of September 1994 are summarized.

Friesen, H.N.

1995-06-01T23:59:59.000Z

131

A study of residual Cesium 137 contamination in southwestern Utah soil following the nuclear weapons tests at the Nevada Test Site in the 1950's and 1960's.  

E-Print Network (OSTI)

??The Nevada Test Site (NTS) was the location for at least 100 above ground Nuclear Weapons tests during the 1950's and early 1960's. Radioactive fallout… (more)

[No author

2008-01-01T23:59:59.000Z

132

Preparations for deuterium--tritium experiments on the Tokamak Fusion Test Reactor*  

Science Conference Proceedings (OSTI)

The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. [bold 21], 1324 (1992)]. These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a Fluorinert[sup TM] system, modification of the vacuum system to handle tritium, preparation, and testing of the neutral beam system for tritium operation and a final deuterium--deuterium (D--D) run to simulate expected deuterium--tritium (D--T) operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power D--T experiments using D--D have been performed. The physics objectives of D--T operation are production of [approx]10 MW of fusion power, evaluation of confinement, and heating in deuterium--tritium plasmas, evaluation of [alpha]-particle heating of electrons, and collective effects driven by alpha particles and testing of diagnostics for confined [alpha] particles. Experimental results and theoretical modeling in support of the D--T experiments are reviewed.

Hawryluk, R.J.; Adler, H.; Alling, P.; Ancher, C.; Anderson, H.; Anderson, J.L.; Anderson, J.W.; Arunasalam, V.; Ascione, G.; Aschroft, D.; Barnes, C.W.; Barnes, G.; Batchelor, D.B.; Bateman, G.; Batha, S.; Baylor, L.A.; Beer, M.; Bell, M.G.; Biglow, T.S.; Bitter, M.; Blanchard, W.; Bonoli, P.; Bretz, N.L.; Brunkhorst, C.; Budny, R.; Burgess, T.; Bush, H.; Bush, C.E.; Camp, R.; Caorlin, M.; Carnevale, H.; Chang, Z.; Chen, L.; Cheng, C.Z.; Chrzanowski, J.; Collazo, I.; Collins, J.; Coward, G.; Cowley, S.; Cropper, M.; Darrow, D.S.; Daugert, R.; DeLooper, J.; Duong, H.; Dudek, L.; Durst, R.; Efthimion, P.C.; Ernst, D.; Faunce, J.; Fonck, R.J.; Fredd, E.; Fredrickson, E.; Fromm, N.; Fu, G.Y.; Furth, H.P.; Garzotto, V.; Gentile, C.; Gettelfinger, G.; Gilbert, J.; Gioia, J.; Goldfinger, R.C.; Golian, T.; Gorelenkov, N.; Gouge, M.J.; Grek, B.; Grisham, L.R.; Hammett, G.; Hanson, G.R.; Heidbrink, W.; Hermann, H.W.; Hill, K.W.; Hirshman, S.; Hoffman, D.J.; Hosea, J.; Hulse, R.A.; Hsuan, H.; Ja

1994-05-01T23:59:59.000Z

133

Preliminary Nuclear Calculations for the Shield Test Facility  

SciTech Connect

To find the critical size of the proposed shield test facility based upon available data and present construction concepts.

Baucom, H.H.

1960-01-11T23:59:59.000Z

134

FUNDAMENTALS IN THE OPERATION OF NUCLEAR TEST REACTORS. VOLUME 1. REACTOR SCIENCE AND TECHNOLOGY  

SciTech Connect

A resume of nuclear physics basic to reactor operation precedes discussion of aspects of reactor physics, engineering, chemistry, metallurgy, instrumentation, control, kinetics, and safety. The object is to provide an approach to and understanding of problems in irradiation test programs in the Materials Testing and Engineering Test Reactors. (D.C.W.)

1963-06-01T23:59:59.000Z

135

Nevada National Security Site Nuclear Testing Artifacts Become Part of U.S.  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nevada National Security Site Nuclear Testing Artifacts Become Part Nevada National Security Site Nuclear Testing Artifacts Become Part of U.S. Cultural Archive Nevada National Security Site Nuclear Testing Artifacts Become Part of U.S. Cultural Archive April 1, 2012 - 12:00pm Addthis Stanchions are among the remnants of Smoky Tower. Stanchions are among the remnants of Smoky Tower. LAS VEGAS, NV - The Nevada National Security Site's (NNSS) historic Smoky site may soon join a long list of former nuclear testing locations eligible for inclusion in the National Register of Historic Places. The Desert Research Institute (DRI) is currently working alongside the Nevada Site Office (NSO) to determine the eligibility of Smoky and a number of other EM sites slated for cleanup and closure. "In the last year, we've conducted assessments at over 30 EM sites,"

136

United States Nuclear Tests, July 1945 through September 1992, December 2000  

SciTech Connect

This document list chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Revision 15, dated December 2000.

U.S. Department of Energy, Nevada Operations Office

2000-12-01T23:59:59.000Z

137

Evaluated nuclear structure data file. a manual for preparation of data sets  

E-Print Network (OSTI)

This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A = 44, this information is published in the Nuclear Data Sheets; for A < 44, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chain or by nuclide with a varying cycle time dependent on the availability of new information.

Tuli, J K

2001-01-01T23:59:59.000Z

138

ENVIRONMENTAL IlONITORING REPORT FOR THE NEVADA TEST SITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS  

Office of Legacy Management (LM)

IlONITORING REPORT FOR THE NEVADA TEST SITE IlONITORING REPORT FOR THE NEVADA TEST SITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS January through December 1975 Nonitoring Operations Division Environmental Monitoring and Support Laboratory U.S. ENVIRONMENTAL PROTECTION AGENCY Las Vegas, Nevada 89114 APRIL 1976 This work performed under a Memorandum of Understanding No. AT(26-1)-539 for the U . S . ENERGY RESEARCH & DEVELOPMENT ADMINISTRATION EMSL-LV-5 39-4 May 1976 ENVIRONMENTAL 14ONITORING REPORT FOR THE NEVADA TEST SITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS January through December I975 Monitoring Operations Division Environmental Monitoring and Support Laboratory U.S. ENVIRONMENTAL PROTECTION AGENCY Las Vegas, Nevada 89114 APRIL 1976 This work performed under a Memorandum of

139

Spent Fuel Drying System Test Results (Dry-Run in Preparation for Run 8)  

Science Conference Proceedings (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL)(a)on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of a test ''dry-run'' conducted prior to the eighth and last of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister6513U. The system used for the dry-run test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. The experimental results are provided in Section 4.0 and discussed Section 5.0.

BM Oliver; GS Klinger; J Abrefah; SC Marschman; PJ MacFarlan; GA Ritter

1999-08-11T23:59:59.000Z

140

Evaluation of the radionuclide tracer test conducted at the project Gnome Underground Nuclear Test Site, New Mexico  

SciTech Connect

A radionuclide tracer test was conducted in 1963 by the U.S. Geological Survey at the Project Gnome underground nuclear test site, approximately 40 km southeast of Carlsbad, New Mexico. The tracer study was carried out under the auspices of the U.S. Atomic Energy Commission (AEC) to study the transport behavior of radionuclides in fractured rock aquifers. The Culebra Dolomite was chosen for the test because it was considered to be a reasonable analogue of the fractured carbonate aquifer at the Nevada Test Site (NTS), the principal location of U.S. underground nuclear tests. Project Gnome was one of a small number of underground nuclear tests conducted by the AEC at sites distant from the NTS. The Gnome device was detonated on December 10, 1961 in an evaporate unit at a depth of 360 m below ground surface. Recently, the U.S. Department of Energy (DOE) implemented an environmental restoration program to characterize, remediate, and close these offsite nuclear test areas. An early step in this process is performance of a preliminary risk analysis of the hazard posed by each site. The Desert Research Institute has performed preliminary hydrologic risk evaluations for the groundwater transport pathway at Gnome. That evaluation included the radioactive tracer test as a possible source because the test introduced radionuclides directly into the Culebra Dolomite, which is the only aquifer at the site. This report presents a preliminary evaluation of the radionuclide tracer test as a source for radionuclide migration in the Culebra Dolomite. The results of this study will assist in planning site characterization activities and refining estimates of the radionuclide source for comprehensive models of groundwater transport st the Gnome site.

Pohll, G.; Pohlmann, K.

1996-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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

Hanford spent nuclear fuel cold vacuum drying test specification and test plan  

SciTech Connect

This document provides the test plan and test specification for SNF cold vacuum drying proof of concept, CVD process equipment validation, and proof of performance testing.

McCracken, K.J., Westinghouse Hanford

1996-07-10T23:59:59.000Z

142

Fuel subassembly leak test chamber for a nuclear reactor  

DOE Patents (OSTI)

A container with a valve at one end is inserted into a nuclear reactor coolant pool. Once in the pool, the valve is opened by a mechanical linkage. An individual fuel subassembly is lifted into the container by a gripper; the valve is then closed providing an isolated chamber for the subassembly. A vacuum is drawn on the chamber to encourage gaseous fission product leakage through any defects in the cladding of the fuel rods comprising the subassembly; this leakage may be detected by instrumentation, and the need for replacement of the assembly ascertained.

Divona, Charles J. (Santa Ana, CA)

1978-04-04T23:59:59.000Z

143

Spent nuclear fuel storage -- Performance tests and demonstrations  

SciTech Connect

This report summarizes the results of heat transfer and shielding performance tests and demonstrations conducted from 1983 through 1992 by or in cooperation with the US Department of Energy (DOE), Office of Commercial Radioactive Waste Management (OCRWM). The performance tests consisted of 6 to 14 runs involving one or two loadings, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. A description of the test plan, spent fuel load patterns, results from temperature and dose rate measurements, and fuel integrity evaluations are contained within the report.

McKinnon, M.A.; DeLoach, V.A.

1993-04-01T23:59:59.000Z

144

Nuclear Nonproliferation and Arms Control Primer Prepared for the Blue Ribbon Commission on America’s Nuclear Future  

Science Conference Proceedings (OSTI)

To provide a brief overview of key arms control and nonproliferation arrangements for the layperson that may be relevant to the Commission's comprehensive review of policies for managing the back end of the nuclear fuel cycle. Primer would be published by the Commission and made publicly available, probably as an appendix to a larger Commission report.

Williams, Laura S.

2011-05-25T23:59:59.000Z

145

EVALUATION OF ARG-1 SAMPLES PREPARED BY CESIUM CARBONATE DISSOLUTION DURING THE ISOLOK SME ACCEPTABILITY TESTING  

Science Conference Proceedings (OSTI)

Evaluation of Defense Waste Processing Facility (DWPF) Chemical Process Cell (CPC) cycle time identified several opportunities to improve the CPC processing time. The Mechanical Systems & Custom Equipment Development (MS&CED) Section of the Savannah River National Laboratory (SRNL) recently completed the evaluation of one of these opportunities - the possibility of using an Isolok sampling valve as an alternative to the Hydragard valve for taking DWPF process samples at the Slurry Mix Evaporator (SME). The use of an Isolok for SME sampling has the potential to improve operability, reduce maintenance time, and decrease CPC cycle time. The SME acceptability testing for the Isolok was requested in Task Technical Request (TTR) HLW-DWPF-TTR-2010-0036 and was conducted as outlined in Task Technical and Quality Assurance Plan (TTQAP) SRNLRP-2011-00145. RW-0333P QA requirements applied to the task, and the results from the investigation were documented in SRNL-STI-2011-00693. Measurement of the chemical composition of study samples was a critical component of the SME acceptability testing of the Isolok. A sampling and analytical plan supported the investigation with the analytical plan directing that the study samples be prepared by a cesium carbonate (Cs{sub 2}CO{sub 3}) fusion dissolution method and analyzed by Inductively Coupled Plasma - Optical Emission Spectroscopy (ICP-OES). The use of the cesium carbonate preparation method for the Isolok testing provided an opportunity for an additional assessment of this dissolution method, which is being investigated as a potential replacement for the two methods (i.e., sodium peroxide fusion and mixed acid dissolution) that have been used at the DWPF for the analysis of SME samples. Earlier testing of the Cs{sub 2}CO{sub 3} method yielded promising results which led to a TTR from Savannah River Remediation, LLC (SRR) to SRNL for additional support and an associated TTQAP to direct the SRNL efforts. A technical report resulting from this work was issued that recommended that the mixed acid method be replaced by the Cs{sub 2}CO{sub 3} method for the measurement of magnesium (Mg), sodium (Na), and zirconium (Zr) with additional testing of the method by DWPF Laboratory being needed before further implementation of the Cs{sub 2}CO{sub 3} method at that laboratory. While the SME acceptability testing of the Isolok does not address any of the open issues remaining after the publication of the recommendation for the replacement of the mixed acid method by the Cs{sub 2}CO{sub 3} method (since those issues are to be addressed by the DWPF Laboratory), the Cs{sub 2}CO{sub 3} testing associated with the Isolok testing does provide additional insight into the performance of the method as conducted by SRNL. The performance is to be investigated by looking to the composition measurement data generated by the samples of a standard glass, the Analytical Reference Glass - 1 (ARG-1), that were prepared by the Cs{sub 2}CO{sub 3} method and included in the SME acceptability testing of the Isolok. The measurements of these samples were presented as part of the study results, but no statistical analysis of these measurements was conducted as part of those results. It is the purpose of this report to provide that analysis, which was supported using JMP Version 7.0.2.

Edwards, T.; Hera, K.; Coleman, C.

2011-12-05T23:59:59.000Z

146

Biological effects of underground nuclear testing on marine organisms. II. Observed effects of Amchitka Island, Alaska, tests on marine fauna  

SciTech Connect

>From conference on the environmental effects of explosives and explosions; White Oak, Maryland, USA (30 May 1973). The biological effects of the Longshot, Milrow, and Cannikin underground nuclear tests at Amchitka lsland, Alaska, on marine mammals, fishes, and birds are summarized. The biological effects observed were related to the water-borne shock waves produced by the explosions. (CH)

Isakson, J.S.

1973-01-01T23:59:59.000Z

147

GEOPHYSICAL RESEARCH LETTERS, VOL. 27, NO. 15, PAGES 22452248, AUGUST 1, 2000 Subsurface nuclear tests monitoring through the  

E-Print Network (OSTI)

nuclear tests down to 1 kiloton (kt) TNT equivalent anywhere on the planet. The IMS is based upon four waves will help check for underground, under­water and atmospheric nuclear tests. The fourth networkGEOPHYSICAL RESEARCH LETTERS, VOL. 27, NO. 15, PAGES 2245­2248, AUGUST 1, 2000 Sub­surface nuclear

Hourdin, Chez Frédéric

148

Preparation and Testing of the SRF Cavities for the CEBAF 12 GeV Upgrade  

SciTech Connect

Eighty new 7-cell, low-loss cell-shaped cavities are required for the CEBAF 12 GeV Upgrade project. In addition to ten pre-production units fabricated at JLab, the full set of commercially-produced cavities have been delivered. An efficient processing routine, which includes a controlled 30 micron electropolish, has been established to transform these cavities into qualified 8-cavity strings. This work began in 2010 and will run through the end of 2011. The realized cavity performance consistently exceeds project requirements and also the maximum useful gradient in CEBAF: 25 MV/m. We will describe the cavity processing and preparation protocols and summarize test results obtained to date.

Reilly, A. V.; Bass, T.; Burrill, A.; Davis, G. K.; Marhauser, F.; Reece, C. E.; Stirbet, M.

2011-07-01T23:59:59.000Z

149

(beta beta)_{0 nu}-decay: a possible test of the nuclear matrix element calculations  

E-Print Network (OSTI)

The existing calculations of the nuclear matrix elements of the neutrinoless double beta-decay differ by about a factor three. This uncertainty prevents quantative interpretation of the results of experiments searching for this process. We suggest here that the observation of the neutrinoless double beta-decay of several nuclei in future experiments of could allow to test different calculations of the nuclear matrix elements through the direct comparison of them with the experimental data.

S. M. Bilenky; J. A. Grifols

2002-07-23T23:59:59.000Z

150

Z Production as a Test of Nuclear Effects at the LHC  

E-Print Network (OSTI)

We predict the Z transverse momentum distribution from proton-proton and nuclear collisions at the LHC. After demonstrating that higher-twist nuclear effects are very small, we propose $Z^0$ production as a precision test for leading-twist pQCD in the TeV energy region. We also point out that shadowing may result in unexpected phenomenology at the LHC.

Xiaofei Zhang; George Fai

2002-05-15T23:59:59.000Z

151

Integral Benchmark Data for Nuclear Data Testing Through the ICSBEP & IRPhEP  

Science Conference Proceedings (OSTI)

The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiment Evaluation Project (IRPhEP) was last discussed directly with the nuclear data community at ND2007. Since ND2007, integral benchmark data that are available for nuclear data testing have increased significantly. The status of the ICSBEP and the IRPhEP is discussed and selected benchmark configurations that have been added to the ICSBEP and IRPhEP Handbooks since ND2007 are highlighted.

J. Blair Briggs; John D. Bess; Jim Gulliford; Ian Hill

2013-10-01T23:59:59.000Z

152

Evaluated nuclear structure data file. A manual for preparation of data sets  

Science Conference Proceedings (OSTI)

This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A less than or equal to 263), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses A greater than or equal to 45, this information is documented in the Nuclear Data Sheets; for A < 45, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chains with a present cycle time of approximately six years. The body of a data set is composed of numeric data records which describe the measured or deduced properties of levels, ..gamma.. rays, ..cap alpha.. particles, etc. These records are associated with the level which decays (for gamma records) or the level which is populated (for beta, ec, or alpha records). Thus, each level record is followed by a group of records describing charged-particle decay into the level and ..gamma..-ray decay out of the level. (WHK)

Tuli, J.K.

1983-03-01T23:59:59.000Z

153

HEATER TEST PLANNING FOR THE NEAR SURFACE TEST FACILITY AT THE HANFORD RESERVATION  

E-Print Network (OSTI)

Heater Experiment at Hanford. Berkeley, Lawre ;e BerkeleyTest Facility, Hole DC-11, Hanford Reservation. Prepared forof Gable Mountain Basalt Cores, Hanford Nuclear Reservation.

DuBois, A.

2010-01-01T23:59:59.000Z

154

Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

When assessing cable degradation or failure assessment, using the correct test and assessment methodology is critical to obtaining the correct answer. Many in-plant and laboratory tests exist. Some apply to the cable types used in nuclear plants. Some apply only to distribution cables. Most have pertinence to only one issue or even one cable design. This report provides a correlation between specific cable problems and the appropriate tests that may be used to resolve the issue. The report starts with su...

2011-12-23T23:59:59.000Z

155

DOE-STD-1082-94; DOE Standard Preparation, Review, and Approval of Implementaiton Plans For Nuclear Safety Requirements  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

82-94 82-94 October 1994 DOE STANDARD PREPARATION, REVIEW, AND APPROVAL OF IMPLEMENTATION PLANS FOR NUCLEAR SAFETY REQUIREMENTS U.S. Department of Energy AREA SAFT 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. DE95001461 DOE-STD-1082-94 iii FOREWORD 1. This Department of Energy (DOE) technical standard has been prepared by the Office of Environment, Safety and Health with the assistance of Steve

156

Laboratory's role in Cold War nuclear weapons testing program focus of  

NLE Websites -- All DOE Office Websites (Extended Search)

70th anniversary lecture 70th anniversary lecture Laboratory's role in Cold War nuclear weapons testing program focus of next 70th anniversary lecture Lab's role in the development of nuclear weapons during the Cold War period will be discussed by Byron Ristvet of the Defense Threat Reduction Agency. September 5, 2013 This photograph captures the expanding fireball of the world's first full-scale hydrogen bomb test, Ivy-Mike, which was conducted Oct. 31, 1952. This photograph captures the expanding fireball of the world's first full-scale hydrogen bomb test, Ivy-Mike, which was conducted Oct. 31, 1952. Contact Steve Sandoval Communications Office (505) 665-9206 Email "Los Alamos National Laboratory's role in conjunction with the Department of Defense in meeting this challenge with new nuclear weapon

157

DOE/EA-1499; Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site Final Environmental Assessment  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

499 499 Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site Final Environmental Assessment August 2004 U. S. Department of Energy National Nuclear Security Administration Nevada Site Office Las Vegas, Nevada Available for sale to the Public, in paper, from: U.S. Department of Commerce National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Phone: 800.553.6847 Fax: 703.605.6900 Email: orders@ntis..gov Online Ordering: http://www.ntis.gov/ordering.htm Available electronically at: http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors in paper from-- U.S. Department of Energy Office of Scientific and Technical Information

158

Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities  

E-Print Network (OSTI)

1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

159

Fehner and Gosling, Atmospheric Nuclear Weapons Testing, 1951-1963. Battlefield of the Cold War: The Nevada Test Site, Volume I  

Energy.gov (U.S. Department of Energy (DOE))

Terrence R. Fehner and F.G. Gosling. Atmospheric Nuclear Weapons Testing, 1951-1963. Battlefield of the Cold War: The Nevada Test Site, Volume I (pdf). DOE/MA-0003. Washington, D.C.: Department of...

160

Comparative tests of isospin-symmetry-breaking corrections to superallowed 0+-to-0+ nuclear beta decay  

E-Print Network (OSTI)

We present a test with which to evaluate the calculated isospin-symmetry-breaking corrections to superallowed 0+-to-0+ nuclear beta decay. The test is based on the corrected experimental Ft values being required to satisfy conservation of the vector current (CVC). When applied to six sets of published calculations, the test demonstrates quantitatively that only one set -- the one based on the shell model with Saxon-Woods radial wave functions -- provides satisfactory agreement with CVC. This test can easily be applied to any sets of calculated correction terms that are produced in future.

Towner, I S

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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
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161

Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1982  

Science Conference Proceedings (OSTI)

A principal activity of the Offsite Radiological Safety Program is routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests. It is conducted to document compliance with standards, to identify trends, and to provide information to the public. This report summarizes these activities for CY 1982.

Black, S. C.; Grossman, R. F.; Mullen, A. A.; Potter, G. D.; Smith, D. D. [comps.

1983-07-01T23:59:59.000Z

162

Direct Test of the Time-Independence of Fundamental Nuclear Constants Using the Oklo  

E-Print Network (OSTI)

Direct Test of the Time-Independence of Fundamental Nuclear Constants Using the Oklo Natural Reactor #3; Alexander I. Shlyakhter November 18, 1982 1 Introduction The following eight quantities enter the important natural constants of cosmology and atomic theory are connected by simple mathematical relations

Shlyakhter, Ilya

163

Ground Testing a Nuclear Thermal Rocket: Design of a sub-scale demonstration experiment  

SciTech Connect

In 2008, the NASA Mars Architecture Team found that the Nuclear Thermal Rocket (NTR) was the preferred propulsion system out of all the combinations of chemical propulsion, solar electric, nuclear electric, aerobrake, and NTR studied. Recently, the National Research Council committee reviewing the NASA Technology Roadmaps recommended the NTR as one of the top 16 technologies that should be pursued by NASA. One of the main issues with developing a NTR for future missions is the ability to economically test the full system on the ground. In the late 1990s, the Sub-surface Active Filtering of Exhaust (SAFE) concept was first proposed by Howe as a method to test NTRs at full power and full duration. The concept relied on firing the NTR into one of the test holes at the Nevada Test Site which had been constructed to test nuclear weapons. In 2011, the cost of testing a NTR and the cost of performing a proof of concept experiment were evaluated.

David Bedsun; Debra Lee; Margaret Townsend; Clay A. Cooper; Jennifer Chapman; Ronald Samborsky; Mel Bulman; Daniel Brasuell; Stanley K. Borowski

2012-07-01T23:59:59.000Z

164

Tests of Micro-Pattern Gaseous Detectors for Active1 Target Time Projection Chambers in nuclear physics2  

E-Print Network (OSTI)

Tests of Micro-Pattern Gaseous Detectors for Active1 Target Time Projection Chambers in nuclear the gas used as the detection medium10 is also a target for nuclear reactions, have been used for a wide variety of11 nuclear physics applications since the eighties. Improvements in MPGD (Mi-12 cro Pattern

Recanati, Catherine

165

Reversible Bending Fatigue Test System for Investigating Vibration Integrity of Spent Nuclear Fuel during Transportation  

SciTech Connect

Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading during road or rail shipment. Oak Ridge National Laboratory (ORNL) has been developing testing capabilities that can be used to improve the understanding of the impacts on SNF integrity due to vibration loading, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet the nuclear industry and U.S. Nuclear Regulatory Commission needs in the area of safety and security of spent nuclear fuel storage and transport operations. The ORNL developed test system can perform reversible-bending fatigue testing to evaluate both the static and dynamic mechanical response of SNF rods under simulated loads. The testing apparatus is also designed to meet the challenges of hot-cell operation, including remote installation and detachment of the SNF test specimen, in-situ test specimen deformation measurement, and implementation of a driving system suitable for use in a hot cell. The system contains a U-frame set-up equipped with uniquely designed grip rigs, to protect SNF rod and to ensure valid test results, and use of 3 specially designed LVDTs to obtain the in-situ curvature measurement. A variety of surrogate test rods have been used to develop and calibrate the test system as well as in performing a series of systematic cyclic fatigue tests. The surrogate rods include stainless steel (SS) cladding, SS cladding with cast epoxy, and SS cladding with alumina pellets inserts simulating fuel pellets. Testing to date has shown that the interface bonding between the SS cladding and the alumina pellets has a significant impact on the bending response of the test rods as well as their fatigue strength. The failure behaviors observed from tested surrogate rods provides a fundamental understanding of the underlying failure mechanisms of the SNF surrogate rod under vibration which has not been achieved previously. The newly developed device is scheduled to be installed in the hot-cell in summer 2013 to test high burnup SNF.

Wang, Jy-An John [ORNL; Wang, Hong [ORNL; Bevard, Bruce Balkcom [ORNL; Howard, Rob L [ORNL; Flanagan, Michelle [U.S. Nuclear Regulatory Commission

2013-01-01T23:59:59.000Z

166

Assessment of hydrologic transport of radionuclides from the Gnome underground nuclear test site, New Mexico  

SciTech Connect

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary site risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gnome site in southeastern New Mexico was the location of an underground detonation of a 3.5-kiloton nuclear device in 1961, and a hydrologic tracer test using radionuclides in 1963. The tracer test involved the injection of tritium, {sup 90}Sr, and {sup 137}Cs directly into the Culebra Dolomite, a nine to ten-meter-thick aquifer located approximately 150 in below land surface. The Gnome nuclear test was carried out in the Salado Formation, a thick salt deposit located 200 in below the Culebra. Because salt behaves plastically, the cavity created by the explosion is expected to close, and although there is no evidence that migration has actually occurred, it is assumed that radionuclides from the cavity are released into the overlying Culebra Dolomite during this closure process. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides may be present in concentrations exceeding drinking water regulations outside the drilling exclusion boundary established by DOE. Calculated mean tritium concentrations peak at values exceeding the U.S. Environmental Protection Agency drinking water standard of 20,000 pCi/L at distances of up to almost eight kilometers west of the nuclear test.

Earman, S.; Chapman, J.; Pohlmann, K.; Andricevic, R.

1996-09-01T23:59:59.000Z

167

Development of a test system for verification and validation of nuclear transport simulations  

SciTech Connect

Verification and validation of nuclear data is critical to the accuracy of both stochastic and deterministic particle transport codes. In order to effectively test a set of nuclear data, the data must be applied to a wide variety of transport problems. Performing this task in a timely, efficient manner is tedious. The nuclear data team at Los Alamos National laboratory in collaboration with the University of Florida has developed a methodology to automate the process of nuclear data verification and validation (V and V). This automated V and V process can efficiently test a number of data libraries using well defined benchmark experiments, such as those in the International Criticality Safety Benchmark Experiment Project (ICSBEP). The process is implemented through an integrated set of Pyton scripts. Material and geometry data are read from an existing medium or given directly by the user to generate a benchmark experiment template file. The user specifies the choice of benchmark templates, codes, and libraries to form a V and V project. The Python scripts generate input decks for multiple transport codes from the templates, run and monitor individual jobs, and parse the relevant output automatically. The output can then be used to generate reports directly or can be stored into a database for later analysis. This methodology eases the burden on the user by reducing the amount of time and effort required for obtaining and compiling calculation results. The resource savings by using this automated methodology could potentially be an enabling technology for more sophisticated data studies, such as nuclear data uncertainty quantification. Once deployed, this tool will allow the nuclear data community to more thoroughly test data libraries leading to higher fidelity data in the future.

White, Morgan C [Los Alamos National Laboratory; Triplett, Brian S [GENERAL ELECTRIC; Anghaie, Samim [UNIV OF FL

2008-01-01T23:59:59.000Z

168

Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall  

SciTech Connect

Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

Michael Kruzic

2007-09-01T23:59:59.000Z

169

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents (OSTI)

Circuitry for testing the ability of an intermediate range nuclear instrut to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on.

Brown, Roger A. (Amsterdam, NY)

1994-01-01T23:59:59.000Z

170

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents (OSTI)

Circuitry is described for testing the ability of an intermediate range nuclear instrument to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on. 1 figures.

Brown, R.A.

1994-04-19T23:59:59.000Z

171

The possible test of the calculations of nuclear matrix elements of the $(??)_{0?}$-decay  

E-Print Network (OSTI)

The existing calculations of the nuclear matrix elements of the neutrinoless double $\\beta$-decay differ by about a factor three. This uncertainty prevents quantitative interpretation of the results of experiments searching for this process. We suggest here that the observation of the neutrinoless double $\\beta$-decay of {\\em several} nuclei could allow to test calculations of the nuclear matrix elements through the comparison of the ratios of the calculated lifetimes with experimental data. It is shown that the ratio of the lifetimes is very sensitive to different models.

S. M. Bilenky; J. A. Grifols

2002-11-07T23:59:59.000Z

172

PREPARATION OF UO$sub 2$ FOR NUCLEAR REACTOR FUEL PELLETS  

DOE Patents (OSTI)

A method is given for preparing high-density UO/sub 2/ compacts. An aqueous uranyl fluoride solution is contacted with an aqueous ammonium hydroxide solution at an ammonium to-uranium ratio of 25: 1 to 30:1 to form a precipitate. The precipitate is separated from the- mother liquor, dried, and contacted with steam at a uniform temperature within the range of 400 to 650 deg C to produce U/ sub 3/O/sub 8/. The U/sub 3/O/sub 8/ is red uced to UO/sub 2/ with hydrogen at a uniform temperature within the range of 550 to 600 deg C. The UO/sub 2/ is then compressed into compacts and sintered. High-density compacts are fabricated to close tolerances without use of a binder and without machining or grinding. (AEC)

Googin, J.M.

1962-06-01T23:59:59.000Z

173

Assessment of hydrologic transport of radionuclides from the Rulison Underground Nuclear Test Site, Colorado  

SciTech Connect

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Rulison site in west-central Colorado was the location of an underground detonation of a 40-kiloton nuclear device in 1969. The test took place 2,568 m below ground surface in the Mesaverde Formation. Though located below the regional water table, none of the bedrock formations at the site yielded water during hydraulic tests, indicating extremely low permeability conditions. The scenario evaluated was the migration of radionuclides from the blast-created cavity through the Mesaverde Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity and the correlation scale of hydraulic conductivity, with transport of strontium and cesium also sensitive to the sorption coefficient.

Earman, S.; Chapman, J.; Andricevic, R.

1996-09-01T23:59:59.000Z

174

Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2010, Prepared for the Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 2012  

SciTech Connect

This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission’s (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 2010 annual reports submitted by five of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Because there are no geologic repositories for high-level waste currently licensed and no NRC-licensed low-level waste disposal facilities currently in operation, only five categories will be considered in this report. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in this report in terms of collective dose and the distribution of dose among the monitored individuals. Annual reports for 2010 were received from a total of 190 NRC licensees. The summation of reports submitted by the 190 licensees indicated that 192,424 individuals were monitored, 81,961 of whom received a measurable dose. When adjusted for transient workers who worked at more than one licensee during the year, there were actually 142,471 monitored individuals and 62,782 who received a measurable dose. The collective dose incurred by these individuals was 10,617 person-rem, which represents a 12% decrease from the 2009 value. This decrease was primarily due to the decrease in collective dose at commercial nuclear power reactors, as well as a decrease in the collective dose for most of the other categories of NRC licensees. The number of individuals receiving a measurable dose also decreased, resulting in an average measurable dose of 0.13 rem for 2010. The average measurable dose is defined as the total effective dose equivalent (TEDE) divided by the number of individuals receiving a measurable dose. In calendar year 2010, the average annual collective dose per reactor for light water reactor (LWR) licensees was 83 person-rem. This represents a 14% decrease from the value reported for 2009 (96 person-rem). The decrease in collective dose for commercial nuclear power reactors was due to an 11% decrease in total outage hours in 2010. During outages, activities involving increased radiation exposure such as refueling and maintenance are performed while the reactor is not in operation. The average annual collective dose per reactor for boiling water reactors (BWRs) was 137 personrem for 35 BWRs, and 55 person-rem for 69 pressurized water reactors (PWRs). Analyses of transient individual data indicate that 29,333 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient individuals by multiple licensees. The adjustment to account for transient individuals has been specifically noted in footnotes in the figures and tables for commercial nuclear power reactors. In 2010, the average measurable dose per individual for all licensees calculated from reported data was 0.13 rem. Although the average measurable dose per individual from data submitted by licensees was 0.13 rem, a corrected dose distribution resulted in an average measurable dose per individual of 0.17 rem.

D. E. Lewis D. A. Hagemeyer Y. U. McCormick

2012-07-07T23:59:59.000Z

175

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report  

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

176

The significance of using the Newcomb-Benford law as a test of nuclear half-life calculations  

E-Print Network (OSTI)

Half-life number sequences collected from nuclear data charts are found to obey the Newcomb-Benford law. Based on this fact, it has been suggested recently, that this law should be used to test the quality of nuclear decay models. In this paper we briefly recall how, when and why the Newcomb-Benford law can be observed in a set of numbers with a given probability distribution. We investigate the special case of nuclear half-lives, and show that the law provides no additional clue in understanding decay half-lives. Thus, it can play no significant role in testing nuclear decay theories.

Farkas, Janos

2010-01-01T23:59:59.000Z

177

The significance of using the Newcomb-Benford law as a test of nuclear half-life calculations  

E-Print Network (OSTI)

Half-life number sequences collected from nuclear data charts are found to obey the Newcomb-Benford law. Based on this fact, it has been suggested recently, that this law should be used to test the quality of nuclear decay models. In this paper we briefly recall how, when and why the Newcomb-Benford law can be observed in a set of numbers with a given probability distribution. We investigate the special case of nuclear half-lives, and show that the law provides no additional clue in understanding decay half-lives. Thus, it can play no significant role in testing nuclear decay theories.

Janos Farkas; Gyorgy Gyurky

2010-06-18T23:59:59.000Z

178

Fabrication and Integrity Testing of a Korean ITER TBM FW Mock-Up in Preparation for High Heat Flux Test  

Science Conference Proceedings (OSTI)

Test Blanket, Fuel Cycle, and Breeding / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012

Jae Sung Yoon; Suk Kwon Kim; Eo Hwak Lee; Seungyon Cho; Dong Won Lee

179

Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test  

SciTech Connect

The purpose of this work is to characterize groundwater flow and contaminant transport at the Shoal underground nuclear test through numerical modeling using site-specific hydrologic data. The ultimate objective is the development of a contaminant boundary, a model-predicted perimeter defining the extent of radionuclide-contaminated groundwater from the underground test throughout 1,000 years at a prescribed level of confidence. This boundary will be developed using the numerical models described here, after they are approved for that purpose by DOE and NDEP.

K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

2004-03-01T23:59:59.000Z

180

DOE Order Self Study Modules - DOE-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facilities Documented Safety Analyses  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3009-94 3009-94 PREPARATION GUIDE FOR U.S. DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES DOE-STD-3009-94 Familiar Level June 2011 1 DOE-STD-3009-94 PREPARATION GUIDE FOR U.S. DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES FAMILIAR LEVEL _______________________________________________________________________________ OBJECTIVES Given the familiar level of this module and the resources listed below, you will be able to answer the following questions: 1. What are five general requirements for contractors who are responsible for a hazard category 1, 2, or 3 nuclear facility, as related to establishing a safety basis? 2. What actions must a contractor take when it is made aware of a potential inadequacy of

Note: This page contains sample records for the topic "nuclear test prepared" 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

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plant Projects: Industry Recommendations for Storage, Construction, and Testing  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries and vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

182

Nuclear Data Performance Testing Using Sensitive, but Less Frequently Used ICSBEP Benchmarks  

Science Conference Proceedings (OSTI)

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) has published the International Handbook of Evaluated Criticality Safety Benchmark Experiments annually since 1995. The Handbook now spans over 51,000 pages with benchmark specifications for 4,283 critical, near critical, or subcritical configurations; 24 criticality alarm placement/shielding configurations with multiple dose points for each; and 200 configurations that have been categorized as fundamental physics measurements relevant to criticality safety applications. Benchmark data in the ICSBEP Handbook were originally intended for validation of criticality safety methods and data; however, the benchmark specifications are now used extensively for nuclear data testing. There are several, less frequently used benchmarks within the Handbook that are very sensitive to thorium and certain key structural and moderating materials. Calculated results for many of those benchmarks using modern nuclear data libraries suggest there is still room for improvement. These and other highly sensitive, but rarely quoted benchmarks are highlighted and data testing results provided using the Monte Carlo N-Particle Version 5 (MCNP5) code and continuous energy ENDF/B-V, VI.8, and VII.0, JEFF-3.1, and JENDL-3.3 nuclear data libraries.

J. Blair Briggs; John D. Bess

2011-08-01T23:59:59.000Z

183

CALMOS: Innovative device for the measurement of nuclear heating in material testing reactors  

Science Conference Proceedings (OSTI)

An R and D program has been carried out since 2002 in order to improve gamma heating measurements in the 70 MWth OSIRIS Material Testing Reactor operated by CEA's Nuclear Energy Div. at the Saclay research center. Throughout this program an innovative calorimetric probe associated to a specific handling system has been designed in order to make measurements both along the fissile height and on the upper part of the core, where nuclear heating rates still remain high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for the process validation, while a displacement system has been especially designed to move the probe axially. A final probe has been designed thanks to modeling results and to preliminary measurements obtained with mock-ups irradiated to a heating level of 2W/g, This paper gives an overview of the development, describes the calorimetric probe, and expected advantages such as the possibility to use complementary methods to get the nuclear heating measurement. Results obtained with mock-ups irradiated in ex-core area of the reactor are presented and discussed. (authors)

Carcreff, H. [Alternative Energies and Atomic Energy Commission CEA, Saclay Center, DEN/DANS/DRSN/SIREN, Gif Sur Yvette, 91191 (France)

2011-07-01T23:59:59.000Z

184

Uranium Enrichment Standards of the Y-12 Nuclear Detection and Sensor Testing Center  

SciTech Connect

The Y-12 National Security Complex has recently fabricated and characterized a new series of metallic uranium standards for use in the Nuclear Detection and Sensor Testing Center (NDSTC). Ten uranium metal disks with enrichments varying from 0.2 to 93.2% {sup 235}U were designed to provide researchers access to a wide variety of measurement scenarios in a single testing venue. Special care was taken in the selection of the enrichments in order to closely bracket the definitions of reactor fuel at 4% {sup 235}U and that of highly enriched uranium (HEU) at 20% {sup 235}U. Each standard is well characterized using analytical chemistry as well as a series of gamma-ray spectrometry measurements. Gamma-ray spectra of these standards are being archived in a reference library for use by customers of the NDSTC. A software database tool has been created that allows for easier access and comparison of various spectra. Information provided through the database includes: raw count data (including background spectra), regions of interest (ROIs), and full width half maximum calculations. Input is being sought from the user community on future needs including enhancements to the spectral database and additional Uranium standards, shielding configurations and detector types. A related presentation are planned for the INMM 53rd Annual Meeting (Hull, et al.), which describe new uranium chemical compound standards and testing opportunities at Y-12 Nuclear Detection and Sensor Testing Center (NDSTC).

Cantrell, J.

2012-05-23T23:59:59.000Z

185

Operation Cornerstone onsite radiological safety report for announced nuclear tests, October 1988--September 1989  

SciTech Connect

Cornerstone was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site (NTS) from October 1, 1988, through September 30, 1989. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Radiation Protection Technicians (RPT) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage were provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined.

Not Available

1990-08-01T23:59:59.000Z

186

Development and Testing of a Groundwater Management Model for the Faultless Underground Nuclear Test, Central Nevada Test Area  

DOE Green Energy (OSTI)

This document describes the development and application of a user-friendly and efficient groundwater management model of the Central Nevada Test Area (CNTA) and surrounding areas that will allow the U.S. Department of Energy and state personnel to evaluate the impact of future proposed scenarios. The management model consists of a simple hydrologic model within an interactive groundwater management framework. This framework is based on an object user interface that was developed by the U.S. Geological Survey and has been used by the Desert Research Institute researchers and others to couple disparate environmental resource models, manage the necessary temporal and spatial data, and evaluate model results for management decision making. This framework was modified and applied to the CNTA and surrounding Hot Creek Valley. The utility of the management model was demonstrated through the application of hypothetical future scenarios including mineral mining, regional expansion of agriculture, geothermal energy production, and export of water to large urban areas outside the region. While the results from some of the scenarios indicated potential impacts to the region near CNTA and others did not, together they demonstrate the usefulness of the management tool for managers who need to evaluate the impact proposed changes in groundwater use in or near CNTA may have on radionuclide migration.

Douglas P. Boyle; Gregg Lamorey; Scott Bassett; Greg Pohll; Jenny Chapman

2006-01-25T23:59:59.000Z

187

TEST SYSTEM FOR EVALUATING SPENT NUCLEAR FUEL BENDING STIFFNESS AND VIBRATION INTEGRITY  

SciTech Connect

Transportation packages for spent nuclear fuel (SNF) must meet safety requirements specified by federal regulations. For normal conditions of transport, vibration loads incident to transport must be considered. This is particularly relevant for high-burnup fuel (>45 GWd/MTU). As the burnup of the fuel increases, a number of changes occur that may affect the performance of the fuel and cladding in storage and during transportation. The mechanical properties of high-burnup de-fueled cladding have been previously studied by subjecting defueled cladding tubes to longitudinal (axial) tensile tests, ring-stretch tests, ring-compression tests, and biaxial tube burst tests. The objective of this study is to investigate the mechanical properties and behavior of both the cladding and the fuel in it under vibration/cyclic loads similar to the sustained vibration loads experienced during normal transport. The vibration loads to SNF rods during transportation can be characterized by dynamic, cyclic, bending loads. The transient vibration signals in a specified transport environment can be analyzed, and frequency, amplitude and phase components can be identified. The methodology being implemented is a novel approach to study the vibration integrity of actual SNF rod segments through testing and evaluating the fatigue performance of SNF rods at defined frequencies. Oak Ridge National Laboratory (ORNL) has developed a bending fatigue system to evaluate the response of the SNF rods to vibration loads. A three-point deflection measurement technique using linear variable differential transformers is used to characterize the bending rod curvature, and electromagnetic force linear motors are used as the driving system for mechanical loading. ORNL plans to use the test system in a hot cell for SNF vibration testing on high burnup, irradiated fuel to evaluate the pellet-clad interaction and bonding on the effective lifetime of fuel-clad structure bending fatigue performance. Technical challenges include pure bending implementation, remote installation and detachment of the SNF test specimen, test specimen deformation measurement, and identification of a driving system suitable for use in a hot cell. Surrogate test specimens have been used to calibrate the test setup and conduct systematic cyclic tests. The calibration and systematic cyclic tests have been used to identify test protocol issues prior to implementation in the hot cell. In addition, cyclic hardening in unidirectional bending and softening in reverse bending were observed in the surrogate test specimens. The interface bonding between the surrogate clad and pellets was found to impact the bending response of the surrogate rods; confirming this behavior in the actual spent fuel segments will be an important aspect of the hot cell test implementation,

Wang, Jy-An John [ORNL; Wang, Hong [ORNL; Bevard, Bruce Balkcom [ORNL; Howard, Rob L [ORNL; Flanagan, Michelle [U.S. Nuclear Regulatory Commission

2013-01-01T23:59:59.000Z

188

Testing nuclear parton distributions with pA collisions at the TeV scale  

SciTech Connect

Global perturbative QCD analyses, based on large data sets from electron-proton and hadron collider experiments, provide tight constraints on the parton distribution function (PDF) in the proton. The extension of these analyses to nuclear parton distribution functions (nPDFs) has attracted much interest in recent years. nPDFs are needed as benchmarks for the characterization of hot QCD matter in nucleus-nucleus collisions, and attract further interest since they may show novel signatures of nonlinear density-dependent QCD evolution. However, it is not known from first principles whether the factorization of long-range phenomena into process-independent parton distribution, which underlies global PDF extractions for the proton, extends to nuclear effects. As a consequence, assessing the reliability of nPDFs for benchmark calculations goes beyond testing the numerical accuracy of their extraction and requires phenomenological tests of the factorization assumption. Here, we argue that a proton-nucleus collision program at the Large Hadron Collider would provide a set of measurements, which allow for unprecedented tests of the factorization assumption, underlying global nPDF fits.

Quiroga-Arias, Paloma [Departamento de Fisica de Particulas and Instituto Galego de Fisica de Altas Enerxias, Universidade de Santiago de Compostela 15706 Santiago de Compostela (Spain); Physics Department, Theory Unit, CERN, CH-1211 Geneve 23 (Switzerland); Milhano, Jose Guilherme [Centro Multidisciplinar de Astrofisica-CENTRA, Departamento de Fisica, Instituto Superior Tecnico (IST), Avenida Rovisco Pais 1, P-1049-001 Lisboa (Portugal); Physics Department, Theory Unit, CERN, CH-1211 Geneve 23 (Switzerland); Wiedemann, Urs Achim [Physics Department, Theory Unit, CERN, CH-1211 Geneve 23 (Switzerland)

2010-09-15T23:59:59.000Z

189

Testing nuclear parton distributions with pA collisions at the LHC  

E-Print Network (OSTI)

Global perturbative QCD analyses, based on large data sets from electron-proton and hadron collider experiments, provide tight constraints on the parton distribution function (PDF) in the proton. The extension of these analyses to nuclear parton distributions (nPDF) has attracted much interest in recent years. nPDFs are needed as benchmarks for the characterization of hot QCD matter in nucleus-nucleus collisions, and attract further interest since they may show novel signatures of non-linear density-dependent QCD evolution. However, it is not known from first principles whether the factorization of long-range phenomena into process-independent parton distribution, which underlies global PDF extractions for the proton, extends to nuclear effects. As a consequence, assessing the reliability of nPDFs for benchmark calculations goes beyond testing the numerical accuracy of their extraction and requires phenomenological tests of the factorization assumption. Here we argue that a proton-nucleus collision program at the LHC would provide a set of measurements allowing for unprecedented tests of the factorization assumption underlying global nPDF fits.

Paloma Quiroga-Arias; Jose Guilherme Milhano; Urs Achin Wiedemann

2010-02-12T23:59:59.000Z

190

Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test  

Science Conference Proceedings (OSTI)

Groundwater flow and radionuclide transport at the Shoal underground nuclear test are characterized using three-dimensional numerical models, based on site-specific hydrologic data. The objective of this modeling is to provide the flow and transport models needed to develop a contaminant boundary defining the extent of radionuclide-contaminated groundwater at the site throughout 1,000 years at a prescribed level of confidence. This boundary will then be used to manage the Project Shoal Area for the protection of the public and the environment.

K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

2004-03-01T23:59:59.000Z

191

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices  

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

192

Acoustic emission monitoring of hot functional testing: Watts Bar Unit 1 Nuclear Reactor  

Science Conference Proceedings (OSTI)

Acoustic emission (AE) monitoring of selected pressure boundary areas at TVA's Watts Bar, Unit 1 Nuclear Power Plant during hot functional preservice testing is described in this report. The report deals with background, methodology, and results. The work discussed here is a major milestone in a program supported by NRC to develop and demonstrate application of AE monitoring for continuous surveillance of reactor pressure boundaries to detect and evaluate growing flaws. The subject work demonstrated that anticipated problem areas can be overcome. Work is continuing toward AE monitoring during reactor operation.

Hutton, P.H.; Dawson, J.F.; Friesel, M.A.; Harris, J.C.; Pappas, R.A.

1984-06-01T23:59:59.000Z

193

Assessment of hydrologic transport of radionuclides from the Rio Blanco underground nuclear test site, Colorado  

SciTech Connect

DOE is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations used for nuclear testing. Evaluation of radionuclide transport by groundwater is part of preliminary risk analysis. These evaluations allow prioritization of test areas in terms of risk, provide a basis for discussions with regulators and the public about future work, and provide a framework for assessing site characterization data needs. The Rio Blanco site in Colorado was the location of the simultaneous detonation of three 30-kiloton nuclear devices. The devices were located 1780, 1899, and 2039 below ground surface in the Fort Union and Mesaverde formations. Although all the bedrock formations at the site are thought to contain water, those below the Green River Formation (below 1000 in depth) are also gas-bearing, and have very low permeabilities. The transport scenario evaluated was the migration of radionuclides from the blast-created cavity through the Fort Union Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. This modeling was performed to investigate how the uncertainty in various physical parameters affect radionuclide transport at the site, and to serve as a starting point for discussion regarding further investigation; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values. Given the sparse data, the modeling results may differ significantly from reality. Confidence in transport predictions can be increased by obtaining more site data, including the amount of radionuclides which would have been available for transport (i.e., not trapped in melt glass or vented during gas flow testing), and the hydraulic properties of the formation. 38 refs., 6 figs., 1 tab.

Chapman, J.; Earman, S.; Andricevic, R.

1996-10-01T23:59:59.000Z

194

Plant Engineering: Performance Diagnostic Test Program for the Nuclear Turbine Cycle at Korea Hydro & Nuclear Power Company  

Science Conference Proceedings (OSTI)

Currently, many power generating companies are challenged to reduce operating costs, and at the same time, the cost of unit unavailability can be significant in today's power markets. In the past decade, management of nuclear power plants, including Korea Hydro & Nuclear Power (KHNP), has been focused on reducing forced outage rates and nuclear-safety-related issues, with less attention paid to thermal performance. But recently, KHNP has been strongly challenged to increase unit thermal performance, as f...

2012-02-28T23:59:59.000Z

195

The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology  

Science Conference Proceedings (OSTI)

To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team projects and faculty/staff exchanges. In June of 2008, the first week-long ATR NSUF Summer Session was attended by 68 students, university faculty and industry representatives. The Summer Session featured presentations by 19 technical experts from across the country and covered topics including irradiation damage mechanisms, degradation of reactor materials, LWR and gas reactor fuels, and non-destructive evaluation. High impact research results from leveraging the entire research infrastructure, including universities, industry, small business, and the national laboratories. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. Current partner facilities include the MIT Reactor, the University of Michigan Irradiated Materials Testing Laboratory, the University of Wisconsin Characterization Laboratory, and the University of Nevada, Las Vegas transmission Electron Microscope User Facility. Needs for irradiation of material specimens at tightly controlled temperatures are being met by dedication of a large in-pile pressurized water loop facility for use by ATR NSUF users. Several environmental mechanical testing systems are under construction to determine crack growth rates and fracture toughness on irradiated test systems.

T. R. Allen; J. B. Benson; J. A. Foster; F. M. Marshall; M. K. Meyer; M. C. Thelen

2009-05-01T23:59:59.000Z

196

Proceedings of the 22nd Annual DoD/DOE Seismic Research Symposium: Planning for Verification of and Compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT)  

SciTech Connect

These proceedings contain papers prepared for the 22nd Annual DoD/DOE Seismic Research Symposium: Planning for Verification of and Compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT), held 13-15 September 2000 in New Orleans, Louisiana. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Technical Applications Center (AFTAC), Department of Defense (DoD), US Army Space and Missile Defense Command, Defense Special Weapons Agency (DSWA), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Nichols, James W., LTC [Editor

2000-09-15T23:59:59.000Z

197

TEST - SECRETARY STEVEN CHU'S REMARKS AS PREPARED FOR DELIVERY TO THE DOE TRIBAL SUMMIT  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tribal Summit Tribal Summit Secretary Steven Chu Remarks as Prepared for Delivery Thursday, May 5, 2011 Arlington, VA Good morning. Thank you all for joining us today, including those of you watching online. The Obama Administration is committed to strong engagement with Tribal Nations. As a sign of that commitment, you heard from Secretary Vilsack yesterday, and today you will also hear from Secretary Salazar, Administrator Jackson, and White House officials. When I started as Energy Secretary, I made a commitment to hold this summit because it's important to hear directly from you about our shared energy challenges and opportunities. The second commitment I made was to support the Department of Energy's Office of Indian Energy Policy and Programs, which was established under the 2005 Energy Policy Act.

198

Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)  

SciTech Connect

The compact (R0~1.2-1.3m) Fusion Nuclear Science Facility (FNSF) is aimed at providing a fully integrated, continuously driven fusion nuclear environment of copious fusion neutrons. This facility would be used to test, discover, understand, and innovate scientific and technical solutions for the challenges facing DEMO, by addressing the multi-scale synergistic interactions involving fusion plasma material interactions, tritium fuel cycle, power extraction, and the nuclear effects on materials. Such a facility properly designed would provide, initially at the JET-level plasma pressure (~30%T2) and conditions (e.g., Hot-Ion H-Mode), an outboard fusion neutron flux of 0.25 MW/m2 while requiring a fusion power of 19 MW. If and when this research operation is successful, its performance can be extended to 1 MW/m2 and 76 MW by reaching for twice the JET plasma pressure and Q. High-safety factor q and moderate- plasmas would minimize plasma-induced disruptions, helping to deliver reliably a neutron fluence of 1 MW-yr/m2 and a duty factor of 10% presently anticipated for the FNS research. Success of this research will depend on achieving time-efficient installation and replacement of all components using extensive remote handling (RH). This in turn requires modular designs for all internal components, including the single-turn toroidal field coil center-post with RH-compatible bi-directional sliding joints. Such device goals would further dictate placement of support structures and vacuum seal welds behind the internal and shielding components. If these further goals could be achieved, the FNSF would provide a ready upgrade path to the Component Test Facility (CTF), which would aim to test, at higher neutron fluence and duty cycle, the demanding fusion nuclear engineering and technologies for DEMO. This FNSF-CTF strategy would be complementary to the ITER and the Broader Approach programs, and thereby help mitigate the risks of an aggressive world fusion DEMO R&D Program. The key physics and technology research needed in the next decade to manage the potential risks of this FNSF are identified.

Peng, Yueng Kay Martin [ORNL

2010-01-01T23:59:59.000Z

199

Assessment of hydrologic transport of radionuclides from the Gasbuggy underground nuclear test site, New Mexico  

SciTech Connect

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gasbuggy site in northwestern New Mexico was the location of an underground detonation of a 29-kiloton nuclear device in 1967. The test took place in the Lewis Shale, approximately 182 m below the Ojo Alamo Sandstone, which is the aquifer closest to the detonation horizon. The conservative assumption was made that tritium was injected from the blast-created cavity into the Ojo Alamo Sandstone by the force of the explosion, via fractures created by the shot. Model results suggest that if radionuclides produced by the shot entered the Ojo Alamo, they are most likely contained within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity, followed by the variance in hydraulic conductivity, the correlation scale of hydraulic conductivity, the transverse hydrodynamic dispersion coefficient, and uncertainty in the source size. This modeling was performed to investigate how the uncertainty in various physical parameters affects calculations of radionuclide transport at the Gasbuggy site, and to serve as a starting point for discussion regarding further investigation at the site; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values.

Earman, S.; Chapman, J.; Andricevic, R.

1996-09-01T23:59:59.000Z

200

Nuclear interactions of 160 MeV protons stopping in copper: A test of Monte Carlo nuclear models  

Science Conference Proceedings (OSTI)

To estimate the influence of nuclear interactions on dose or biological effect one uses Monte Carlo programs which include nuclear models. We introduce an experimental method to check these models at proton therapy energies. We have measured the distribution of charge deposited by 160 MeV protons stopping in a stack of insulated copper plates. A buildup region ahead of the main peak contains ?20% of the total charge and is entirely due to charged secondaries from inelastic nuclear interactions. The acceptance for charged secondaries is 100%. Therefore the data are a good benchmark for nuclear models. We have simulated the stack using GEANT with two nuclear models.FLUKA agrees fairly well with the measurement but GHEISHA

Bernard Gottschalk; Rachel Platais; Harald Paganetti

1999-01-01T23:59:59.000Z

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201

SiC-CMC-Zircaloy-4 Nuclear Fuel Cladding Performance during 4-Point Tubular Bend Testing  

SciTech Connect

The U.S. Department of Energy Office of Nuclear Energy (DOE NE) established the Light Water Reactor Sustainability (LWRS) program to develop technologies and other solutions to improve the reliability, sustain the safety, and extend the life of current reactors. The Advanced LWR Nuclear Fuel Development Pathway in the LWRS program encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. Recent investigations of potential options for “accident tolerant” nuclear fuel systems point to the potential benefits of silicon carbide (SiC) cladding. One of the proposed SiC-based fuel cladding designs being investigated incorporates a SiC ceramic matrix composite (CMC) as a structural material supplementing an internal Zircaloy-4 (Zr-4) liner tube, referred to as the hybrid clad design. Characterization of the advanced cladding designs will include a number of out-of-pile (nonnuclear) tests, followed by in-pile irradiation testing of the most promising designs. One of the out-of-pile characterization tests provides measurement of the mechanical properties of the cladding tube using four point bend testing. Although the material properties of the different subsystems (materials) will be determined separately, in this paper we present results of 4-point bending tests performed on fully assembled hybrid cladding tube mock-ups, an assembled Zr-4 cladding tube mock-up as a standard and initial testing results on bare SiC-CMC sleeves to assist in defining design parameters. The hybrid mock-up samples incorporated SiC-CMC sleeves fabricated with 7 polymer impregnation and pyrolysis (PIP) cycles. To provide comparative information; both 1- and 2-ply braided SiC-CMC sleeves were used in this development study. Preliminary stress simulations were performed using the BISON nuclear fuel performance code to show the stress distribution differences for varying lengths between loading points and clad configurations. The 2-ply sleeve samples show a higher bend momentum compared to those of the 1-ply sleeve samples. This is applicable to both the hybrid mock-up and bare SiC-CMC sleeve samples. Comparatively both the 1- and 2-ply hybrid mock-up samples showed a higher bend stiffness and strength compared with the standard Zr-4 mock-up sample. The characterization of the hybrid mock-up samples showed signs of distress and preliminary signs of fraying at the protective Zr-4 sleeve areas for the 1-ply SiC-CMC sleeve. In addition, the microstructure of the SiC matrix near the cracks at the region of highest compressive bending strain shows significant cracking and flaking. The 2-ply SiC-CMC sleeve samples showed a more bonded, cohesive SiC matrix structure. This cracking and fraying causes concern for increased fretting during the actual use of the design. Tomography was proven as a successful tool to identify open porosity during pre-test characterization. Although there is currently insufficient data to make conclusive statements regarding the overall merit of the hybrid cladding design, preliminary characterization of this novel design has been demonstrated.

IJ van Rooyen; WR Lloyd; TL Trowbridge; SR Novascone; KM Wendt; SM Bragg-Sitton

2013-09-01T23:59:59.000Z

202

Department of Mechanical and Nuclear Engineering Fall 2011 Torque and Axial Measurement Device for Soil Abrasion Testing  

E-Print Network (OSTI)

PENNSTATE Department of Mechanical and Nuclear Engineering Fall 2011 Torque and Axial Measurement Device for Soil Abrasion Testing Overview The Penn State Department of Energy and Mineral Engineering to completely re-design with five weeks left. This left minimal time for machining, assembly, testing

Demirel, Melik C.

203

Department of Mechanical and Nuclear Engineering Spring 2012 Heavy-Duty Diesel Engine Friction Reduction Testing and Analysis  

E-Print Network (OSTI)

PENNSTATE Department of Mechanical and Nuclear Engineering Spring 2012 Heavy-Duty Diesel Engine Friction Reduction Testing and Analysis Overview Volvo Group Powertrain Engineering is interested in increasing fuel efficiency through the reduction of parasitic friction and pumping losses. A test cell

Demirel, Melik C.

204

GEOPHYSICAL RESEARCH LETTERS, VOL. 27, NO. 15, PAGES 2245-2248, AUGUST 1, 2000 Sub-surface nuclear tests monitoring through the  

E-Print Network (OSTI)

) which should detect nuclear tests down to 1 kiloton (kt) TNT equivalent anywhere on the planet. The IMS), hydroacoustic and infrasound waves will help check for underground, under-water and atmospheric nuclear testsGEOPHYSICAL RESEARCH LETTERS, VOL. 27, NO. 15, PAGES 2245-2248, AUGUST 1, 2000 Sub-surface nuclear

Hourdin, Chez Frédéric

205

Concentration of Actinides in Plant Mounds at Safety Test Nuclear Sites in Nevada  

SciTech Connect

Plant mounds or blow-sand mounds are accumulations of soil particles and plant debris around large shrubs and are common features in deserts in the southwestern United States. Believed to be an important factor in their formation, the shrubs create surface roughness that causes wind-suspended particles to be deposited and resist further suspension. Shrub mounds occur in some plant communities on the Nevada Test Site, the Nevada Test and Training Range (NTTR), and Tonopah Test Range (TTR), including areas of surface soil contamination from past nuclear testing. In the 1970s as part of early studies to understand properties of actinides in the environment, the Nevada Applied Ecology Group (NAEG) examined the accumulation of isotopes of Pu, {sup 241}Am, and U in plant mounds at safety test sites. The NAEG studies found concentrations of these contaminants to be greater in shrub mounds than in the surrounding areas of desert pavement. For example, at Project 57 on the NTTR, it was estimated that 15 percent of the radionuclide inventory of the site was associated with shrub mounds, which accounted for 17 percent of the surface area of the site, a ratio of inventory to area of 0.85. At Clean Slate III at the TTR, 29 percent of the inventory was associated with approximately 32 percent of the site covered by shrub mounds, a ratio of 0.91. While the total inventory of radionuclides in intershrub areas was greater, the ratio of radionuclide inventory to area was 0.40 and 0.38, respectively, at the two sites. The comparison between the shrub mounds and adjacent desert pavement areas was made for only the top 5 cm since radionuclides at safety test sites are concentrated in the top 5 cm of intershrub areas. Not accounting for radionuclides associated with the shrub mounds would cause the inventory of contaminants and potential exposure to be underestimated. As part of its Environmental Restoration Soils Subproject, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office has proposed that the majority of its contaminated soil 'Corrective Action Units', including the safety test sites, be closed by fencing and posting with administrative controls. The concentration of actinides in the shrub mounds has important implications for postclosure management of the safety test sites. Because resuspension factors at safety test sites can be three to four orders-of-magnitude higher than soil sites associated with atmospheric tests where criticality occurred, the shrub mounds are an important factor in stabilization of actinide contaminants. Loss of shrubs associated with mounds from fire or plant die-back from drought could cause radionuclides at these sites to become more prone to suspension and water erosion until the sites are stabilized. Alternatively, although shrub mounds are usually composed of predominantly fine sand size particles, smaller silt and clay size particles in them are often high in CaCO{sub 3} content. The CaCO{sub 3} may act as a cementing agent to limit erosion of the shrub mounds even if the vegetation cover is temporarily lost.

David S. Shafer; Jenna Gommes

2008-09-15T23:59:59.000Z

206

Characterization of microbial communities in subsurface nuclear blast cavities of the Nevada Test Site  

SciTech Connect

This US Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada Test Site subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this programâ??s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

Duane P. Moser; Ken Czerwinski; Charles E. Russell; Mavrik Zavarin

2010-07-13T23:59:59.000Z

207

Characterization of Microbial Communities in Subsurface Nuclear Blast Cavities of the Nevada Test Site  

Science Conference Proceedings (OSTI)

This U.S. Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada Test Site subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this program’s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

Duane P. Moser, Jim Bruckner, Jen Fisher, Ken Czerwinski, Charles E. Russell, and Mavrik Zavarin

2010-09-01T23:59:59.000Z

208

Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991  

Science Conference Proceedings (OSTI)

This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program.

Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

1992-01-01T23:59:59.000Z

209

Planning, Preparation, and Transport of the High-Enriched Uranium Spent Nuclear Fuel from the Czech Republic to the Russian Federation  

SciTech Connect

The United States, Russian Federation, and the International Atomic Energy Agency have been working together on a program called the Russian Research Reactor Fuel Return (RRRFR) Program, which is part of the Global Threat Reduction Initiative. The purpose of this program is to return Soviet or Russian-supplied high-enriched uranium (HEU) fuel, currently stored at Russian-designed research reactors throughout the world, to Russia. In February 2003, the RRRFR Program began discussions with the Nuclear Research Institute (NRI) in Rež, Czech Republic, about returning their HEU spent nuclear fuel to the Russian Federation for reprocessing. In March 2005, the U.S. Department of Energy signed a contract with NRI to perform all activities needed for transporting their HEU spent nuclear fuel to Russia. After 2 years of intense planning, preparations, and coordination at NRI and with three other countries, numerous organizations and agencies, and a Russian facility, this shipment is scheduled for completion before the end of 2007. This paper will provide a summary of activities completed for making this international shipment. This paper contains an introduction and background of the RRRFR Program and the NRI shipment project. It summarizes activities completed in preparation for the shipment, including facility preparations at NRI in Rež and FSUE “Mayak” in Ozyorsk, Russia; a new transportation cask system; regulatory approvals; transportation planning and preparation in the Czech Republic, Slovakia, Ukraine, and the Russian Federation though completion of the Unified Project and Special Ecological Programs. The paper also describes fuel loading and cask preparations at NRI and final preparations/approvals for transporting the shipment across the Czech Republic, Slovakia, Ukraine, and the Russian Federation to FSUE Mayak where the HEU spent nuclear fuel will be processed, the uranium will be downblended and made into low-enriched uranium fuel for commercial reactor use, and the high-level waste from the processing will be stabilized and stored for less than 20 years before being sent back to the Czech Republic for final disposition. Finally, the paper contains a section for the summary and conclusions.

M. J. Tyacke; I. Bolshinsky; Frantisek Svitak

2007-10-01T23:59:59.000Z

210

Proceedings of the Numerical Modeling for Underground Nuclear Test Monitoring Symposium  

SciTech Connect

The purpose of the meeting was to discuss the state-of-the-art in numerical simulations of nuclear explosion phenomenology with applications to test ban monitoring. We focused on the uniqueness of model fits to data, the measurement and characterization of material response models, advanced modeling techniques, and applications of modeling to monitoring problems. The second goal of the symposium was to establish a dialogue between seismologists and explosion-source code calculators. The meeting was divided into five main sessions: explosion source phenomenology, material response modeling, numerical simulations, the seismic source, and phenomenology from near source to far field. We feel the symposium reached many of its goals. Individual papers submitted at the conference are indexed separately on the data base.

Taylor, S.R.; Kamm, J.R. [eds.

1993-11-01T23:59:59.000Z

211

Three path interference using nuclear magnetic resonance: a test of the consistency of Born's rule  

E-Print Network (OSTI)

The Born rule is at the foundation of quantum mechanics and transforms our classical way of understanding probabilities by predicting that interference occurs between pairs of independent paths of a single object. One consequence of the Born rule is that three way (or three paths) quantum interference does not exist. In order to test the consistency of the Born rule, we examine detection probabilities in three path intereference using an ensemble of spin-1/2 quantum registers in liquid state nuclear magnetic resonance (LSNMR). As a measure of the consistency, we evaluate the ratio of three way interference to two way interference. Our experiment bounded the ratio to the order of $10^{-3} \\pm 10^{-3}$, and hence it is consistent with Born's rule.

Daniel K. Park; Osama Moussa; Raymond Laflamme

2012-07-10T23:59:59.000Z

212

Standard test methods for chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide (Gd2O3) powder  

E-Print Network (OSTI)

1.1 These test methods cover procedures for the chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide powders to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Carbon by Direct CombustionThermal Conductivity C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method Total Chlorine and Fluorine by Pyrohydrolysis Ion Selective Electrode C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide Loss of Weight on Ignition 7-13 Sulfur by CombustionIodometric Titration Impurity Elements by a Spark-Source Mass Spectrographic C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical,Nuclear, and Radiochemical Analysis of Uranium Hexafluoride C1287 Test Method for Determination of Impurities In Uranium Dioxide By Inductively Coupled Plasma Mass Spectrometry Gadolinium Content in Gadolinium Oxid...

American Society for Testing and Materials. Philadelphia

2006-01-01T23:59:59.000Z

213

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called User’s Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. User’s week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

214

Preparation of design specifications and design reports for pumps, valves, piping, and piping supports used in safety-related portions of nuclear power plants  

SciTech Connect

Section III of the ASME Boiler and Pressure Vessel Code requires the preparation of Design Specifications and Design Reports as part of the design process leading to construction of a nuclear power plant, in compliance with provisions of Title 10 of the Code of Federal Regulations (10 CFR). Guidelines for preparing this documentation are contained in nonmandatory Appendixes B and C of the ASME Code. This report gives an in-depth review of the ASME Code requirements and guidance, beginning with the first edition of the Code in 1963 through the 1983 edition, Summer 1985 Addenda. Recommendations for substantial revisions to the Code are presented based on the authors experience in conducting design documentation audits of pumps, valves, piping, and piping supports for nuclear power plants undergoing Nuclear Regulatory Commission (NRC) review for Operating Licenses. It is concluded that adequate Design Specifications and Design Reports are absolutely necessary for the normal operating life of a plant and are vital if plant life extension is planned.

Rodabaugh, E.C.; Moore, S.E.

1987-06-01T23:59:59.000Z

215

Development of an Automated Testing System for Verification and Validation of Nuclear Data and Simulation Code  

Science Conference Proceedings (OSTI)

Technical Paper / Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Radiation Measurements and Instrumentation

Brian S. Triplett; Samim Anghaie; Morgan C. White

216

Advanced Burner Test Reactor - Preconceptual Design Report  

NLE Websites -- All DOE Office Websites (Extended Search)

Burner Test Reactor Preconceptual Design Report ANL-ABR-1 (ANL-AFCI-173) Nuclear Engineering Division Disclaimer This report was prepared as an account of work sponsored by an...

217

Standard test methods for determining chemical durability of nuclear, hazardous, and mixed waste glasses and multiphase glass ceramics: The product consistency test (PCT)  

E-Print Network (OSTI)

1.1 These product consistency test methods A and B evaluate the chemical durability of homogeneous glasses, phase separated glasses, devitrified glasses, glass ceramics, and/or multiphase glass ceramic waste forms hereafter collectively referred to as “glass waste forms” by measuring the concentrations of the chemical species released to a test solution. 1.1.1 Test Method A is a seven-day chemical durability test performed at 90 ± 2°C in a leachant of ASTM-Type I water. The test method is static and conducted in stainless steel vessels. Test Method A can specifically be used to evaluate whether the chemical durability and elemental release characteristics of nuclear, hazardous, and mixed glass waste forms have been consistently controlled during production. This test method is applicable to radioactive and simulated glass waste forms as defined above. 1.1.2 Test Method B is a durability test that allows testing at various test durations, test temperatures, mesh size, mass of sample, leachant volume, a...

American Society for Testing and Materials. Philadelphia

2002-01-01T23:59:59.000Z

218

Live Operation Data Collection Optimization and Communication for the Domestic Nuclear Detection Office’s Rail Test Center  

Science Conference Proceedings (OSTI)

For the Domestic Nuclear Detection Office’s Rail Test Center (i.e., DNDO’s RTC), port operation knowledge with flexible collection tools and technique are essential in both technology testing design and implementation intended for live operational settings. Increased contextual data, flexibility in procedures, and rapid availability of information are keys to addressing the challenges of optimization, validation, and analysis within live operational setting data collection. These concepts need to be integrated into technology testing designs, data collection, validation, and analysis processes. A modified data collection technique with a two phased live operation test method is proposed.

Gelston, Gariann M.

2010-04-06T23:59:59.000Z

219

Fabrication of CeO2 by sol-gel process based on microfluidic technology as an analog preparation of ceramic nuclear fuel microspheres  

E-Print Network (OSTI)

Microfluidics integrated with sol-gel processes is introduced in preparing monodispersed MOX nuclear fuel microspheres using nonactive cerium as a surrogate for uranium or plutonium. The detailed information about microfluidic devices and sol-gel processes are provided. The effects of viscosity and flow rate of continuous and dispersed phase on size and size distribution of CeO2 microspheres have been investigated. A comprehensive characterization of the CeO2 microspheres has been conducted, including XRD pattern, SEM, density, size and size distribution. The size of prepared monodisperse particles can be controlled precisely in range of 10{\\mu}m to 1000{\\mu}m and the particle CV is below 3%.

Bin Ye; Jilang Miao; Jiaolong Li; Zichen Zhao; Zhenqi Chang; Christophe A. Serra

2012-12-15T23:59:59.000Z

220

Fabrication of CeO2 by sol-gel process based on microfluidic technology as an analog preparation of ceramic nuclear fuel microspheres  

E-Print Network (OSTI)

Microfluidics integrated with sol-gel processes is introduced in preparing monodispersed MOX nuclear fuel microspheres using nonactive cerium as a surrogate for uranium or plutonium. The detailed information about microfluidic devices and sol-gel processes are provided. The effects of viscosity and flow rate of continuous and dispersed phase on size and size distribution of CeO2 microspheres have been investigated. A comprehensive characterization of the CeO2 microspheres has been conducted, including XRD pattern, SEM, density, size and size distribution. The size of prepared monodisperse particles can be controlled precisely in range of 10{\\mu}m to 1000{\\mu}m and the particle CV is below 3%.

Ye, Bin; Li, Jiaolong; Zhao, Zichen; Chang, Zhenqi; Serra, Christophe A

2012-01-01T23:59:59.000Z

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221

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

of nuclear proliferation: a quantitative test. Journal ofINTERNATIONAL NUCLEAR ASSISTANCE DATA To test this strategictheory of nuclear proliferation faces a difficult test in

Kroenig, Matthew

2006-01-01T23:59:59.000Z

222

ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. INITIAL FULL POWER AND LIMITED ENDURANCE TESTS OF THE ML-1 NUCLEAR POWER PLANT. Final Test Report  

SciTech Connect

The evaluation of the data generated during the full power and limited endurance tests of the ML-1 mobile nuclear power plant indicates that the reactor performs in accordance with the design specifications. During the 101 hr test period, the reactor attained a maximum power of 3.44 Mw( and 247 kw(e) was measured at the output shaft of the turbine-compressor set. No operating limits were exceeded during these tests and all systems performed satisfactorily Except for the known performance deficiency of the turbinecompressor set, which prevented the attainment of design output power, no operational, stability, or control problems were encountered. All test objectives were achieved and the tests were considered completely successful. (auth)

Kattchee, N.

1963-07-01T23:59:59.000Z

223

Test Operation of Oxygen-Enriched Incinerator for Wastes From Nuclear Fuel Fabrication Facility  

SciTech Connect

The oxygen-enriched combustion concept, which can minimize off-gas production, has been applied to the incineration of combustible uranium-containing wastes from a nuclear fuel fabrication facility. A simulation for oxygen combustion shows the off-gas production can be reduced by a factor of 6.7 theoretically, compared with conventional air combustion. The laboratory-scale oxygen enriched incineration (OEI) process with a thermal capacity of 350 MJ/h is composed of an oxygen feeding and control system, a combustion chamber, a quencher, a ceramic filter, an induced draft fan, a condenser, a stack, an off-gas recycle path, and a measurement and control system. Test burning with cleaning paper and office paper in this OEI process shows that the thermal capacity is about 320 MJ/h, 90 % of design value and the off-gas reduces by a factor of 3.5, compared with air combustion. The CO concentration for oxygen combustion is lower than that of air combustion, while the O2 concentration in off-gas is kept above 25 vol % for a simple incineration process without any grate. The NOx concentration in an off-gas stream does not reduce significantly due to air incoming by leakage, and the volume and weight reduction factors are not changed significantly, which suggests a need for an improvement in sealing.

Kim, J.-G.; Yang, H.cC.; Park, G.-I.; Kim, I.-T.; Kim, J.-K.

2002-02-26T23:59:59.000Z

224

High energy nuclear quasielastic reactions: Decisive tests of nuclear binding/pion models of the EMC effect  

SciTech Connect

The light-cone nucleon momentum distributions obtained from non- relativistic spectral functions or given by nuclear binding/pion models are often used to analyze high Q{sup 2} quasi-elastic and deep-inelastic (e,e{prime}) reactions. We demonstrate that in such models the presence of non-nucleonic components causes the scattering from forward and backward moving target protons to be significantly different. Other models do not have this property. The sensitivity of current (e,e{prime}p) and (p,pp) color transparency experiments is sufficient to observe these differences.

Frankfurt, L; Strikman, M [Washington Univ., Seattle, WA (United States). Inst. for Nuclear Theory AN SSSR, Leningrad (USSR). Inst. Yadernoj Fiziki; Miller, G A [Washington Univ., Seattle, WA (United States). Inst. for Nuclear Theory

1991-01-01T23:59:59.000Z

225

Guidelines for Fabrication, Examination, Testing and Oversight of Spent Nuclear Fuel Dry Storage Systems  

Science Conference Proceedings (OSTI)

The Nuclear Waste Policy Act (NWPA) of 1982 and subsequent amendments require the U. S. Department of Energy (DOE) to receive and be responsible for disposal of spent commercial nuclear power plant fuel from U.S. utilities. However, because of delays in the siting of a permanent federal repository, and with no federal interim storage facilities designated, U.S. utilities have been forced to provide additional spent nuclear fuel (SNF) storage capability to accommodate spent fuel discharge requirements. At...

1999-12-10T23:59:59.000Z

226

How ORISE is Making a Difference: Message Testing for a Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

OMB and IRB approval, ORAU coordinated the production of a short film that depicted a nuclear explosion, while setting up research facilities and other logistical requirements...

227

Nuclear Maintenance Applications Center: Wire Brush Testing, Procurement, and Usage Guide  

Science Conference Proceedings (OSTI)

Improper design, selection, or use of wire brushes will cause the loss of wire brush filaments and can result in damage to plant equipment and nuclear fuel.

2010-12-23T23:59:59.000Z

228

Method of preparing gas tags for identification of single and multiple failures of nuclear reactor fuel assemblies  

DOE Patents (OSTI)

For use in the identification of failed fuel assemblies in a nuclear reactor, the ratios of the tag gas isotopic concentrations are located on curved surfaces to enable the ratios corresponding to failure of a single fuel assembly to be distinguished from those formed from any combination of two or more failed assemblies.

McCormick, Norman J. (Seattle, WA)

1976-01-01T23:59:59.000Z

229

A report on high-level nuclear waste transportation: Prepared pursuant to assembly concurrent resolution No. 8 of the 1987 Nevada Legislature  

SciTech Connect

This report has been prepared by the staff of the State of Nevada Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) in response to Assembly Concurrent Resolution No. 8 (ACR 8), passed by the Nevada State Legislature in 1987. ACR 8 directed the NWPO, in cooperation with affected local governments and the Legislative committee on High-Level Radioactive Waste, to prepare this report which scrutinizes the US Department of Energy`s (DOE) plans for transportation of high-level radioactive waste to the proposed yucca Mountain repository, which reviews the regulatory structure under which shipments to a repository would be made and which presents NWPO`s plans for addressing high-level radioactive waste transportation issues. The report is divided into three major sections. Section 1.0 provides a review of DOE`s statutory requirements, its repository transportation program and plans, the major policy, programmatic, technical and institutional issues and specific areas of concern for the State of Nevada. Section 2.0 contains a description of the current federal, state and tribal transportation regulatory environment within which nuclear waste is shipped and a discussion of regulatory issues which must be resolved in order for the State to minimize risks and adverse impacts to its citizens. Section 3.0 contains the NWPO plan for the study and management of repository-related transportation. The plan addresses four areas, including policy and program management, regulatory studies, technical reviews and studies and institutional relationships. A fourth section provides recommendations for consideration by State and local officials which would assist the State in meeting the objectives of the plan.

1988-12-01T23:59:59.000Z

230

A dose assessment for a U.S. nuclear test site -- Bikini Atoll  

Science Conference Proceedings (OSTI)

On March 1, 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. Here the authors provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island. The unique composition of coral soil greatly alters the relative contribution of cesium-137 and strontium-90 to the total estimated dose relative to expectations based on North American and European soils. Cesium-137 produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The estimated maximum annual effective dose is 4.4 mSv y{sup {minus}1} when imported foods, which are now an established part of the diet, are available. The 30-, 50-, and 70-y integral effective doses are 10 cSv, 14 cSv, and 16 cSv, respectively. An analysis of interindividual variability in 0- to 30-y expected integral dose indicates that 95% of Bikini residents would have expected doses within a factor of 3.4 above and 4.8 below the population-average value. A corresponding uncertainty analysis showed that after about 5 y of residence, the 95% confidence limits on population-average dose would be {+-}35% of its expected value. The authors have evaluated various countermeasures to reduce {sup 137}Cs in food crops. Treatment with potassium reduces the uptake of {sup 137}Cs into food crops, and therefore the ingestion dose, to less than 10% of pretreatment levels and has essentially no negative environmental consequences.

Robison, W.L.; Bogen, K.T.; Conrado, C.L.

1993-07-01T23:59:59.000Z

231

An updated dose assessment for a U.S. Nuclear Test Site - Bikini Atoll  

Science Conference Proceedings (OSTI)

On March 1, 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. There has been a continuing effort since 1977 to refine dose assessments for resettlement options at Bikini Atoll. Here we provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island as part of our continuing research and monitoring program that began in 1975. The unique composition of coral soil greatly alters the relative contribution of cesium-137 ({sup 137}Cs) and strontium-90 ({sup 90}Sr) to the total estimated dose relative to expectations based on North American and European soils. Without counter measures, cesium-137 produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The doses are calculated assuming a resettlement date of 1999. The estimated maximum annual effective dose for current island conditions is 4.0 mSv when imported foods, which are now an established part of the diet, are available. The corresponding 30-, 50-, and 70-y integral effective doses are 9.1 cSv, 13 cSv, and 15 cSv, respectively. A corresponding uncertainty analysis showed that after about 5 y of residence, the 95% confidence limits on population-average dose would be {plus_minus}35% of its expected value. We have evaluated various countermeasures to reduce {sup 137}Cs in food crops. Treatment with potassium reduces the uptake of {sup 137}Cs into food crops, and therefore the ingestion dose, to about 5% of pretreatment levels and has essentially no negative environmental consequences.

Robison, W.L.; Bogen, K.T.; Conrado, C.L.

1995-10-01T23:59:59.000Z

232

Nuclear fuels technologies fiscal year 1998 research and development test plan  

Science Conference Proceedings (OSTI)

A number of research and development (R and D) activities are planned at Los Alamos National Laboratory (LANL) in FY98 in support of the Department of Energy Office of Fissile Materials Disposition (DOE-MD). During the past few years, the ability to fabricate mixed oxide (MOX) nuclear fuel using surplus-weapons plutonium has been researched, and various experiments have been performed. This research effort will be continued in FY98 to support further development of the technology required for MOX fuel fabrication for reactor-based plutonium disposition. R and D activities for FY98 have been divided into four major areas: (1) feed qualification/supply, (2) fuel fabrication development, (3) analytical methods development, and (4) gallium removal. Feed qualification and supply activities encompass those associated with the production of both PuO{sub 2} and UO{sub 2} feed materials. Fuel fabrication development efforts include studies with a new UO{sub 2} feed material, alternate sources of PuO{sub 2}, and determining the effects of gallium on the sintering process. The intent of analytical methods development is to upgrade and improve several analytical measurement techniques in support of other R and D and test fuel fabrication tasks. Finally, the purpose of the gallium removal system activity is to develop and integrate a gallium removal system into the Pit Disassembly and Conversion Facility (PDCF) design and the Phase 2 Advanced Recovery and Integrated Extraction System (ARIES) demonstration line. These four activities will be coordinated and integrated appropriately so that they benefit the Fissile Materials Disposition Program. This plan describes the activities that will occur in FY98 and presents the schedule and milestones for these activities.

Alberstein, D.; Blair, H.T.; Buksa, J.J. [and others

1998-06-01T23:59:59.000Z

233

Evaluation of Cavity Collapse and Surface Crater Formation at the Norbo Underground Nuclear Test in U8c, Nevada Nuclear Security Site, and the Impact on Stability of the Ground Surface  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL) Containment Program performed a review of nuclear test-related data for the Norbo underground nuclear test in U8c to assist in evaluating this legacy site as a test bed for application technologies for use in On-Site Inspections (OSI) under the Comprehensive Nuclear Test Ban Treaty. This request is similar to one made for the Salut site in U8c (Pawloski, 2012b). Review of the Norbo site is complicated because the test first exhibited subsurface collapse, which was not unusual, but it then collapsed to the surface over one year later, which was unusual. Of particular interest is the stability of the ground surface above the Norbo detonation point. Proposed methods for on-site verification include radiological signatures, artifacts from nuclear testing activities, and imaging to identify alteration to the subsurface hydrogeology due to the nuclear detonation. Aviva Sussman from the Los Alamos National Laboratory (LANL) has also proposed work at this site. Both proposals require physical access at or near the ground surface of specific underground nuclear test locations at the Nevada Nuclear Security Site (NNSS), formerly the Nevada Test Site (NTS), and focus on possible activities such as visual observation, multispectral measurements, and shallow and deep geophysical surveys.

Pawloski, G A

2012-06-18T23:59:59.000Z

234

TYBO/BENHAM: Model Analysis of Groundwater Flow and Radionuclide Migration from Underground Nuclear Tests in Southwestern Pahute Mesa, Nevada  

Science Conference Proceedings (OSTI)

Recent field studies have led to the discovery of trace quantities of plutonium originating from the BENHAM underground nuclear test in two groundwater observation wells on Pahute Mesa at the Nevada Test Site. These observation wells are located 1.3 km from the BENHAM underground nuclear test and approximately 300 m from the TYBO underground nuclear test. In addition to plutonium, several other conservative (e.g. tritium) and reactive (e.g. cesium) radionuclides were found in both observation wells. The highest radionuclide concentrations were found in a well sampling a welded tuff aquifer more than 500m above the BENHAM emplacement depth. These measurements have prompted additional investigations to ascertain the mechanisms, processes, and conditions affecting subsurface radionuclide transport in Pahute Mesa groundwater. This report describes an integrated modeling approach used to simulate groundwater flow, radionuclide source release, and radionuclide transport near the BENHAM and TYBO underground nuclear tests on Pahute Mesa. The components of the model include a flow model at a scale large enough to encompass many wells for calibration, a source-term model capable of predicting radionuclide releases to aquifers following complex processes associated with nonisothermal flow and glass dissolution, and site-scale transport models that consider migration of solutes and colloids in fractured volcanic rock. Although multiple modeling components contribute to the methodology presented in this report, they are coupled and yield results consistent with laboratory and field observations. Additionally, sensitivity analyses are conducted to provide insight into the relative importance of uncertainty ranges in the transport parameters.

Andrew Wolfsberg; Lee Glascoe; Guoping Lu; Alyssa Olson; Peter Lichtner; Maureen McGraw; Terry Cherry; Guy Roemer

2002-09-01T23:59:59.000Z

235

Letter Report: Scoping Analysis of Gas Phase Transport from the Rulison Underground Nuclear Test  

DOE Green Energy (OSTI)

This letter report documents the results of a computer model to quantify the travel time of tritium (radioactive hydrogen) from an underground nuclear detonation in 1969 toward a proposed producing gas well located 1,500 feet (457 meters) away.

Clay Cooper

2004-05-06T23:59:59.000Z

236

Evaluation of Cavity Collapse and Surface Crater Formation for Selected Lawrence Livermore National Laboratory Underground Nuclear Tests - 2010  

SciTech Connect

This report evaluates collapse evolution for selected Lawrence Livermore National Laboratory (LLNL) underground nuclear tests at the Nevada National Security Site (NNSS, formerly called the Nevada Test Site). The work is being done at the request of Navarro-Interra LLC, and supports environmental restoration efforts by the Department of Energy, National Nuclear Security Administration for the Nevada Site Office. Safety decisions must be made before a surface crater area, or potential surface crater area, can be reentered for any work. Our statements on cavity collapse and surface crater formation are input into their safety decisions. These statements do not include the effects of erosion that may modify the surface collapse craters over time. They also do not address possible radiation dangers that may be present. Subject matter experts from the LLNL Containment Program who had been active in weapons testing activities performed these evaluations. Information used included drilling and hole construction, emplacement and stemming, timing and sequence of the selected test and nearby tests, geology, yield, depth of burial, collapse times, surface crater sizes, cavity and crater volume estimations, and ground motion. Both classified and unclassified data were reviewed. Various amounts of information are available for these tests, depending on their age and other associated activities. Lack of data can hamper evaluations and introduce uncertainty. We make no attempt to quantify this uncertainty.

Pawloski, G A

2011-01-03T23:59:59.000Z

237

Evaluation of Cavity Collapse and Surface Crater Formation for Selected Lawrence Livermore National Laboratory Underground Nuclear Tests - 2011, Part 2  

SciTech Connect

This report evaluates collapse evolution for selected Lawrence Livermore National Laboratory (LLNL) underground nuclear tests at the Nevada National Security Site (NNSS, formerly called the Nevada Test Site). The work is being done to support several different programs that desire access to the ground surface above expended underground nuclear tests. The programs include: the Borehole Management Program, the Environmental Restoration Program, and the National Center for Nuclear Security Gas-Migration Experiment. Safety decisions must be made before a crater area, or potential crater area, can be reentered for any work. Evaluation of cavity collapse and crater formation is input into the safety decisions. Subject matter experts from the LLNL Containment Program who participated in weapons testing activities perform these evaluations. Information used included drilling and hole construction, emplacement and stemming, timing and sequence of the selected test and nearby tests, geology, yield, depth of burial, collapse times, surface crater sizes, cavity and crater volume estimations, ground motion, and radiological release information. Both classified and unclassified data were reviewed. The evaluations do not include the effects of erosion that may modify the collapse craters over time. They also do not address possible radiation dangers that may be present. Various amounts of information are available for these tests, depending on their age and other associated activities. Lack of data can hamper evaluations and introduce uncertainty. We make no attempt to quantify this uncertainty. Evaluation of Cavity Collapse and Surface Crater Formation for Selected Lawrence Livermore National Laboratory Underground Nuclear Tests - 2011 was published on March 2, 2011. This report, considered Part 2 of work undertaken in calendar year 2011, compiles evaluations requested after the March report. The following unclassified summary statements describe collapse evolution and crater stability in response to a recent request to review 6 LLNL test locations in Yucca Flat, Rainier Mesa, and Pahute Mesa. They include: Baneberry in U8d; Clearwater in U12q; Wineskin in U12r, Buteo in U20a and Duryea in nearby U20a1; and Barnwell in U20az.

Pawloski, G A

2012-01-30T23:59:59.000Z

238

Ground motion from earthquakes and underground nuclear weapons tests: a comparison as it relates to siting a nuclear waste storage facility at NTS  

Science Conference Proceedings (OSTI)

Ground motion generated by a magnitude 4.3 earthquake at Massachusetts Mountain on the Nevada Test Site was measured at the control point and compared with ground motion generated at about the same distance by four underground nuclear weapons tests. The depth of the earthquake was between 4 and 4.6 km. The resulting signal at the distance considered was almost entirely body-wave components and had little or no contribution from the surface wave. The motion from the relatively shallower weapons tests had a signal with a pronounced surface-wave component. Comparison of the Pseudo Relative Response Velocity (PSRV) plots shows the earthquake signal richer in high frequencies and the weapons-test signals richer in low frequencies. If relationship between ground motion from the two sources can be confirmed for other earthquakes, weapons test ground motion could be used to estimate earthquake ground motion for magnitudes for which probability of occurrence in a given montoring period would be very small.

Vortman, L.J.

1982-01-01T23:59:59.000Z

239

Implementation of test for quality assurance in nuclear medicine gamma camera  

Science Conference Proceedings (OSTI)

In nuclear medicine (NM) over 90% of procedures are performed for diagnostic purposes. To ensure adequate diagnostic quality of images and the optimization of the doses received by patients originated from the radioactive material is essential for regular monitoring and equipment performance through a quality assurance program (QAP). The QAP consists of 15 proposed performance tomographic and not tomographic gamma camera (GC) tests, and is based on recommendations of international organizations. We describe some results of the performance parameters of QAP applied to a GC model e.cam Siemens, of the Department of NM of the National Cancer Institute of Mexico (INCan). The results were: (1) The average intrinsic spatial resolution (R{sub in}) was 4.67 {+-} 0.25 mm at the limit of acceptance criterion of 4.4 mm. (2) The sensitivity extrinsic (S{sub ext}), with maximum variations of 1.8% (less than 2% which is the criterion of acceptance). (3) Rotational Uniformity (U{sub rot}), with values of integral uniformity (IU) in the useful field of view detector (UFOV), with maximum percentage change of 0.97% and monthly variations equal angles, ranging from 0.13 to 0.99% less than 1%. (4) The displacement of the center of rotation (DCOR), indicated a maximum deviation of 0.155 {+-} 0.039 mm less than 4.795 mm, an absolute deviation of less than 0.5 where pixel 0.085 pixel is suggested, the criteria are assigned to low-energy collimator high resolution. (5) In tomographic uniformity (U{sub tomo}), UI values (%) and percentage noise level (rms%) were 7.54 {+-} 1.53 and 4.18 {+-} 1.69 which are consistent with the limits of acceptance of 7.0-12.0% and 3.0-6.0% respectively. The smallest cold sphere has a diameter of 11.4 mm. The implementation of a QAP allows for high quality diagnostic images, optimization of the doses given to patients, a reduction of exposure to occupationally exposed workers (POE, by its Spanish acronym), and generally improves the productivity of the service. This proposal can be used to develop a similar QAP in other facilities and may serve as a precedent for the proposed regulations for quality assurance (QA) teams in MN.

Montoya Moreno, A.; Rodriguez Laguna, A.; Trujillo Zamudio, Flavio E [Department of Nuclear Medicine, National Cancer Institute San Fernando Avenue No.22, Col. Section XVI (Mexico)

2012-10-23T23:59:59.000Z

240

DOE-STD-3007-93 CN-1; DOE Standard Guidelines For Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7-93 7-93 November 1993 CHANGE NOTICE NO. 1 September 1998 DOE STANDARD GUIDELINES FOR PREPARING CRITICALITY SAFETY EVALUATIONS AT DEPARTMENT OF ENERGY NON-REACTOR NUCLEAR FACILITIES U.S. Department of Energy AREA SAFT 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; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Order No. DE98003918 Change Notice No. 1 DOE-STD-3007-93 September 1998

Note: This page contains sample records for the topic "nuclear test prepared" from the National Library of EnergyBeta (NLEBeta).
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241

Design of the Next Generation Nuclear Plant Graphite Creep Experiments for Irradiation in the Advanced Test Reactor  

SciTech Connect

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain seven separate stacks of graphite specimens. Six of the specimen stacks will have half of their graphite specimens under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will be organized into pairs with a different compressive load being applied to the top half of each pair of specimen stacks. The seventh stack will not have a compressive load on the graphite specimens during irradiation. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the experiment. The final design phase for the first experiment was completed in September 2008, and the fabrication and assembly of the experiment test train as well as installation and testing of the control and support systems that will monitor and control the experiment during irradiation are being completed in early calendar 2009. The first experiment is scheduled to be ready for insertion in the ATR by April 30, 2009. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and data collection systems.

S. Blaine Grover

2009-05-01T23:59:59.000Z

242

Subsurface mass transport affects the radioxenon signatures that are used to identify clandestine nuclear tests  

E-Print Network (OSTI)

detail. In nuclear accidents such as that in Fukushima, a high radiation dose of a few Gy can be absorbed reconstruction for the Fukushima event carried out by Garnier-Laplace et al.,1 the maxi- mum dose rates for 131 I-Seiller, K.; Hinton, T. G. Fukushima wildlife dose reconstruction signals ecological consequen- ces. Environ

Deinert, Mark

243

Report on Department of Homeland Security Sponsored Research Project at Lawrence Livermore National Laboratory on Preparation for an Improvised Nuclear Device Event  

SciTech Connect

Following the events of September 11th, a litany of imaginable horribles was trotted out before an anxious and concerned public. To date, government agencies and academics are still grappling with how to best respond to such catastrophes, and as Senator Lieberman's quote says above, now is the time to plan and prepare for such events. One of the nation's worst fears is that terrorists might detonate an improvised nuclear device (IND) in an American city. With 9/11 serving as the catalyst, the government and many NGOs have invested money into research and development of response capabilities throughout the country. Yet, there is still much to learn about how to best respond to an IND event. My summer 2008 internship at Lawrence Livermore National Laboratory afforded me the opportunity to look in depth at the preparedness process and the research that has been conducted on this issue. While at the laboratory I was tasked to collect, combine, and process research on how cities and the federal government can best prepare for the horrific prospect of an IND event. Specific projects that I was involved with were meeting reports, research reviews, and a full project report. Working directly with Brooke Buddemeier and his support team at the National Atmospheric Release Advisory Center, I was able to witness first hand, preparation for meetings with response planners to inform them of the challenges that an IND event would pose to the affected communities. In addition, I supported the Homeland Security Institute team (HSI), which was looking at IND preparation and preparing a Congressional report. I participated in meetings at which local responders expressed their concerns and contributed valuable information to the response plan. I specialized in the psycho-social aspects of an IND event and served as a technical advisor to some of the research groups. Alongside attending and supporting these meetings, I worked on an independent research project which collected information from across disciplines to outline where the state of knowledge on IND response is. In addition, the report looked at meetings that were held over the summer in various cities. The meetings were attended by both federal responders and local responders. The meetings explored issues regarding IND preparation and how to mitigate the effects of an IND detonation. Looking at the research and current preparation activity the report found that the state of knowledge in responding and communicating is a mixed bag. Some aspects of an IND attack are well understood, some are not, but much is left to synthesize. The effects of an IND would be devastating, yet much can be done to mitigate those effects through education, preparation, and research. A major gap in current knowledge is how to effectively communicate with the public before an attack. Little research on the effectiveness of public education has been done, but it is likely that educating the public about the effects of an IND and how to best protect oneself could save many lives.

A., B

2008-07-31T23:59:59.000Z

244

DOE-STD-1065-94; DOE Standard Guideline to Good Practices For Postmaintenance Testing at DOE Nuclear Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

65-94 65-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR POSTMAINTENANCE TESTING AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY 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; (423) 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. DE94014953 DOE-STD-1065-94 FOREWORD The purpose of the Guide to Good Practices for Postm aintenance T esting at DOE Nuclear Facilities is to provide contractor maintenance

245

Guideline to good practices for control and calibration of measuring and test equipment (M TE) at DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of the Guideline to Good Practices for Control and Calibration of Measuring and Test Equipment (M TE) at DOE Nuclear Facilities is to provide contractor maintenance organizations with information that may be used for the development and implementation of a rigorously controlled maintenance program directed at controlling and calibrating M TE used for maintenance tasks at DOE nuclear facilities. This document is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter II, Element 11. DOE contractors should not feel obligated to adopt all parts of this guide. Rather, they should use the information contained herein as a guide for developing an M TE program applicable to their facility.

Not Available

1993-03-01T23:59:59.000Z

246

Measurement of 37Ar to support technology for On-site Inspection under the Comprehensive Nuclear-Test-Ban Treaty  

E-Print Network (OSTI)

On-Site Inspection (OSI) is a key component of the verification regime for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Measurements of radionuclide isotopes created by an underground nuclear explosion are a valuable signature of a Treaty violation. Argon-37 is produced from neutron interaction with calcium in soil, 40Ca(n,{\\alpha})37Ar. For OSI, the 35-day half-life of 37Ar provides both high specific activity and sufficient time for completion of an inspection before decay limits sensitivity. This paper presents a low-background internal-source gas proportional counter with an 37Ar measurement sensitivity level equivalent to 45.1 mBq/SCM in whole air.

C. E. Aalseth; A. R. Day; D. A. Haas; E. W. Hoppe; B. J. Hyronimus; M. E. Keillor; E. K. Mace; J. L. Orrell; A. Seifert; V. T. Woods

2010-08-04T23:59:59.000Z

247

PERSPECTIVES OF NUCLEAR PHYSICS  

E-Print Network (OSTI)

The organizers of this meeting have asked me to present perspectives of nuclear physics. This means to identify the areas where nuclear physics will be expanding in the next future. In six chapters a short overview of these areas will be given, where I expect that nuclear physics will develop quite fast: (1) Quantum Chromodynamics and effective field theories in the confinement region. (2) Nuclear structure at the limits. (3) High energy heavy ion collisions. (4) Nuclear astrophysics. (5) Neutrino physics. (6) Test of physics beyond the standard model by rare processes. After a survey over these six points I will pick out a few topics where I will go more in details. There is no time to give for all six points detailed examples. I shall discuss the following examples of the six topics mentionned above: (1) The perturbative chiral quark model and the nucleon ?-term. (2) VAMPIR (Variation After Mean field Projection In Realistic model spaces and with realistic forces) as an example of the nuclear structure renaissance. (3) Measurement of important astrophysical nuclear reactions in the Gamow peak. (4) The solar neutrino problem. As examples for testing new physics beyond the standard model by rare processes I had prepared to speak about the measurement of the electric neutron dipole moment and of the neutrinoless double beta decay. But the time is limited and so I have to skip these points, although they are extremely interesting.

Amand Faessler

2002-01-01T23:59:59.000Z

248

Direct Test of the Time-Independence of Fundamental Nuclear Constants Using the Oklo Natural Reactor  

E-Print Network (OSTI)

[NOTE: This 1983 preprint is being uploaded to arXiv.org after the death of its author, who supported online distribution of his work. Contact info of the submitter is at http://ilya.cc .] The positions of neutron resonances have been shown to be highly sensitive to the variation of fundamental nuclear constants. The analysis of the measured isotopic shifts in the natural fossil reactor at Oklo gives the following restrictions on the possible rates of the interaction constants variation: strong ~2x10^-19 yr^-1, electromagnetic ~5x10^-18 yr^-1, weak ~10^-12 yr^-1. These limits permit to exclude all the versions of nuclear constants contemporary variation discussed in the literature. URL: http://alexonline.info >. For more recent analyses see hep-ph/9606486, hep-ph/0205206 and astro-ph/0204069 .

Alexander I. Shlyakhter

2003-07-03T23:59:59.000Z

249

INTEGRAL BENCHMARK DATA FOR NUCLEAR DATA TESTING THROUGH THE ICSBEP AND THE NEWLY ORGANIZED IRPHEP  

Science Conference Proceedings (OSTI)

The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) was last reported in a nuclear data conference at the International Conference on Nuclear Data for Science and Technology, ND-2004, in Santa Fe, New Mexico. Since that time the number and type of integral benchmarks have increased significantly. Included in the ICSBEP Handbook are criticality-alarm / shielding and fundamental physic benchmarks in addition to the traditional critical / subcritical benchmark data. Since ND 2004, a reactor physics counterpart to the ICSBEP, the International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. The IRPhEP is patterned after the ICSBEP, but focuses on other integral measurements, such as buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics measurements, reaction-rate and power distributions, nuclide compositions, and other miscellaneous-type measurements in addition to the critical configuration. The status of these two projects is discussed and selected benchmarks highlighted in this paper.

J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

2007-04-01T23:59:59.000Z

250

Reaction mechanisms in transport theories: a test of the nuclear effective interaction  

E-Print Network (OSTI)

We review recent results concerning collective excitations in neutron-rich systems and reactions between charge asymmetric systems at Fermi energies. Solving numerically self-consistent transport equations for neutrons and protons with specific initial conditions, we explore the structure of the different dipole vibrations in the $^{132}Sn$ system and investigate their dependence on the symmetry energy. We evidence the existence of a distinctive collective mode, that can be associated with the Pygmy Dipole Resonance, with an energy well below the standard Giant Dipole Resonance and isoscalar-like character, i.e. very weakly dependent on the isovector part of the nuclear effective interaction. At variance, the corresponding strength is rather sensitive to the behavior of the symmetry energy below saturation, which rules the number of excess neutrons in the nuclear surface. In reactions between charge asymmetric systems at Fermi energies, we investigate the interplay between dissipation mechanisms and isospin effects. Observables sensitive to the isospin dependent part of nuclear interaction are discussed, providing information on the symmetry energy density dependence below saturation.

M. Colonna; V. Baran; M. Di Toro; B. Frecus; Y. X. Zhang

2012-09-07T23:59:59.000Z

251

Nuclear fuels technologies: Thermally induced gallium removal system (TIGRS), fiscal year 1998 research and development test plan  

SciTech Connect

This document details the research and development (R and D) activities that will be conducted in Fiscal Year 1998 (FY98) by the Thermally Induced Gallium Removal System (TIGRS) team for the Department of Energy Office of Fissile Materials Disposition. This work is a continuation and extension of experimental activities that have been conducted in support of using weapons-derived plutonium in the fabrication of mixed-oxide (MOX) nuclear fuel for reactor-based plutonium disposition. The ultimate purpose of this work is to demonstrate adequate Thermally Induced Gallium Removal with a prototypic system. This Test Plan presents more than the FY98 R and D efforts in order to frame the Task in its entirety. To achieve the TIGRS Program objectives, R and D activities during the next two years will be focused on (1) process development leading to a prototypic TIGRS design, and (2) prototypic TIGRS design and testing leading to and including a prototypic demonstration of TIGRS operation. Both the process development and system testing efforts will consist of a series of surrogate-based cold tests and plutonium-based hot tests. Some of this testing has already occurred and will continue into FY99.

Buksa, J.J.; Butt, D.P.; Chidester, K.; DeMuth, S.F.; Havrilla, G.J.; James, C.A.; Kolman, D.G.

1997-12-24T23:59:59.000Z

252

THE TESTING OF COMMERCIALLY AVAILABLE ENGINEERING AND PLANT SCALE ANNULAR CENTRIFUGAL CONTACTORS FOR THE PROCESSING OF SPENT NUCLEAR FUEL  

Science Conference Proceedings (OSTI)

Annular centrifugal contactors are being evaluated for process scale solvent extraction operations in support of United State Advanced Fuel Cycle Initiative goals. These contactors have the potential for high stage efficiency if properly employed and optimized for the application. Commercially available centrifugal contactors are being tested at the Idaho National Laboratory to support this program. Hydraulic performance and mass transfer efficiency have been measured for portions of an advanced nuclear fuel cycle using 5-cm diameter annular centrifugal contactors. Advanced features, including low mix sleeves and clean-in-place rotors, have also been evaluated in 5-cm and 12.5-cm contactors.

Jack D. Law; David Meikrantz; Troy Garn; Nick Mann; Scott Herbst

2006-10-01T23:59:59.000Z

253

Finding the Site of the First Soviet Nuclear Test in 1949  

Science Conference Proceedings (OSTI)

Efforts by the U.S. government to detect the first Soviet atomic test began at least as early as 1946. Interception of radioactive debris from the first test was made by the Air Weather Service B-29 weather reconnaissance aircraft, which was ...

Lester Machta

1992-11-01T23:59:59.000Z

254

HALLAM NUCLEAR POWER FACILITY, PREOPERATIONAL TEST INTERIM REPORT DRY EXCESS LOADING  

SciTech Connect

A test to obtain data for use in determining the reactivlty wohh of Na in the Hallam reactor core is described. The test is designed to obtain information on the dry temperature coefficient of reactivity and to train operators. An evaluation of results is included. (J.R.D.)

Kempt, H.C.; Corcoran, W.P.

1962-02-25T23:59:59.000Z

255

Nuclear Maintenance Applications Center: Air-Operated Valve Diagnostic Testing Guide  

Science Conference Proceedings (OSTI)

This report provides information for personnel involved in the performance of air-operated valve (AOV) diagnostic testing, including the benefits of using diagnostics to understand valve health and to tie information into preventive maintenance programs. It provides insights for experienced personnel as well as basic information, guidance, and instructions for personnel assigned to perform, analyze, or purchase diagnostic test equipment.

2011-12-23T23:59:59.000Z

256

Joint EPRI-CEA Research on Small Punch Testing for Nuclear Application  

Science Conference Proceedings (OSTI)

A joint research project between EPRI and the Commissariat a l'Energie Atomique (CEA) has been under way since 1998 to compare the fracture behavior of reactor pressure vessel (RPV) materials in the transition region as tested by a subsize impact test (Charpy) and subsize specimen techniques. This report summarizes the progress made under this joint effort.

2001-12-13T23:59:59.000Z

257

Isospin distillation with radial flow: A test of the nuclear symmetry energy  

Science Conference Proceedings (OSTI)

We discuss mechanisms related to isospin transport in central collisions between neutron-rich systems at Fermi energies to gain information on the nuclear symmetry energy at and below saturation. A fully consistent study of the isospin distillation and expansion dynamics in two-component systems is presented in the framework of a stochastic transport theory. We analyze correlations between fragment observables, focusing on the study of the fragment asymmetry N/Z as a function of their kinetic energy. We find that the relation between these observables allows us to better characterize the fragmentation path and to access new information on the low-density behavior of the symmetry energy.

Colonna, M. [LNS-INFN, I-95123 Catania (Italy); Baran, V. [NIPNE-HH, Bucharest, and Bucharest University, Bucharest (Romania); Toro, M. Di [LNS-INFN, I-95123 Catania (Italy); Department of Physics and Astronomy, University of Catania, Catania (Italy); Wolter, H. H. [LNS-INFN, I-95123 Catania (Italy); Fakultaet fuer Physik, University of Munich, Garching (Germany)

2008-12-15T23:59:59.000Z

258

Test of Parity-Conserving Time-Reversal Invariance Using Polarized Neutrons and Nuclear Spin Aligned Holmium  

E-Print Network (OSTI)

A test of parity-conserving, time-reversal non-invariance (PC TRNI) has been performed in 5.9 MeV polarized neutron transmission through nuclear spin aligned holmium. The experiment searches for the T-violating five-fold correlation via a double modulation technique - flipping the neutron spin while rotating the alignment axis of the holmium. Relative cross sections for spin-up and spin-down neutrons are found to be equal to within $1.2 \\times 10^{-5}$ (80\\% confidence). This is a two order of magnitude improvement compared to traditional detailed balance studies of time reversal, and represents the most precise test of PC TRNI in a dynamical process.

P. R. Huffman; N. R. Roberson; W. S. Wilburn; C. R. Gould; D. G. Haase; C. D. Keith; B. W. Raichle; M. L. Seely; J. R. Walston

1996-05-24T23:59:59.000Z

259

Progress Letter Report on Bending Fatigue Test System Development for Spent Nuclear Fuel Vibration Integrity Study (Out-of-cell fatigue testing development - Task 2.4)  

SciTech Connect

Vibration integrity of high burn-up spent nuclear fuel in transportation remains to be a critical component of US nuclear waste management system. The structural evaluation of package for spent fuel transportation eventually will need to see if the content or spent fuel is in a subcritical condition. However, a system for testing and characterizing such spent fuel is still lacking mainly due to the complication involved with dealing radioactive specimens in a hot cell environment. Apparently, the current state-of-the-art in spent fuel research and development is quite far away from the delivery of reliable mechanical property data for the assessment of spent fuels in the transport package evaluation. Under the sponsorship of US NRC, ORNL has taken the challenge in developing a robust testing system for spent fuel in hot cell. An extensive literature survey was carried out and unique requirements of such testing system were identified. The U-frame setup has come to the top among various designs examined for reverse bending fatigue test of spent fuel rod. The U-frame has many features that deserve mentioned here: Easy to install spent fuel rod in test; Less linkages than in conventional bending test setup such as three-point or four-point bending; Target the failure mode relevant to the fracture of spent fuel rod in transportation by focusing on pure bending; The continuous calibrations and modifications resulted in the third generation (3G) U-frame testing setup. Rigid arms are split along the LBB axis at rod sample ends. For each arm, this results in a large arm body and an end piece. Mating halves of bushings were modified into two V-shaped surfaces on which linear roller bearings (LRB) are embedded. The rod specimen is installed into the test fixture through opening and closing slide end-pieces. The 3G apparently has addressed major issues of setup identified in the previous stage and been proven to be eligible to be further pursued in this project. On the other hand, the purchase of universal testing machine or Bose dual LM2 TB was completed and the testing system was delivered to ORNL in August 2012. The preliminary confirmation of the system and on-site training were given by Bose field engineer and regional manager on 8/1-8/2/2012. The calibration of Bose testing system has been performed by ORNL because the integration of ORNL setup into the Bose TestBench occurred after the installation. Major challenge with this process arose from two aspects: 1) the load control involves two load cells, and 2) U-frame setup itself is a non-standard specimen. ORNL has been able to implement the load control through Cycle Indirect along with pinning the U-frame setup. Two meetings with ORNL hot-cell group (November 2012 and January 2013) were held to discuss the potential issues with both epoxy mounting of rigid sleeve and U-frame setup. Many suggestions were provided to make the procedure friendlier to the manipulator in hot cell. Addressing of these suggestions resulted in another cycle of modifications of both vise mold and setup. The initial meeting with ORNL I&C group occurred in November 2012 with regard to the Bose cable modification and design of central panel to integrate the cables and wires. The first round of cable modification and central panel fabrication was completed in February 2012. The testing with the modified cables exhibited substantial noises and the testing system was not shown to be stable. It was believed the cross talk was responsible to the noise, and a central panel with a better grounding and shielding was highly recommended. The central panel has been re-designed and fabricated in March 2013. In the subsequent period, the ORNL made substantial effort to debug the noises with the load cell channel, and to resolve the noises and nonlinearity with RDP LVDTs related to the integration of RDP LVDTs to Bose system. At the same time, ORNL has completed the verification tests of Bose test system, including cycle tests under reversal bending in load control, bending tests under monotonic load, and cycle test

Wang, Jy-An John [ORNL; Wang, Hong [ORNL; Cox, Thomas S [ORNL; Baldwin, Charles A [ORNL; Bevard, Bruce Balkcom [ORNL

2013-08-01T23:59:59.000Z

260

FIRST SODIUM REACTOR EXPERIMENT (SRE) TEST OF HALLAM NUCLEAR POWER FACILITY (HNPF) CONTROL MATERIALS  

SciTech Connect

An experiment was conducted in the SRE to measure temperatures and neutron flux levels in and near a boron-containing simulated control rod. The data are being used to check analytical methods developed for prediction of control rod heat generation rates and maximum temperatures in this type of control rod in the Hallam Nuclear Power Facility. The maximum observed temperatures with a reactor power level of 20 Mw were 1363 deg F for a boron-- nickel alloy ring having a 0.105-in. radial clearance with the thimble and 1100 deg F for a boron -nickel alloy ring having a 0.020-in. radial clearance. The maximum temperature difference between the coolant and the control rod was 473 deg F. It is concluded that the expected greater heat generation rates in the Hallam reactor would prohibit the use of boron-containing absorber materials in a combined a him-safety rod. (auth)

Arneson, S.O.

1959-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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261

Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a US Component Testing Facility  

Science Conference Proceedings (OSTI)

The use of a fusion component testing facility to study and establish, during the ITER era, the remaining scientific and technical knowledge needed by fusion Demo is considered and described in this paper. This use aims to lest components in an integrated fusion nuclear environment, for the first time, to discover and understand the underpinning physical properties, and to develop improved components for further testing, in a time-efficient manner. It requires a design with extensive modularization and remote handling of activated components, and flexible hot-cell laboratories. It further requires reliable plasma conditions to avoid disruptions and minimize their impact, and designs to reduce the divertor heat flux to the level of ITER design. As the plasma duration is extended through the planned ITER level (similar to 10(3) s) and beyond, physical properties with increasing time constants, progressively for similar to 10(4) s, similar to 10(5) s, and similar to 10(6) s, would become accessible for testing and R&D. The longest time constants of these are likely to be of the order of a week ( 106 S). Progressive stages of research operation are envisioned in deuterium, deuterium-tritium for the ITER duration, and deuterium-tritium with increasingly longer plasma durations. The fusion neutron fluence and operational duty factor anticipated for this "scientific exploration" phase of a component test facility are estimated to be up to 1 MW-yr/m(2) and up to 10%, respectively.

Peng, Yueng Kay Martin [ORNL; Burgess, Thomas W [ORNL; Carroll, Adam J [ORNL; Neumeyer, C. L. [Princeton Plasma Physics Laboratory (PPPL); Canik, John [ORNL; Cole, Michael J [ORNL; Dorland, W. D. [University of Maryland; Fogarty, P. J. [Oak Ridge National Laboratory (ORNL); Grisham, L. [Princeton Plasma Physics Laboratory (PPPL); Hillis, Donald Lee [ORNL; Katoh, Yutai [ORNL; Korsah, Kofi [ORNL; Kotschenreuther, M. [University of Texas, Austin; LaHaye, R. [General Atomics, San Diego; Mahajan, S. [University of Texas, Austin; Majeski, R. [Princeton Plasma Physics Laboratory (PPPL); Nelson, Brad E [ORNL; Patton, Bradley D [ORNL; Rasmussen, David A [ORNL; Sabbagh, S. A. [Columbia University; Sontag, Aaron C [ORNL; Stoller, Roger E [ORNL; Tsai, C. C. [Oak Ridge National Laboratory (ORNL); Vanlanju, P. [University of Texas, Austin; Wagner, Jill C [ORNL; Yoder, III, Graydon L [ORNL

2009-08-01T23:59:59.000Z

262

The Next Generation Nuclear Plant/Advanced Gas Reactor Fuel Irradiation Experiments in the Advanced Test Reactor  

SciTech Connect

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating eight separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of at least six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006, and the second experiment (AGR-2) is currently in the design phase. The design of test trains, as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation will be discussed. In addition, the purpose and differences between the two experiments will be compared and the irradiation results to date on the first experiment will be presented.

S. Blaine Grover

2009-09-01T23:59:59.000Z

263

J. H. Scofield and D. M. Fleetwood, IEEE Transactions on Nuclear Science NS-38, 1567-77 (December 1991). PHYSICAL BASIS FOR NONDESTRUCTIVE TESTS OF MOS RADIATION HARDNESS*  

E-Print Network (OSTI)

J. H. Scofield and D. M. Fleetwood, IEEE Transactions on Nuclear Science NS-38, 1567-77 (December 1991). PHYSICAL BASIS FOR NONDESTRUCTIVE TESTS OF MOS RADIATION HARDNESS* John H. Scofield Department noise and channel mobility measurements may be useful in defining nondestructive hardness assurance test

Scofield, John H.

264

Materials for Nuclear Power: Digital Resource Center -- Articles and ...  

Science Conference Proceedings (OSTI)

... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science, Nuclear Engineering ... BOOK: Safety Related Issues of Spent Nuclear Fuel Storage ... A compilation of reports prepared by the Center for Nuclear Waste Regulatory ...

265

NUREG/CR-6695 PNNL-13375 Hydrologic Uncertainty Assessment for Decommissioning Sites: Hypothetical Test Case Applications Prepared by  

E-Print Network (OSTI)

This report uses hypothetical decommissioning test cases to illustrate an uncertainty assessment methodology for dose assessments conducted as part of decommissioning analyses for NRC-licensed facilities. This methodology was presented previously in NUREG/CR-6656. The hypothetical test case source term and scenarios are based on an actual decommissioning case and the physical setting is based on the site of a field experiment carried out for the NRC in Arizona. The emphasis in the test case was on parameter uncertainty. The analysis is limited to the hydrologic aspects of the exposure pathway involving infiltration of water at the ground surface, leaching of contaminants, and transport of contaminants through the groundwater to a point of exposure. The methodology uses generic parameter distributions based on national or regional databases for estimating

P. D. Meyer; R. Y. Taira

2001-01-01T23:59:59.000Z

266

Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1993  

Science Conference Proceedings (OSTI)

This report describes the Offsite Radiation Safety Program conducted during 1993 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory - Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ionization chambers (PICs); by biological monitoring of foodstuffs including animal tissues and food crops; and by measurement of radioactive material deposited in humans.

Chaloud, D.J; Daigler, D.M.; Davis, M.G. [and others

1996-06-01T23:59:59.000Z

267

Control of Test Conduct  

NLE Websites -- All DOE Office Websites (Extended Search)

2 Revision 1 Effective June 2008 Control of Test Conduct Prepared by Electric Transportation Applications Prepared by: Date: Garrett P....

268

Review of Test Results  

NLE Websites -- All DOE Office Websites (Extended Search)

GAC004 Revision 1 Effective June 2008 Review of Test Results Prepared by Electric Transportation Applications Prepared by: Date: Garrett...

269

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement; Volume 1, Appendix F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs  

Science Conference Proceedings (OSTI)

This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering.

NONE

1994-06-01T23:59:59.000Z

270

Characterization of Pu-contaminated soils from Nuclear Site 201 at the Nevada Test Site  

SciTech Connect

Distribution and characteristics of Pu-bearing radioactive particles throughout five soil profiles from Nuclear Site (NS) 201 were investigated. Concentrations of /sup 239/ /sup 240/Pu and /sup 241/Am decreased with depth and most of the contamination was contained in the top 5 cm except in profile 4 where it extended to 10 cm. The mean activity ratio of /sup 239/ /sup 240/Pu to /sup 241/Am and its standard error were 5.8 +- 0.3 (N=42). Most of the total radioactivity of the soils was contributed by 0.25 to 2 mm sand size fraction which comprised 20 to 50% by weight of the soils. The radioactive particles in the 0.25 to 2 mm size fraction occurred as spherical glass particles or as glass coatings on sand particles. The glass coatings had gas voids in the matrix but were not as porous as the radioactive particles from NS 219. After impact grinding the >0.25-mm size fractions for one hour, 85% of the initial activity in a NS 201 sample remained with the particles on the 0.25 mm sieve, whereas in the NS 219 sample only 10% remained. The results show that the radioactive particles from NS 201 were much more stable against the impact grinding force than those from NS 219. Therefore, the NS 201 soils would be expected to have a lower probability of producing respirable-size radioactive particles by saltation during wind erosion. 19 references, 3 figures, 3 tables.

Lee, S.Y.; Tamura, T.; Larsen, I.L.

1983-01-01T23:59:59.000Z

271

Studies of participants in nuclear tests. Final report, 1 September 1978-31 October 1984  

SciTech Connect

A study of mortality, by cause of death, was done on a cohort of 46,186 participants in one or more of five test series. The series studied were UPSHOT-KNOTHOLE (1953) and PLUMBBOB (1957) at the Nevada Test Site, and GREENHOUSE (1951), CASTLE (1954), and REDWING (1956) which were conducted at the Pacific Proving Ground at Enewetak and Bikini. The participants were traced individually by the use of Veterans Administration records. For the participants in each series, the number of deaths attributed to particular causes was compared with the number expected to occur at US cause- and age-specific mortality rates. A total of 5113 deaths from all causes was ascertained; this was 11.1% of the number of participants. The number was, however, only 83.5% of the number expected at US mortality rates. Mortality from leukemia among the 3554 participants at SMOKY - 10 deaths below age 85 - were 2.5 times the expected number. When the leukemia deaths are compared to other deaths in all six data sets, the differences among the series are not significant. No cancer other than leukemia was ascertained to have occurred in significant excess among SMOKY participants and the number of deaths from other cancers (67) was less than the number expected at population rates (83.8). The total body of evidence cannot convincingly either affirm or deny that the higher than statistically expected incidence of leukemia among SMOKY participants (or of prostate cancer among REDWING participants) is the result of radiation exposure incident to the tests. 19 refs., 27 tabs.

Robinette, C.D.; Jablon, S.; Preston, T.L.

1985-05-01T23:59:59.000Z

272

General Outline for Conducting Quality Inspections and Tests of Concrete Placement at Nuclear Facilities: Standard and Optimized for Electronic Viewing Versions  

Science Conference Proceedings (OSTI)

This field guide provides a field-deployable resource for utility professionals who are responsible for inspecting and testing concrete placements at nuclear facilities. It addresses development and submittal of concrete mixes, qualification and inspection of batching facilities, qualification of testing agencies and personnel, review of construction procedures, and development of inspection and testing plans. It also provides checklists for pre-placement inspection; concrete conveyance; placement ...

2013-05-30T23:59:59.000Z

273

Recovery Efficiency Test Project: Phase 1, Activity report. Volume 1: Site selection, drill plan preparation, drilling, logging, and coring operations  

SciTech Connect

The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

1987-04-01T23:59:59.000Z

274

16th nuclear engineering education conference on international nuclear engineering: development and planning  

SciTech Connect

Separate abstracts were prepared for the ten summaries, dealing with various energy and nuclear topics. (DLC)

1977-01-01T23:59:59.000Z

275

3He- and 4He-induced nuclear fission - a test of the transition state method  

E-Print Network (OSTI)

Fission in 3He and 4He induced reactions at excitation energies between the fission barrier and 140 MeV has been investigated. Twentythree fission excitation functions of various compound nuclei in different mass regions are shown to scale exactly according to the transition state prediction once the shell effects are accounted for. New precise measurements of excitation functions in a mass region where shell effects are very strong, allow one to test the predictions with an even higher accuracy. The fact that no deviations from the transition state method have been observed within the experimentally investigated excitation energy regime allows one to assign limits for the fission transient time. The precise measurement of fission excitation functions of neighboring isotopes enables us to experimentally estimate the first chance fission probability. Even if only first chance fission is investigated, no evidence for fission transient times larger than 30 zs can be found.

Th. Rubehn; K. X. Jing; L. G. Moretto; L. Phair; K. Tso; G. J. Wozniak

1997-04-18T23:59:59.000Z

276

Subsurface Completion Report for Amchitka Underground Nuclear Test Sites: Long Shot, Milrow, and Cannikin, Rev. No.: 1  

Science Conference Proceedings (OSTI)

Three underground nuclear tests were conducted on Amchitka Island, Alaska, in 1965, 1969, and 1971. The effects of the Long Shot, Milrow, and Cannikin tests on the environment were extensively investigated during and following the detonations, and the area continues to be monitored today. This report is intended to document the basis for the Amchitka Underground Nuclear Test Sites: Long Shot, Milrow, and Cannikin (hereafter referred to as ''Amchitka Site'') subsurface completion recommendation of No Further Remedial Action Planned with Long-Term Surveillance and Maintenance, and define the long-term surveillance and maintenance strategy for the subsurface. A number of factors were considered in evaluating and selecting this recommendation for the Amchitka Site. Historical studies and monitoring data, ongoing monitoring data, the results of groundwater modeling, and the results of an independent stakeholder-guided scientific investigation were also considered in deciding the completion action. Water sampling during and following the testing showed no indication that radionuclides were released to the near surface, or marine environment with the exception of tritium, krypton-85, and iodine-131 found in the immediate vicinity of Long Shot surface ground zero. One year after Long Shot, only tritium was detectable (Merritt and Fuller, 1977). These tritium levels, which were routinely monitored and have continued to decline since the test, are above background levels but well below the current safe drinking water standard. There are currently no feasible means to contain or remove radionuclides in or around the test cavities beneath the sites. Surface remediation was conducted in 2001. Eleven drilling mud pits associated with the Long Shot, Milrow and Cannikin sites were remediated. Ten pits were remediated by stabilizing the contaminants and constructing an impermeable cap over each pit. One pit was remediated by removing all of the contaminated mud for consolidation in another pit. In addition to the mud pits, the hot mix plant was also remediated. Ongoing monitoring data does not indicate that radionuclides are currently seeping into the marine environment. Additionally, the groundwater modeling results indicate no seepage is expected for tens to thousands of years. If seepage does occur in the future, however, the rich, diverse ecosystems around the island could be at risk, as well as people eating foods from the area. An independent science study was conducted by the Consortium for Risk Evaluation with Stakeholder Participation (CRESP) in accordance with the Amchitka Independent Science Plan (2003). The study report was published on August 1, 2005. The CRESP study states ''our geophysical and biological analyses did not find evidence of risk from radionuclides from the consumption of marine foods, nor indication of any current radionuclide contaminated migration into the marine environment from the Amchitka test shots''. The study also found evidence supporting the groundwater modeling conclusions of very slow contaminant transport (CRESP, 2005). While no further action is recommended for the subsurface of the Amchitka Site, long-term stewardship of Amchitka Island will be instituted and will continue into the future. This will include institutional controls management and enforcement, post-completion monitoring, performance of five-year reviews, public participation, and records management. Long-term stewardship will be the responsibility of the U.S. Department of Energy Office of Legacy Management. The Department of Energy is recommending completion of the investigation phase of the Amchitka Sites. The recommended remedy for the Amchitka Site is No Further Action with Long-Term Monitoring and Surveillance. The future long-term stewardship actions will be governed by a Long-Term Surveillance and Maintenance Plan. This Plan is currently being developed with input from the State, landowner, and other interested or affected stakeholders.

Echelard, Tim

2006-09-01T23:59:59.000Z

277

About underground nuclear tests, magnetometers, and (last but not least) the ionosphere  

SciTech Connect

About six to eight minutes after an underground test, an acoustic wave reaches the E and F layers of the ionosphere. Recent radiosonde experiments and propagation calculations verify that a detectable disturbance results therefrom. Next, the authors are investigating whether or not the interaction of that acoustic motion with the Earth`s magnetic field might result in a detectable magnetic disturbance at the surface. There are several interaction concepts by which they might estimate this signal: (1) the ionospheric plasma displacement interacts such that a transverse current is induced in it via v x B, that volume current may be represented as a current dipole moment, by which to estimate the magnetic field change at the Earth`s surface below; (2) the displaced free electrons bend in the Earth`s field, collectively, this cyclotron spiraling gives rise to an equivalent magnetic dipole moment; (3) the conducting ionosphere behaves as a diamagnetic layer, which drags the magnetic field with it as it moves. That might be observed downstream, at the axial intercept.

Wouters, L.F.

1978-09-25T23:59:59.000Z

278

Nuclear Medicine CT Angiography  

E-Print Network (OSTI)

Nuclear Medicine CT Angiography Stress Testing Rotation The Nuclear Medicine/CT angiography. Understand the indications for exercise treadmill testing and specific nuclear cardiology tests, safe use patient and learn the importance of physical and pharmacologic stress in nuclear cardiology 3. Interpret

Ford, James

279

Nuclear Sites Map  

NLE Websites -- All DOE Office Websites (Extended Search)

reactor operations, nuclear research, weapons disassembly, maintenance and testing, hot cell operations, nuclear material storage and processing and waste disposal. Each...

280

TEST  

Science Conference Proceedings (OSTI)

This is an abstract. TEST Lorem ipsum dolor sit amet, consectetur adipiscing elit. Cras lacinia dui et est venenatis lacinia. Vestibulum lacus dolor, adipiscing id mattis sit amet, ultricies sed purus. Nulla consectetur aliquet feugiat. Maecenas ips

Note: This page contains sample records for the topic "nuclear test prepared" 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

Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference; Sessions 1--8  

SciTech Connect

Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

1991-02-01T23:59:59.000Z

282

Nuclear Systems Technologies - Nuclear Engineering Division ...  

NLE Websites -- All DOE Office Websites (Extended Search)

Departments involved: Research & Test Reactor | Engineering Development and Applications "Decommissioning of Nuclear Facilities" training courses Argonne Decommissioning Training...

283

Review of geomechanics data from French nuclear explosions in the Hoggar granite, with some comparisons to tests in US granite  

SciTech Connect

Numerous unclassified reports on the French nuclear explosions in the Hoggar (1961-1966) were reviewed from the standpoint of geomechanics. The following aspects of the tests are summarized: spectral content of the tests compared to U.S. results; shock front positions with time; cavity radius as a function of yield, coupling, density of rock, rock shear strength, and overburden; radial pressure, tangential pressure and peak velocity as a function of distance and yield; pressure vs. time at various distances; mechanical properties of granite; scaling laws for acceleration, velocity and displacement as a function of yield and distance for all Hoggar shots; extent of tunnel damage as a function of distance and yield; time to collapse of chimney as a function of yield, or cavity radius; extent of granite crushing and disking as a function of distance and yield cavity height relation to cavity radius; faulting and jointing on the Taourirt Tan Afella massif; and influence of water content on cavity radius vs. yield. Whenever possible, these French data are compared to corresponding data obtained in the U.S. granite events Hard Hat, Shoal, and Piledriver. The following results emerge from the comparison: (1) agreement is found between the French and U.S. experience for: mechanical properties of the granites, rock damage due to the blast, and yield-scaled peak values of acceleration, velocity and displacement; and (2) lack of agreement exists for: cavity size, chminey height, and time to cavity collapse. Average spacing of rock joints also was about 5 times greater in the Hoggar.

Heuze, F.E.

1983-05-01T23:59:59.000Z

284

$?$-mass Modification in $He^3$ - a Signal of Restoration of Chiral Symmetry or Test for Nuclear Matter Models ?  

E-Print Network (OSTI)

Two recent experiments have demonstrated that the effective $\\rho$-mass in nuclear medium, as extracted from the $^3He(\\gamma, \\pi^+ \\pi^-)$ reaction, is substantially reduced. This has been advocated as an indication of partial restoration of chiral symmetry in nuclear matter. We show that even in the absence of chiral symmetry, effective mean field nuclear matter models can explain these findings quantitatively.

Abhijit Bhattacharyya; Sanjay K. Ghosh; Sibaji Raha

1999-02-23T23:59:59.000Z

285

Nuclear test experimental science  

Science Conference Proceedings (OSTI)

This report discusses research being conducted at Lawrence Livermore Laboratory under the following topics: prompt diagnostics; experimental modeling, design, and analysis; detector development; streak-camera data systems; weapons supporting research.

Struble, G.L.; Middleton, C.; Bucciarelli, G.; Carter, J.; Cherniak, J.; Donohue, M.L.; Kirvel, R.D.; MacGregor, P.; Reid, S. (eds.)

1989-01-01T23:59:59.000Z

286

Predictions for p+Pb at 5.02A TeV to test initial state nuclear shadowing at the Large Hadron Collider  

E-Print Network (OSTI)

Collinear factorized perturbative QCD model predictions are compared for $p+{\\rm Pb}$ at 5.02$A$ TeV to test nuclear shadowing of parton distribution at the Large Hadron Collider (LHC). The pseudorapidity distribution and the nuclear modification factor (NMF), $R_{p{\\rm Pb}}(y=0,p_T<20\\;{\\rm GeV}/{\\it c}) = dn_{p{\\rm Pb}} /(N_{\\rm coll}(b)dn_{pp})$, is computed within {\\small HIJING/\\=B v2.0 model}. These results are updated calculations of those presented in Ref. Phys. Rev C85, 024903 (2012).

Barnafoldi, G G; Gyulassy, M; Levai, P; Petrovici, M; Pop, V Topor

2012-01-01T23:59:59.000Z

287

Prepared by  

E-Print Network (OSTI)

adjust their physical inventory of source or special nuclear material (SNM) to document and report such activities. The reports are submitted using U.S. Department of Energy (DOE)/NRC Form 741. Licensees may need to provide additional information on some imports or exports of source or SNM. The additional information is reported using DOE/NRC Form 740M. This NUREG contains instructions for preparing these forms. Paperwork Reduction Act Statement The information collections contained in this NUREG are covered by DOE/NRC Forms 741 and 740M, which the Office of Management and Budget (OMB) approved under approval numbers 3150-0003 and 3150-0057. Public Protection Notification If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. iii NUREG/BR-0006, Rev. 7NUREG/BR-0006, Rev. 7 iv CONTENTS

C. Graves

2009-01-01T23:59:59.000Z

288

Prepared by  

E-Print Network (OSTI)

This report does not contain any information that is proprietary to Westinghouse Electric Company. The U.S. Nuclear Regulatory Commission (NRC) has also prepared a proprietary version of this report for internal distribution. In order to conform to the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, as set forth in Title 10, Section 2.790, of the Code of Federal Regulations (10 CFR 2.790), the proprietary information in the proprietary version of this document is contained within brackets and, where the proprietary information has been deleted in the non-proprietary version, only the brackets remain (the information within the brackets in the proprietary version having been deleted). The justification for claiming the information as proprietary is indicated in both versions by means of lower case letters (a) through (f), located as a superscript immediately following the brackets enclosing each bracketed item of proprietary information, or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence, as identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying the transmittal of these documents pursuant to 10 CFR 2.790(b)(1).

K. B. Welter; S. M. Bajorek; Jose Reyes; Brian Woods; John Groome; John Hopson; Eric Young; John Denoma; Kent Abel

2005-01-01T23:59:59.000Z

289

Notice of Intent to Prepare an Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center (3/13/03)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 4 Federal Register / Vol. 68, No. 49 / Thursday, March 13, 2003 / Notices Dated: March 6, 2003. Gerald A. Reynolds, Assistant Secretary for Civil Rights. [FR Doc. 03-5999 Filed 3-12-03; 8:45 am] BILLING CODE 4000-01-M DEPARTMENT OF ENERGY Notice of Intent to Prepare an Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center AGENCY: Department of Energy. ACTION: Notice of Intent. SUMMARY: The U.S. Department of Energy (DOE) and the New York State Energy Research and Development Authority (NYSERDA) are announcing their intent to prepare an Environmental Impact Statement (EIS) for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project (WVDP) and

290

Evaluation of Cavity Collapse and Surface Crater Formation at the Salut Underground Nuclear Test in U20ak, Nevada National Security Site, and the Impact of Stability of the Ground Surface  

Science Conference Proceedings (OSTI)

At the request of Jerry Sweeney, the LLNL Containment Program performed a review of nuclear test-related data for the Salut underground nuclear test in U20ak to assist in evaluating this legacy site as a test bed for application technologies for use in On-Site Inspections (OSI) under the Comprehensive Nuclear Test Ban Treaty. Review of the Salut site is complicated because the test experienced a subsurface, rather than surface, collapse. Of particular interest is the stability of the ground surface above the Salut detonation point. Proposed methods for on-site verification include radiological signatures, artifacts from nuclear testing activities, and imaging to identify alteration to the subsurface hydrogeologogy due to the nuclear detonation. Sweeney's proposal requires physical access at or near the ground surface of specific underground nuclear test locations at the Nevada Nuclear Test Site (NNSS, formerly the Nevada Test Site), and focuses on possible activities such as visual observation, multispectral measurements, and shallow, and deep geophysical surveys.

Pawloski, G A

2012-04-25T23:59:59.000Z

291

EV America Skid Test Procedure  

NLE Websites -- All DOE Office Websites (Extended Search)

6 Revision 3 Effective February 1, 2008 Braking Test Prepared by Electric Transportation Applications Prepared by: Date: Derek Peterson...

292

Performance testing and Bayesian Reliability Analysis of small diameter, high power electric heaters for the simulation of nuclear fuel rod temperatures  

E-Print Network (OSTI)

The conversion of plutonium from a nuclear weapon to nuclear reactor fuel requires an evaluation of the residual gallium as a potential corrosive material within an operating nuclear fuel element. Homogeneous trace levels of gallium may remain following conversion and have the potential to migrate along the thermal gradient within the fuel and concentrate at the cladding-fuel contact zone. A system to investigate this material transport phenomenon was constructed using small diameter (0.18 inch), indirect electric heaters to simulate the centerline temperatures of operating nuclear fuel in a pressurized water reactor. The heater was inserted into annular surrogate fuel pellets containing depleted uranium, cerium oxide and trace quantities (10 ppm) of gallium to perform an initial study of the gallium migration using non-plutonium fuels and evaluate the performance of the simulation system. Heat was removed from the operating heaters by using an innovative liquid metal heat exchanger. The heaters were of a new design and were required to operate at a nominal temperature of 1000?C and for a minimum of 5000 hours. An evaluation of the expected heater lifetime and the thermal simulation system was needed in order to justify the high expense of a proposed full test using prototypic mixed-oxide fuel (MOX) containing plutonium from converted nuclear weapons. Bayesian reliability analysis methods were used to determine the expected heater failure rate because of the expected short test duration and the small sample size. Results from the operation of the simulation system and lifetime data indicate the current heater design is capable of producing the required temperatures and thermal gradients normally found in operating nuclear fuels. However, a design weakness in the heaters resulted in an unacceptably high failure rate of the heaters. The heaters were determined to have a reliability of 0.83 % at 5000 hours of operation with a Mean Time to Failure (MTTF) of 485 hours. The current heater design would require some modification and further testing prior to beginning a full scale test using prototypic MOX fuel pellets.

O'Kelly, David Sean

2000-01-01T23:59:59.000Z

293

Reconversion of nuclear weapons  

E-Print Network (OSTI)

The nuclear predicament or nuclear option. Synopsis of three lectures : 1- The physical basis of nuclear technology. Physics of fission. Chain reaction in reactors and weapons. Fission fragments. Separration of isotopes. Radiochemistry.2- Nuclear reactors with slow and fast neutrons. Power, size, fuel and waste. Plutonium production. Dose rate, shielding and health hazard. The lessons of Chernobyl3- Nuclear weapons. Types, energy, blast and fallout. Fusion and hydrogen bombs. What to do with nuclear weapons when you cannot use them? Testing. Nonmilittary use. Can we get rid of the nuclear weapon? Nuclear proliferation. Is there a nuclear future?

Kapitza, Sergei P

1993-01-01T23:59:59.000Z

294

Nuclear methods in environmental and energy research  

SciTech Connect

The topics considered in the seven sessions were nuclear methods in atmospheric research; nuclear and atomic methodology; nuclear methods in tracer applications; energy exploration, production, and utilization; nuclear methods in environmental monitoring; nuclear methods in water research; and nuclear methods in biological research. Individual abstracts were prepared for each paper. (JSR)

Vogt, J.R. (ed.)

1977-01-01T23:59:59.000Z

295

Weak reactions with light nuclei - 6He beta-decay as a test case for the nuclear weak current  

E-Print Network (OSTI)

We present a microscopic calculation of the 6He beta-decay into the ground state of 6Li. To this end we use the impulse approximation to describe the nuclear weak current. The ground state wave functions are obtained from the solution of the nuclear 6-body problem. The nucleonnucleon interaction is described via the J-matrix inverse scattering potential (JISP), and the nuclear problem is solved using the hyperspherical-harmonics approach. This approach results in numerical accuracy of about 2 per mil in the transition matrix element. Bearing in mind that the contribution of meson-exchange currents to the transition matrix element is about 5%, these results pave the way for accurate estimation of their effect.

Doron Gazit; Sergey Vaintraub; Nir Barnea

2009-01-18T23:59:59.000Z

296

Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors (9) System Outline and Endurance Test of Low-Pressure Steam Injectors  

Science Conference Proceedings (OSTI)

A Steam Injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater. This provides SI with capability to serve also as a direct-contact feedwater heater that heats up feedwater by using extracted steam from the turbine. We are developing technology for 'Innovative Simplified Nuclear Power Plants' in order to further improve the economy and safety of nuclear power plants. Our technology development aims to significantly simplify equipment and reduce physical quantities by applying 'High-Efficiency SI', which are applicable to a wide range of operation regimes beyond the performance and applicable range of existing SIs and enables unprecedented multistage and parallel operation, to the low-pressure feedwater heaters and Emergency Core Cooling Systems (ECCS) of nuclear power plants, as well as achieve high inherent safety to prevent severe accidents by keeping the core covered with water (a Severe Accident-Free Concept). The innovative-simplified nuclear power plant consists of a simplified feedwater heating system, a passive core injection system and a passive containment cooling system. This report describes the results of the endurance and performance tests of low-pressure SIs for feedwater heaters with Jet-deaerator and core injection system. A part of this report are fruits of research which is carried out by Tokyo Electric Power Company (TEPCO), Toshiba, and 7 Universities in Japan, funded from the Ministry of Economy, Trade and Industry (METI) of Japan as the national public research-funded program. (authors)

Shuichi Ohmori; Michitsugu Mori; Shoji Goto [Tokyo Electric Power Company (Japan); Tadashi Narabayashi [Hokkaido University, Kita-ku, Sapporo (Japan); Chikako Iwaki; Yutaka Asanuma [Toshiba Corporation (Japan)

2006-07-01T23:59:59.000Z

297

The Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada, was the site for a 12-kiloton-ton nuclear test  

Office of Legacy Management (LM)

NV/13609-53 NV/13609-53 Development of a Groundwater Management Model for the Project Shoal Area prepared by Gregg Lamorey, Scott Bassett, Rina Schumer, Douglas P. Boyle, Greg Pohll, and Jenny Chapman submitted to Nevada Site Office National Nuclear Security Administration U.S. Department of Energy Las Vegas, Nevada September 2006 Publication No. 45223 Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. Available for sale to the public, in paper, from: U.S. Department of Commerce

298

The Office of Nuclear Detonation Detection (NDD) | National Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

of Nuclear Detonations: Develops and builds space sensors for the nation's operational nuclear test treaty monitoring and Integrated Threat WarningAttack Assessment...

299

Implementation of IAEA /1/INT/054 Project in Nuclear Analytical Techniques Group of Argentina: Current State  

Science Conference Proceedings (OSTI)

This paper presents the implementation of the training received through the IAEA Project 'Preparation of Reference Materials and Organization of Proficiency Tests Rounds' in the Nuclear Analytical (NAT) Group of CNEA. Special emphasis is done on those activities related to the first Proficiency Test being carried out by the NAT Group.

Sara, Resnizky; Rita, Pla [Nuclear Analytical Techniques Group, Argentine National Atomic Energy Commission (CNEA), Av. Del Libertador 8250 (1429) Buenos Aires (Argentina); Alba, Zaretzky [Ionizing Radiation Dosimetry Group(CRRD), Argentine National Atomic Energy Commission (CNEA), Av. Del Libertador 8250, 1429 Buenos Aires (Argentina)

2008-08-14T23:59:59.000Z

300

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Dose Commitments from Nuclear Tests carried out beforeDose Commitments from Nuclear Tests carried out before 1968,of the dose from nuclear weapons test fallout. As indicated

Nero, A.V.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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

Preparing for Decommissioning: The Oyster Creek Experience  

Science Conference Proceedings (OSTI)

This report chronicles the process of preparing GPU Nuclear's Oyster Creek Nuclear Generating Station for early retirement and decommissioning. The Oyster Creek experience has great relevance to the nuclear industry, as future decommissioning projects will benefit from the comprehensive preplanning work performed there.

2000-06-06T23:59:59.000Z

302

Preparing Your  

NLE Websites -- All DOE Office Websites (Extended Search)

of third party vendors, enter "international shipping and shopping carts" or similar search terms into an Internet search engine. 52 Preparing Your Business for Global...

303

Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters  

Science Conference Proceedings (OSTI)

Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

Konzek, G.J.

1983-07-01T23:59:59.000Z

304

A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants  

SciTech Connect

This report describes an engineering-scale, mock UF6 feed and withdrawal (F&W) system, its operation, and its intended uses. This system has been assembled to provide a test bed for evaluating and demonstrating new methodologies that can be used in remote, unattended, continuous monitoring of nuclear material process operations. These measures are being investigated to provide independent inspectors improved assurance that operations are being conducted within declared parameters, and to increase the overall effectiveness of safeguarding nuclear material. Testing applicable technologies on a mock F&W system, which uses water as a surrogate for UF6, enables thorough and cost-effective investigation of hardware, software, and operational strategies before their direct installation in an industrial nuclear material processing environment. Electronic scales used for continuous load-cell monitoring also are described as part of the basic mock F&W system description. Continuous monitoring components on the mock F&W system are linked to a data aggregation computer by a local network, which also is depicted. Data collection and storage systems are described only briefly in this report. The mock UF{sub 6} F&W system is economical to operate. It uses a simple process involving only a surge tank between feed tanks and product and withdrawal (or waste) tanks. The system uses water as the transfer fluid, thereby avoiding the use of hazardous UF{sub 6}. The system is not tethered to an operating industrial process involving nuclear materials, thereby allowing scenarios (e.g., material diversion) that cannot be conducted otherwise. These features facilitate conducting experiments that yield meaningful results with a minimum of expenditure and quick turnaround time. Technologies demonstrated on the engineering-scale system lead to field trials (described briefly in this report) for determining implementation issues and performance of the monitoring technologies under plant operating conditions. The ultimate use of technologies tested on the engineering-scale test bed is to work with safeguards agencies to install them in operating plants (e.g., enrichment and fuel processing plants), thereby promoting new safeguards measures with minimal impact to operating plants. In addition, this system is useful in identifying features for new plants that can be incorporated as part of 'safeguards by design,' in which load cells and other monitoring technologies are specified to provide outputs for automated monitoring and inspector evaluation.

Krichinsky, Alan M [ORNL; Bates, Bruce E [ORNL; Chesser, Joel B [ORNL; Koo, Sinsze [ORNL; Whitaker, J Michael [ORNL

2009-12-01T23:59:59.000Z

305

Plutonium Pits | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

nuclear weapons without underground nuclear testing; weapons go through a surveillance process, where they are regularly taken apart, examined, and tests run on their components....

306

Biological effects of underground nuclear testing on marine organisms. I. Review of documented shock effects, discussion of mechanisms of damage, and predictions of Amchitka test effects  

SciTech Connect

From conference on the environmental effects of explosives and explosions; White Oak, Maryland, USA (30 May 1973). The potential mechanisms of biological damage to fish resulting from a nuclear-induced shock wave appear to involve mechanical damage from bottom acceleration and rockspall; the synergistic effect of compression to decompression producing the mechanical expansion of gas spaces within the organism; effects of cavitation; and possibly the alteration of blood constituents. The indirect effects of the shock wave should also be considered in a truly ecological approach. Loss of fish or other marine organisms may reduce food resources for other species and place an unusual stress upon the community's food web and increased predation created by the influx of a formerly minor constituent may also be a real consideration. The determinants of biological damage involve the anatomical morphology, the ecological characteristics of the various members of the fish community, and the physical characteristics of the environment as produced by the introduced shock wave. (auth)

Simenstad, C.A.

1973-01-01T23:59:59.000Z

307

Independent Verification and Validation Of SAPHIRE 8 System Test Plan Project Number: N6423 U.S. Nuclear Regulatory Commission  

Science Conference Proceedings (OSTI)

The purpose of the Independent Verification and Validation (IV&V) role in the evaluation of the SAPHIRE System Test Plan is to assess the approach to be taken for intended testing activities associated with the SAPHIRE software product. The IV&V team began this endeavor after the software engineering and software development of SAPHIRE had already been in production.

Kent Norris

2010-02-01T23:59:59.000Z

308

"Order Module--DOE-STD-3009-94, PREPARATION GUIDE FOR U.S. DEPARTMENT OF  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

"Order Module--DOE-STD-3009-94, PREPARATION GUIDE FOR U.S. "Order Module--DOE-STD-3009-94, PREPARATION GUIDE FOR U.S. DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY "Order Module--DOE-STD-3009-94, PREPARATION GUIDE FOR U.S. DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY "The familiar level of this module is divided into three sections. The first section is an introduction to DOE-STD-3009-94. In the second section, we will introduce the 17 chapters of a documented safety analysis (DSA). The third section covers the evaluation guideline that appears in appendices 1-5 of the standard. We have provided several examples and practices throughout the module to help familiarize you with the material. The practice will also help prepare you for the criterion test." DOE Order Self Study Modules - DOE-STD-3009-94, Preparation Guide for U.S.

309

Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility  

Science Conference Proceedings (OSTI)

Volume 4 contains the following appendices: nuclear reactors at educational institutions in the United States; data sheets for nuclear reactors at educational institutions in the United States(operational reactors and shut-down reactors); supplemental data for Fort St. Vrain spent fuel; supplemental data for Peach Bottom 1 spent fuel; and supplemental data for Fast Flux Test Facility.

Not Available

1992-07-01T23:59:59.000Z

310

Medical Radioisotope | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Medical Medical Radioisotope SHARE Medical Radioisotope Staff members preparing Ac-225 in glove boxes for shipment to hospitals to support radiotherapy cancer clinical trials in multiple locations around the world. ORNL's Medical Radioisotope Program is focused on the development of improved reactor production and processing methods to provide medical radioisotopes, the development of new radionuclide generator systems, the design and evaluation of new radiopharmaceuticals for applications in nuclear medicine and oncology, and association with Medical Cooperative Programs throughout the world for further preclinical testing and clinical evaluation of agents developed at ORNL. The collective resources of ORNL, including access to the enriched stable isotope inventory, a High Flux

311

Prepared by  

E-Print Network (OSTI)

This safety evaluation report documents the Nuclear Regulatory Commission’s (NRC’s) review of Duke Energy Corporation’s (Duke’s) application to renew the operating licenses for McGuire

R. Franovich

2003-01-01T23:59:59.000Z

312

Assessment of the impacts of spent fuel disassembly alternatives on the Nuclear Waste Isolation System. [Preparing and packaging spent fuel assemblies for geologic disposal  

SciTech Connect

The objective of this report was to evaluate four possible alternative methods of preparing and packaging spent fuel assemblies for geologic disposal against the Reference Process of unmodified spent fuel. The four alternative processes were: (1) End fitting removal, (2) Fission gas venting and resealing, (3) Fuel bundle disassembly and close packing of fuel pins, and (4) Fuel shearing and immobilization. Systems analysis was used to develop a basis of comparison of the alternatives. Conceptual processes and facility layouts were devised for each of the alternatives, based on technology deemed feasible for the purpose. Assessments were made of 15 principal attributes from the technical, operational, safety/risk, and economic considerations related to each of the alternatives, including both the surface packaging and underground repository operations. Specific attributes of the alternative processes were evaluated by assigning a number for each that expressed its merit relative to the corresponding attribute of the Reference Process. Each alternative process was then ranked by summing the numbers for attributes in each of the four assessment areas and collectively. Fuel bundle disassembly and close packing of fuel pins was ranked the preferred method of disposal of spent fuel. 63 references, 46 figures, 46 tables.

Not Available

1984-07-01T23:59:59.000Z

313

Microsoft Word - Final Nuclear Materials Management and Safeguards...  

National Nuclear Security Administration (NNSA)

and Safeguards System (NMMSS) Users Guide-Rev. 2.0 Prepared by: Department of Energy National Nuclear Security Administration Nuclear Materials Integration - NA-73 April...

314

Specimen Preparation  

Science Conference Proceedings (OSTI)

Table 1   Standard preparation conditions for structural ceramics (e.g., Si 3 N 4 , AlN, SiC and Al 2 O 3 ), semiautomatic

315

Deputy Secretary Poneman's Remarks at the Nuclear Energy Assembly...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy Assembly - As Prepared for Delivery Deputy Secretary Poneman's Remarks at the Nuclear Energy Assembly - As Prepared for Delivery May 11, 2011 - 6:01pm Addthis Deputy...

316

Field Testing of Behavioral Barriers for Fish Exclusion at Cooling-Water Intake Systems, Ontario Hydro Pickering Nuclear Generating Station  

Science Conference Proceedings (OSTI)

Depending on site-specific considerations, behavioral barriers such as sound and lights may be more effective, less expensive, and more environmentally suitable for excluding fish from power plant intakes than physical barriers. Specifically, field tests at Ontario Hydro's Pickering station on Lake Ontario indicated that behavioral barriers excluded alewife, an important prey species in the Great Lakes.

1989-03-15T23:59:59.000Z

317

McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: The national organization of test research and training reactors  

SciTech Connect

This year's TRTR conference is being hosted by the McClellan Nuclear Radiation Center. The conference will be held at the Red Lion Hotel in Sacramento, CA. The conference dates are scheduled for October 11-14, 1994. Deadlines for sponsorship commitment and papers have not been set, but are forthcoming. The newly remodeled Red Lion Hotel provides up-to-date conference facilities and one of the most desirable locations for dining, shopping and entertainment in the Sacramento area. While attendees are busy with the conference activities, a spouses program will be available. Although the agenda has not been set, the Sacramento area offers outings to San Francisco, Pier 39, Ghirardelli Square (famous for their chocolate), and a chance to discover 'El Dorado' in the gold country. Not to forget our own bit of history with visits to 'Old Sacramento and Old Folsom', where antiquities abound, to the world renown train museum and incredible eating establishments. (author)

Kiger, Kevin M. [SWI-ALC/TIR, 5335 Price Ave., McClellan Air Force Base Sacramento, CA 95652-2504 (United States)

1994-07-01T23:59:59.000Z

318

EIS-0402: Notice of Intent to Prepare an Environmental Impact Statement |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2: Notice of Intent to Prepare an Environmental Impact 2: Notice of Intent to Prepare an Environmental Impact Statement EIS-0402: Notice of Intent to Prepare an Environmental Impact Statement Remediation of Area IV of the Santa Susana Field Laboratory The Department of Energy (DOE) announces its intent to prepare an Environmental Impact Statement (EIS) and conduct public scoping meetings under the National Environmental Policy Act (NEPA) for remediation of Area IV of the Santa Susana Field Laboratory (SSFL Area IV). The SSFL, approximately 2,852 acres in the hills between Chatsworth and Simi Valley, CA, was developed as a remote site to test rocket engines and conduct nuclear research. Notice of Intent To Prepare an Environmental Impact Statement for Remediation of Area IV of the Santa Susana Field Laboratory and Conduct

319

EIS-0310: Notice of Intent to Prepare a Programmatic Environmental Impact  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10: Notice of Intent to Prepare a Programmatic Environmental 10: Notice of Intent to Prepare a Programmatic Environmental Impact Statement EIS-0310: Notice of Intent to Prepare a Programmatic Environmental Impact Statement Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the United States, Including the Role of the Fast Flux Test Facility The Secretary of Energy recently announced DOE's intent to prepare a programmatic environmental impact statement (PEIS) on accomplishing these new missions through the proposed enhancement of the existing infrastructure, including the possible role of the Fast Flux Test Facility (FFTF), located at DOE's Hanford Site near Richland, Washington. This PEIS will analyze the potential environmental impacts of alternative ways to meet the projected irradiation needs for the next 35 years.

320

EIS-0310: Notice of Intent to Prepare a Programmatic Environmental Impact  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10: Notice of Intent to Prepare a Programmatic Environmental 10: Notice of Intent to Prepare a Programmatic Environmental Impact Statement EIS-0310: Notice of Intent to Prepare a Programmatic Environmental Impact Statement Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the United States, Including the Role of the Fast Flux Test Facility The Secretary of Energy recently announced DOE's intent to prepare a programmatic environmental impact statement (PEIS) on accomplishing these new missions through the proposed enhancement of the existing infrastructure, including the possible role of the Fast Flux Test Facility (FFTF), located at DOE's Hanford Site near Richland, Washington. This PEIS will analyze the potential environmental impacts of alternative ways to meet the projected irradiation needs for the next 35 years.

Note: This page contains sample records for the topic "nuclear test prepared" 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

Reflective Cracking Study: Initial Construction, Phase 1 HVS Testing, and Overlay Construction  

E-Print Network (OSTI)

a relationship between the nuclear test and laboratory test= 0.77 Air-Void Content, CT308 or Nuclear Test (%) Caltrans308 Nuclear Test Linear (Nuclear Test) Air-Void Content,

Bejarano, Manuel O.; Jones, David; Morton, Bruce S.; Scheffy, Clark

2008-01-01T23:59:59.000Z

322

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic...

323

Target preparations and thickness measurements  

SciTech Connect

A wide variety of isotope target preparative methods have been used, including rolling of metals, vapor deposition, electrodeposition, chemical vapor deposition, and sputtering, to obtain thin and thick films of most elements or compounds of elements in the Periodic Table. Most thin films prepared for use in self-supported form as well as those deposited on substrates require thickness measurement (atom count and distribution) and/or thickness uniformity determination before being used in nuclear research. Preparative methods are described together with thickness and uniformity determination procedures applicable to samples being prepared (in situ) and to completed samples. Only nondestructive methods are considered applicable to target samples prepared by the ORNL Solid State Division, Isotope Research Materials Laboratory. Thickness or areal density measurements of sufficient sophistication to yield errors of less than +-1 percent have been achieved with regularity. A statistical analysis procedure is applied which avoids error caused by balance zero-point drift in direct weight measurement methods. (auth)

Adair, H.L.; Kobisk, E.H.

1975-01-01T23:59:59.000Z

324

VARIATIONS IN RADON-222 IN SOIL AND GROUND WATER AT THE NEVADA TEST SITE  

E-Print Network (OSTI)

Table 1 Underground nuclear tests which were studied forunderground nuclear explosions, in "Nevada Test Site," E. B.Underground nuclear explosions at the Nevada Test Site (NTS)

Wollenberg, H.

2010-01-01T23:59:59.000Z

325

Notice of Intent to Prepare a Programmatic Environmental Impact...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Notice of Intent To Prepare a Programmatic Environmental Impact Statement for the Global Nuclear Energy Partnership AGENCY: Department of Energy. ACTION: Notice of Intent....

326

EIS-0225: Amended Notice of Intent to Prepare an Environmental...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Notice of Intent to Prepare an Environmental Impact Statement Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components The Department of Energy...

327

EA-1592: Notice of Intent to Prepare an Environmental Assessment...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and Infrastructure for the Non-Nuclear Production Activities Conducted at the Kansas City Plant Notice of Intent to Prepare an Environmental Assessment for the Transformation...

328

Standard Review Plan Preparation for Facility Operations Strengthening...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities August 2013 2 OFFICE OF ENVIRONMENTAL MANAGEMENT Standard Review Plan (SRP) Preparation...

329

Nevada Test Site Environmental Report 2008  

Science Conference Proceedings (OSTI)

The Nevada Test Site Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

Cathy A. Wills

2009-09-01T23:59:59.000Z

330

Nevada Test Site Environmental Report 2008 Summary  

SciTech Connect

The Nevada Test Site Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

Cathy A. Wills

2009-09-01T23:59:59.000Z

331

Prepared by  

E-Print Network (OSTI)

As part of its redesign of the materials licensing process, the United States Nuclear Regulatory Commission (NRC) consolidated and updated numerous guidance documents into a single comprehensive repository, as described in NUREG-1539, “Methodology and Findings of the NRC’s Materials Licensing Process Redesign, ” dated April 1996, and draft NUREG-1541, “Process and Design for Consolidating and Updating Materials Licensing Guidance, ” dated

D. B. Howe; M. Beardsley; S. R. Bakhsh

2008-01-01T23:59:59.000Z

332

Prepared by  

E-Print Network (OSTI)

As part of its redesign of the materials licensing process, the United States Nuclear Regulatory Commission (NRC) is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539, “Methodology and Findings of the NRC’s Materials Licensing Process Redesign, ” dated April 1996, and draft NUREG-1541,

Licenses Of Broad Scope; James P. Dwyer; Orysia Masnyk Baily; James R. Mullauer; Torre M. Taylor

1999-01-01T23:59:59.000Z

333

Process for preparing fluorine-18  

DOE Patents (OSTI)

An improved process for preparation of fluorine-18 by a neon (deuteron, alpha particle) fluorine-18 nuclear reaction in a non-reactive enclosed reaction zone wherein a ultrapure product is recovered by heating the reaction zone to a high temperature and removing the product with an inert gas.

Winchell, Harry S. (Lafayette, CA); Wells, Dale K. (Martinez, CA); Lamb, James F. (Albany, CA); Beaudry, Samuel B. (Walnut Creek, CA)

1976-09-21T23:59:59.000Z

334

LWRS ATR Irradiation Testing Readiness Status  

SciTech Connect

The Light Water Reactor Sustainability (LWRS) Program was established by the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) to develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors. The LWRS Program is divided into four R&D Pathways: (1) Materials Aging and Degradation; (2) Advanced Light Water Reactor Nuclear Fuels; (3) Advanced Instrumentation, Information and Control Systems; and (4) Risk-Informed Safety Margin Characterization. This report describes an irradiation testing readiness analysis in preparation of LWRS experiments for irradiation testing at the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) under Pathway (2). The focus of the Advanced LWR Nuclear Fuels Pathway is to improve the scientific knowledge basis for understanding and predicting fundamental performance of advanced nuclear fuel and cladding in nuclear power plants during both nominal and off-nominal conditions. This information will be applied in the design and development of high-performance, high burn-up fuels with improved safety, cladding integrity, and improved nuclear fuel cycle economics

Kristine Barrett

2012-09-01T23:59:59.000Z

335

The design, construction, and testing of a nuclear fuel rod thermal simulation system to study gallium/Zircaloy interactions  

E-Print Network (OSTI)

The presence of gallium in weapons grade plutonium has raised many questions concerning its use in light water reactor (LWR) fuel rods. The biggest concern is that the gallium will migrate down the thermal gradient in the fuel rod and deposit on the inner surface of the clad, which could cause it to fail. In order to study these effects, a fuel rod thermal simulation system (FRTSS) has been developed to recreate the shape and magnitude of the temperature profile in pressurized water reactor (PWR) fuel rods. The system uses electrically heated simulated fuel rods inside of a large, natural convection heat exchanger that uses lead-bismuth eutectic (LBE) (45 <% Pb, 55 <% Bi) as the working fluid. The simulated rods consist of small diameter electric heaters, annular pellets of depleted uranium/cerium oxide doped with approximately 10 ppm of gallium, a small helium filled gap, and generic Zircaloy IV cladding. The system is controlled through a computer-based data acquisition system that is used to record temperature data and operate the various pieces of equipment. A simple mathematical model was used to design the heat exchanger and predict the temperature profile within the simulated rods. Results from system tests indicated that the mathematical model was capable of predicting heater surface temperatures within 6.15% +/- 1.82% and clad outer surface temperatures within 1.91% +/- 4.46%. In addition, the tests also revealed that the system could accurately simulate the temperature profiles of operating PWR fuel rods. Consequently, the FRTSS provides a safe and effective means for studying gallium migration in the fuel pellets and its subsequent interactions with Zircaloy IV.

Allison, Christopher Curtis

1999-01-01T23:59:59.000Z

336

Report Preparation  

NLE Websites -- All DOE Office Websites (Extended Search)

been completed (as described in ETA-GAC002, "Control of Test Conduct") prior to the report being formally issued. 4.2 All necessary test documentation has been completed,...

337

World nuclear outlook 1995  

Science Conference Proceedings (OSTI)

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

NONE

1995-09-29T23:59:59.000Z

338

World nuclear outlook 1994  

Science Conference Proceedings (OSTI)

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2010 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for three different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

NONE

1994-12-01T23:59:59.000Z

339

Nuclear Nonproliferation  

Science Conference Proceedings (OSTI)

With an explosion equivalent of about 20kT of TNT, the Trinity test was the first demonstration of a nuclear weapon. Conducted on July 16, 1945 in Alamogordo, NM this site is now a Registered National Historic Landmark. The concept and applicability of nuclear power was demonstrated on December 20, 1951 with the Experimental Breeder Reactor Number One (EBR-1) lit four light bulbs. This reactor is now a Registered National Historic Landmark, located near Arco, ID. From that moment forward it had been clearly demonstrated that nuclear energy has both peaceful and military applications and that the civilian and military fuel cycles can overlap. For the more than fifty years since the Atoms for Peace program, a key objective of nuclear policy has been to enable the wider peaceful use of nuclear energy while preventing the spread of nuclear weapons. Volumes have been written on the impact of these two actions on the world by advocates and critics; pundits and practioners; politicians and technologists. The nations of the world have woven together a delicate balance of treaties, agreements, frameworks and handshakes that are representative of the timeframe in which they were constructed and how they have evolved in time. Collectively these vehicles attempt to keep political will, nuclear materials and technology in check. This paper captures only the briefest abstract of the more significant aspects on the Nonproliferation Regime. Of particular relevance to this discussion is the special nonproliferation sensitivity associated with the uranium isotope separation and spent fuel reprocessing aspects of the nuclear fuel cycle.

Atkins-Duffin, C E

2008-12-10T23:59:59.000Z

340

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

The National Nuclear Security Administration Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Test...

Note: This page contains sample records for the topic "nuclear test prepared" 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

Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

The National Nuclear Security Administration Reports Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Test and...

342

Summary of Construction Activities and Results from Six Initial Accelerated Pavement Tests Conducted on Asphalt Concrete Pavement Section for Modified-Binder Overlay  

E-Print Network (OSTI)

a relationship between nuclear test and laboratory test air-Caltrans 308 or Nuclear Test, % AV(Nuclear) = 0.90AV(T-166)R2 = 0.77 Caltrans 308 Nuclear Test Linear (Nuclear Test)

Bejarano, Manuel O.; Morton, Bruce S.; Scheffy, Clark

2005-01-01T23:59:59.000Z

343

Nuclear and Particle Physics, Astrophysics and Cosmology : T...  

NLE Websites -- All DOE Office Websites (Extended Search)

applied and basic science, nuclear many-body theory, nuclear reaction theory, fission, nuclear data evaluation, processing and validation testing for applications that include...

344

Pig shipping container test sequence  

SciTech Connect

This test plan outlines testing of the integrity of the pig shipping container. It is divided into four sections: (1) drop test requirements; (2) test preparations; (3) perform drop test; and (4) post-test examination.

Adkins, H.E. Jr.

1995-01-13T23:59:59.000Z

345

Prepared Remarks  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Prepared Prepared Remarks of Brian Forshaw Connecticut Municipal Electric Energy Cooperative At U.S. DOE Workshop on Transmission Congestion Hartford, Connecticut July 9,2008 The Connecticut Municipal Electric Energy Cooperative was created by the publicly-owned electric systems in the State of Connecticut to enable the municipal systems to provide electric service to their customers at the lowest reasonable cost. Currently, CMEEC provides full requirements wholesale electric service to the State's eight public power systems as well as the Mohegan Tribal Utility Authority. As Director of Energy Markets, I am responsible for strategic planning activities and analysis of the impacts that wholesale markets will have on the municipal electric utilities. My responsibilities also include representing CMEEC in the ISO-NE stakeholder process, including the ISO-NE technical committees.

346

Radiation doses for Marshall Islands Atolls Affected by U.S. Nuclear Testing:All Exposure Pathways, Remedial Measures, and Environmental Loss of 137Cs  

SciTech Connect

The United States conducted 24 nuclear tests at Bikini Atoll with a total yield of 76.8 Megatons (MT). The Castle series produced about 60% of this total and included the Bravo test that was the primary source of contamination of Bikini Island and Rongelap and Utrok Atolls. One of three aerial drops missed the atoll and the second test of the Crossroads series, the Baker test, was an underwater detonation. Of the rest, 17 were on barges on water and 3 were on platforms on an island; they produced most of the contamination of islands at the atoll. There were 42 tests conducted at Enewetak Atoll with a total yield of 31.7 MT (Simon and Robison, 1997; UNSCEAR, 2000). Of these tests, 18 were on a barge over wateror reef, 7 were surface shots, 2 aerial drops, 2 under water detonations, and 13 tower shots on either land or reef. All produced some contamination of various atoll islands. Rongelap Atoll received radioactive fallout as a result of the Bravo test on March 1, 1954 that was part of the Castle series of tests. This deposition was the result of the Bravo test producing a yield of 15 MT, about a factor of three to four greater than the predicted yield that resulted in vaporization of more coral reef and island than expected and in the debris-cloud reaching a much higher altitude than anticipated. High-altitude winds were to the east at the time of detonation and carried the debris-cloud toward Rongelap Atoll. Utrok Atoll also received fallout from the Bravo test but at much lower air and ground-level concentrations than at Rongelap atoll. Other atolls received Bravo fallout at levels below that of Utrok [other common spellings of this island and atoll (Simon, et al., 2009)]. To avoid confusion in reading other literature, this atoll and island are spelled in a variety of ways (Utrik, Utirik, Uterik or Utrok). Dose assessments for Bikini Island at Bikini Atoll (Robison et al., 1997), Enjebi Island at Enewetak Atoll (Robison et al., 1987), Rongelap Island at Rongelap Atoll (Robison et al., 1994; Simon et al., 1997), and Utrok Island at Utrok Atoll (Robison, et al., 1999) indicate that about 95-99% of the total estimated dose to people who may return to live at the atolls today (Utrok Island is populated) is the result of exposure to {sup 137}Cs. External gamma exposure from {sup 137}Cs in the soil accounts for about 10 to 15% of the total dose and {sup 137}Cs ingested during consumption of local food crops such as drinking coconut meat and fluid (Cocos nucifera L.), copra meat and milk, Pandanus fruit, and breadfruit accounts for about 85 to 90%. The other 1 to 2% of the estimated dose is from {sup 90}Sr, {sup 239+240}Pu, and {sup 241}Am. The {sup 90}Sr exposure is primarily through the food chain while the exposure to {sup 239+240}Pu, and {sup 241}Am is primarily via the inhalation pathway as a result of breathing re-suspended soil particles.

Robison, W L; Hamilton, T F

2009-04-20T23:59:59.000Z

347

Testing to evaluate the suitability of waste forms developed for electrometallurgically treated spent sodium-bonded nuclear fuel for disposal in the Yucca Mountain reporsitory.  

Science Conference Proceedings (OSTI)

The results of laboratory testing and modeling activities conducted to support the development of waste forms to immobilize wastes generated during the electrometallurgical treatment of spent sodium-bonded nuclear fuel and their qualification for disposal in the federal high-level radioactive waste repository are summarized in this report. Tests and analyses were conducted to address issues related to the chemical, physical, and radiological properties of the waste forms relevant to qualification. These include the effects of composition and thermal treatments on the phase stability, radiation effects, and methods for monitoring product consistency. Other tests were conducted to characterize the degradation and radionuclide release behaviors of the ceramic waste form (CWF) used to immobilize waste salt and the metallic waste form (MWF) used to immobilize metallic wastes and to develop models for calculating the release of radionuclides over long times under repository-relevant conditions. Most radionuclides are contained in the binder glass phase of the CWF and in the intermetallic phase of the MWF. The release of radionuclides from the CWF is controlled by the dissolution rate of the binder glass, which can be tracked using the same degradation model that is used for high-level radioactive waste (HLW) glass. Model parameters measured for the aqueous dissolution of the binder glass are used to model the release of radionuclides from a CWF under all water-contact conditions. The release of radionuclides from the MWF is element-specific, but the release of U occurs the fastest under most test conditions. The fastest released constituent was used to represent all radionuclides in model development. An empirical aqueous degradation model was developed to describe the dependence of the radionuclide release rate from a MWF on time, pH, temperature, and the Cl{sup -} concentration. The models for radionuclide release from the CWF and MWF are both bounded by the HLW glass degradation model developed for use in repository licensing, and HLW glass can be used as a surrogate for both CWF and MWF in performance assessment calculations. Test results indicate that the radionuclide release from CWF and MWF is adequately described by other relevant performance assessment models, such as the models for the solution chemistries in breached waste packages, dissolved concentration limits, and the formation of radionuclide-bearing colloids.

Ebert, W. E.

2006-01-31T23:59:59.000Z

348

TEST TEST TEST  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSA/EA-1375 NNSA/EA-1375 Environmental Assessment for Construction and Operation of a New Office Building and Related Structures within TA-3 at Los Alamos National Laboratory, Los Alamos, New Mexico July 26, 2001 Department of Energy National Nuclear Security Administration Los Alamos Area Office Environmental Assessment for Proposed Construction and Operation of a New Office Building and Related Structures NNSA/LAAO July 26,, 2001 iii Contents Acronyms and Terms .................................................................................................................. vi Executive Summary ..................................................................................................................... ix 1.0 Purpose and Need

349

test02  

Gasoline and Diesel Fuel Update (EIA)

2Q) 2Q) Distribution Category UC-950 Quarterly Coal Report April-June 1996 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. Contacts This publication was prepared by Paulette Young under the direction of Noel C. Balthasar, Chief, Coal Data Branch, Coal and Electric Data and Renewables Division, Office of Coal, Nuclear, Electric and Alter- nate Fuels. Specific information about the

350

test02  

Gasoline and Diesel Fuel Update (EIA)

3Q) 3Q) Distribution Category UC-950 Quarterly Coal Report July-September 1996 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. Contacts This publication was prepared by Paulette Young under the direction of Noel C. Balthasar, Chief, Coal Data Branch, Coal and Electric Data and Renewables Division, Office of Coal, Nuclear, Electric and Alter- nate Fuels. Specific information about

351

Nuclear data for nuclear transmutation  

Science Conference Proceedings (OSTI)

Current status on nuclear data for the study of nuclear transmutation of radioactive wastes is reviewed

Hideo Harada

2009-01-01T23:59:59.000Z

352

Countdown on the Comprehensive Test Ban  

E-Print Network (OSTI)

to test new designs for nuclear weapons frequency = app. 10-B) to test effects of nuclear weapons frequency = app. twice2. What states have nuclear weapons? Admitted United States

Joeck, Neil

1986-01-01T23:59:59.000Z

353

Full-scale hot cell test of an acoustic sensor dedicated to measurement of the internal gas pressure and composition of a LWR nuclear fuel rod  

SciTech Connect

A full-scale hot cell test of the internal gas pressure and composition measurement by an acoustic sensor was carried on successfully between 2008 and 2010 on irradiated fuel rods in the LECA-STAR facility at Cadarache Centre. The acoustic sensor has been specially designed in order to provide a nondestructive technique to easily carry out the measurement of the internal gas pressure and gas composition of a LWR nuclear fuel rod. This sensor has been achieved in 2007 and is now covered by an international patent. The first positive result, concerning the device behaviour, is that the sensor-operating characteristics have not been altered by a two-year exposure in the hot cell ambient. We performed the gas characterisation contained in irradiated fuel rods. The acoustic method accuracy is now {+-}5 bars on the pressure measurement result and {+-}0.3% on the evaluated gas composition. The results of the acoustic method were compared to puncture results. Another significant conclusion is that the efficiency of the acoustic method is not altered by the irradiation time, and possible modification of the cladding properties. These results make it possible to demonstrate the feasibility of the technique on irradiated fuel rods. The transducer and the associated methodology are now operational. (authors)

Ferrandis, J. Y.; Rosenkrantz, E.; Leveque, G. [CNRS - Univ. Montpellier 2, Southern Electronic Inst., UMR 5214, F-34095 Montpellier (France); Baron, D. [EDF, R and D, F-77250 Moret sur Loing (France); Segura, J. C. [EDF, SEPTEN, F-69628 Villeurbanne (France); Cecilia, G.; Provitina, O. [CEA - Nuclear Energy Direction DEN - Fuel Studies Dept. - Cadarache, F-13108 Saint-Paul-Lez-Durance (France)

2011-07-01T23:59:59.000Z

354

Experiments to investigate direct containment heating phenomena with scaled models of the Zion Nuclear Power Plant in the Surtsey Test Facility  

SciTech Connect

The Surtsey Facility at Sandia National Laboratories (SNL) is used to perform scaled experiments that simulate hypothetical high-pressure melt ejection (HPME) accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effect of specific phenomena associated with direct containment heating (DCH) on the containment load, such as the effect of physical scale, prototypic subcompartment structures, water in the cavity, and hydrogen generation and combustion. In the Integral Effects Test (IET) series, 1:10 linear scale models of the Zion NPP structures were constructed in the Surtsey vessel. The RPV was modeled with a steel pressure vessel that had a hemispherical bottom head, which had a 4-cm hole in the bottom head that simulated the final ablated hole that would be formed by ejection of an instrument guide tube in a severe NPP accident. Iron/alumina/chromium thermite was used to simulate molten corium that would accumulate on the bottom head of an actual RPV. The chemically reactive melt simulant was ejected by high-pressure steam from the RPV model into the scaled reactor cavity. Debris was then entrained through the instrument tunnel into the subcompartment structures and the upper dome of the simulated reactor containment building. The results of the IET experiments are given in this report.

Allen, M.D.; Pilch, M.M.; Blanchat, T.K.; Griffith, R.O. [Sandia National Labs., Albuquerque, NM (United States); Nichols, R.T. [Ktech Corp., Albuquerque, NM (United States)

1994-05-01T23:59:59.000Z

355

Prepared by  

E-Print Network (OSTI)

As part of its redesign of the materials licensing process, the United States Nuclear Regulatory Commission (NRC) is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539, “Methodology and Findings of NRC’s Materials Licensing Process Redesign, ” dated April 1996, and draft NUREG-1541, “Process and Design for Consolidating and Updating Materials Licensing Guidance, ” dated April 1996. NUREG-1556, Vol. 12, “Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Possession Licenses for Manufacturing and Distribution, ” dated December 2000, is the twelfth program-specific guidance developed for the new process and is intended for use by applicants, licensees, and NRC staff, and will also be available to Agreement States. This document combines and updates the guidance found in: (1) Regulatory Guide 10.7, “Guide for

Distribution; D. J. Collins; C. F. Gill; A. S. Kirkwood; L. Manning Iii; E. H. Reber; M. E. Schwartz; R. E. Zelac

2000-01-01T23:59:59.000Z

356

Prepared by:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference therein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed therein do not necessarily state or reflect those of the United States Government

Thermoelectric Plant Technologies; Phil Dipietro; Kristin Gerdes; Christopher Nichols

2008-01-01T23:59:59.000Z

357

Prepared by:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference therein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed therein do not necessarily state or reflect those of the United States Government or any agency thereof. Beluga Coal Gasification Feasibility Study

Brent Sheets; Robert Chaney

2006-01-01T23:59:59.000Z

358

Prepared for  

E-Print Network (OSTI)

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. This effort is based on the continuation of work initiated under a collaborative “National Laboratory-University-industrial Three-party Program ” namely:

R. W. Goles; G. A. Whyatt; R. A. Merrill; D. K. Seiler; C. J. Freeman; D. A. Lamar; G. B. Josephson; R. W. Goles; G. A. Whyatt; R. A. Merrill; D. K. Seiler; C. J. Freeman; D. A. Lamar; G. B. Josephson

1998-01-01T23:59:59.000Z

359

Prepared by  

E-Print Network (OSTI)

over additional byproduct material. This new byproduct material now also includes naturally occurring materials, such as discrete sources of Radium-226, and accelerator-produced radioactive materials (NARM). This revision of NUREG-1556, Vol. 13, adds guidance needed to license commercial radiopharmacies as a result of the regulatory changes made by the EPAct and the NARM rule, “Requirements for Expanded Definition of Byproduct Material.” This guidance document contains information that is intended to assist applicants for commercial radiopharmacy licenses in preparing their license applications. In particular, it describes the type of information needed to complete NRC Form 313, “Application for Materials License. ” This document both describes the methods acceptable to NRC license reviewers in implementing the regulations and the techniques used by the reviewers in evaluating the application to determine if the proposed activities are acceptable for licensing purposes. Paperwork Reduction Act Statement

Commercial Radiopharmacy Licenses; D. E. White; J. F. Katanic; D. B. Howe

2007-01-01T23:59:59.000Z

360

Prepared by:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, subcontractors, or affiliated partners makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States government or any agency thereof. Available electronically at

Philip Kerrigan; In Paper; Philip Kerrigan

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear test prepared" 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

Second Line of Defense, Megaports Initiative, Operational Testing and Evaluation Plan, Port of Lazaro Cardenas, Mexico  

Science Conference Proceedings (OSTI)

The purpose of the Operational Testing and Evaluation (OT&E) phases of the project is to prepare for turnover of the Megaports System supplied by U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA)—located at the Export Lanes of the Port of Lazaro Cardenas, Mexico—to the Government of Mexico (GOM).

Hughes, Jamie D.

2012-05-30T23:59:59.000Z

362

WSDOT Test Method T 127 Preparation of Leachate Sample for Testing Toxicity of HECP Effluents 1. Scope This test method outlines the procedure for collecting leachate from a HECP sample. 2. References 2.1 EPA-821-R-02-012 Methods for Measuring Acute Toxic  

E-Print Network (OSTI)

3.1 Lay cheesecloth over clean topsoil 3.2 Apply the HECP to the cheesecloth at the following coverage: 3.2.1 HECP Long-Term or Moderate-Term Mulch 3,500 lbs per acre in two lifts with no more than 2000 # per acre in any one lift. 3.2.2 HECP Short-Term Mulch 2000 # per acre minimum, or manufacturer’s recommended rate may be used. 3.3 Allow material to cure for 48 hours 3.4 Pull cheesecloth up with mat of HECP, brush off any soil 3.5 Cut HECP into squares and provide 1.02 pounds of HECP to the laboratory. 4. Preparation of the Leachate (done by the laboratory) 4.1 Allow hydromulch product to soak in water for one hour 4.2 Remove hydromulch sheet from water 4.3 Filter water through a 60 micron filter – water may be pre-filtered through a 35 mesh and then a 120 mesh before using the 230 mesh/63 micron filter. Note: Leachate not immediately used for testing should be stored at 4 ° C in the dark until

unknown authors

2012-01-01T23:59:59.000Z

363

RW Prepared  

Office of Legacy Management (LM)

r tz r tz s /r;1 RW Prepared by Oak Ridge Associated Un iversities Prepared for Division of Remedial Action Projects U.S. Department of Energy C O M P R E H E N S I V E R A D I O L O G I C A L S U R V E Y O F F - S I T E P R O P E R T Y B N I A G A R A F A L L S S T O R A G E S I T E L E W I S T O N , N E W Y O R K J . D . B E R G E R R a d i o l o g i c a l S i t e A s s e s s m e n t p r o g r a m Manpower Education, Research, and Training Division FINAL REPORT M a y 1 9 8 4 COMPREEENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY B NIAGARA FAI"LS STORAGE SITE LE"I{ISTON, NE}I YoRK u. s. F o r m e r l y U t i l i z e d P r e p a r e d f o r Department of EnergY as Dart of the S i t e s - - R e m e d i a l A c t i o n P r o g r a u J . D . B e r g e r P r o j e c t J. Burden* R . D . C o n d r a J . S . E p l e r * P . l { . F r a m e l,l . O. Eelton R . C . G o s s l e e S t a f f t { . L . S n i t h * T . J . S o w e l l ' L . B . T a u s * C. F . Weaver B . S . Z a c h a r e k R a d i o l o g i c a l Manpower Educati-on, Oak Ridge O a k R

364

Prepared by  

E-Print Network (OSTI)

FRAPTRAN to model steady-state and transient fuel behavior, respectively, in regulatory analysis. In this document, material property correlations for oxide fuels and cladding materials are presented and discussed. Comparisons are made between the material property correlations used in the most recent versions of the codes, FRAPCON-3.4 and FRAPTRAN 1.4. Comparisons are also made with MATPRO, which is a compilation of material property correlations with an extensive history of use with various fuel performance and severe accident codes. In addition to model-to-model comparisons, model-to-data comparisons and source codes for the FRAPCON-3.4 and FRAPTRAN 1.4 correlations are provided. iii ivForeword The U.S. Nuclear Regulatory Commission uses the computer codes FRAPCON and FRAPTRAN to model steady-state and transient fuel behavior, respectively, in regulatory analysis. To effectively model fuel behavior, material property correlations must be used for a wide range of operating conditions (e.g., temperature and burnup). In this sense, a “material property ” is a physical characteristic of the material whose quantitative value is necessary in the analysis process.

W. G. Luscher; K. J. Geelhood

2010-01-01T23:59:59.000Z

365

Prepared for  

E-Print Network (OSTI)

This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. In situ reheat is an alternative to traditional gas turbine reheat design in which fuel is fed through airfoils rather than in a bulky discrete combustor separating HP and LP turbines. The goals are to achieve increased power output and/or efficiency without higher emissions. In this program the scientific basis for achieving burnout with low emissions has been explored.

D. M. Bachovchin; R. A. Newby; Alafaya Trail; Charles Alsup

2004-01-01T23:59:59.000Z

366

Prepared by:  

E-Print Network (OSTI)

This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor the Regents of the University of California, nor any of their employees, makes any warranty, express or implied, or assumes any legal responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by its trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or the Regents of the University of California. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof or the Regents of the University of California. Cover images: Upper left: offshore wind turbine, source: Large-Scale Offshore Wind Power in the United States,

F. Alexander (lanl; M. Anitescu (anl; D. Brown (lbnl; S. Mehrotra (northwestern; A. Pinar (snl; K. Willcox (mit

2011-01-01T23:59:59.000Z

367

Prepared for:  

E-Print Network (OSTI)

Important Disclaimer: The sole purpose of this document and associated services performed by CSIRO is to provide scientific knowledge to the South Australian Government. Work has been carried out in accordance with the scope of services identified in the agreement dated 22 October 2003, between South Australian Government through the EPA (‘the Client’) and the Commonwealth Scientific and Industrial Research Organisation (CSIRO). This document provides a review of environmental impacts of the in-situ acid leach uranium mining process. The material presented in this document has been derived from information supplied to CSIRO by the Client and from consultation with stakeholders and research conducted by CSIRO and other agencies and consultants. The passage of time, manifestation of latent conditions or impact of future events may require further exploration and re-evaluation of the findings, observations, conclusions, and recommendations expressed in this document. This document has been prepared on behalf of and for the exclusive use of the Client, and is subject to and issued in conjunction with the provisions of the agreement between CSIRO and the Client. CSIRO accepts no liability or responsibility whatsoever for or in respect of any use of or reliance upon this document by any third party.

Graham Taylor; Vic Farrington; Peter Woods; Robert Ring; Robert Molloy; Graham Taylor; Vic Farrington; Peter Woods; Robert Ring; Robert Molloy; Mr Peter Dolan; Adelaide Sa

2004-01-01T23:59:59.000Z

368

Prepared for:  

E-Print Network (OSTI)

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. This report presents and discusses results from the project “Fate of Mercury in Synthetic Gypsum Used for Wallboard Production, ” performed at five different full-scale commercial wallboard plants. Synthetic gypsum produced by wet flue gas desulfurization (FGD) systems on coal-fired power plants is commonly used in the manufacture of wallboard. This practice has

Jessica Sanderson; Gary M. Blythe; Mandi Richardson; Charles Miller

2008-01-01T23:59:59.000Z

369

Prepared By:  

E-Print Network (OSTI)

Team (VSCPT) since the last publication in 2004. Much has happened in Vermont schools, and in schools throughout the country, to warrant the production of a second edition of the Crisis Guide. School leaders and emergency responders have learned a great deal from planning, simulating and responding to real-life school emergencies over the past four years. The Crisis Team has incorporated this new learning within the updated Crisis Guide. The Crisis Guide contains new incident response forms for severe weather, infectious disease, power outages and other hazards that schools need to address in their safety plans. It includes information and an appendix full of useful assessments, ideas and references that the Crisis Team believes will make school response plans more focused, easier to implement and effective. The guidelines are meant to bring school leaders and emergency responders together to plan for school emergencies. In reviewing the past four years, one fact is obvious, school emergencies will happen. The question is, will your school and community be prepared to minimize property damage, reduce injuries and hopefully save lives. This work is too important to ignore. The Vermont School Crisis Planning Team’s work was crucial prior to and following the school shooting in Essex Town. Understanding that “It Can Happen Here”, school and community

unknown authors

2008-01-01T23:59:59.000Z

370

Prepared for:  

E-Print Network (OSTI)

report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, nor any of its contractors, subcontractors, nor their employees makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe upon privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States government or any other agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States government or any agency thereof. ARC-2007-D2540-032-04 In Situ Remediation and Stabilization Technologies for Mercury in Clay Soils The present study includes innovative in situ remediation technologies for the treatment and/or stabilization of mercury contaminated soils. It presents four green alternatives for the treatment

Elsa Cabrejo (doe Fellow; Doe Em; Oak Ridge Office

2010-01-01T23:59:59.000Z

371

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel ... nuclear reactors, generation, spent fuel. Total Energy. Comprehensive data summaries, comparisons, analysis, and projections ...

372

Nuclear power and nuclear weapons  

SciTech Connect

The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described.

Vaughen, V.C.A.

1983-01-01T23:59:59.000Z

373

Testing of T-odd, P-even interactions by nonpolarized neutron transmission through a nonpolarized nuclear target placed into electric field  

E-Print Network (OSTI)

A new possibility for the study of time-reversal violation is described. It consists in measurement of nonpolarized neutron transmission through nonpolarized nuclear target placed into electric field

V. G. Baryshevsky

2003-12-01T23:59:59.000Z

374

Historical Photographs: Nevada Test Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Nevada Test Site Small Image 1. A nuclear reactor sitting on a test cell pad prior to preliminary tests at the Nevada Test Site (circa 1968). This Phoebus 2 design was part of...

375

Introduction to Nuclear Engineering Introduction to Nuclear Engineering  

E-Print Network (OSTI)

Cardiopulmonary Resuscitation CSA Canadian Standards Association D&D Decontamination and Decommissioning DC, dc Association NNSA National Nuclear Security Administration #12;NRTL Nationally Recognized Testing Laboratory

Corley, Bill

376

State Nuclear Profiles 2010  

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

State Nuclear Profiles 2010 State Nuclear Profiles 2010 April 2012 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. U.S. Energy Information Administration | State Nuclear Profiles 2010 i Contacts This report was prepared by the staff of the Renewables and Uranium Statistics Team, Office of Electricity,

377

Related Resources - Nuclear Data Program, Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

378

Publications: Other Resources - Nuclear Data Program - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

379

Publications 2005 - Nuclear Data Program - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

380

Publications 2003 - Nuclear Data Program - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

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they are not comprehensive nor are they the most current set.
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to obtain the most current and comprehensive results.


381

Contacts - Nuclear Data Program, Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

382

Publications 2001 - Nuclear Data Program - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

383

Publications 2004 - Nuclear Data Program - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

384

Publications 2009 - Nuclear Data Program - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

385

Nuclear Criticality Safety: Current Activities - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

386

Nuclear Criticality Safety - Nuclear Engineering Division (Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

387

Nuclear Systems Analysis - Nuclear Engineering Division (Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

388

Publications 2011 - Nuclear Data Program - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

389

Nuclear & Particle Physics Directorate  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear & Particle Physics Program Advisory Committee Meeting 21-22 June 2010 Agenda Submitted Proposals STAR Beam Use Proposal PHENIX Beam Use Proposal LoI: Feasibility Test of...

390

Nuclear Facilities Production Facilities  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration under contract DE-AC04-94AL85000. Sand 2011-4582P. ENERGY U.S. DEPARTMENT OF Gamma Irradiation Facility (GIF) The GIF provides test cells for...

391

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

392

Capabilities listed by Department: Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Executive Bio Research & Test Reactor Advanced Reactor Development Decontamination and Decommissioning Heat Transfer and fluid Mechanics International Nuclear Safety Reactor...

393

Accelerated Materials Evaluation for Nuclear Application Utilizing ...  

Science Conference Proceedings (OSTI)

Jul 15, 2013... of accelerated nuclear materials testing for fission and fusion reactors. Presentations combining experiment with theory, modeling and ...

394

INFORMATION INTEGRATION IN CONTROL ROOMS AND TECHNICAL OFFICES IN NUCLEAR POWER PLANTS  

E-Print Network (OSTI)

Information integration in control rooms and technical offices in nuclear power plants Report prepared within the framework of the

unknown authors

2001-01-01T23:59:59.000Z

395

Contact Us | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

The National Nuclear Security Administration Contact Us Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Test...

396

Argonne Chemical Sciences & Engineering - People - Nuclear and...  

NLE Websites -- All DOE Office Websites (Extended Search)

fax 630972-4456, e-mail: ebert@anl.gov Ph.D., Chemistry, Northwestern University Nuclear waste material formulation, testing, and modeling Test method development and...

397

National Nuclear Security Administration Overview  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1, 2011 - 1, 2011 - Page 1 National Transportation Stakeholders Forum Denver, Colorado May 11, 2011 Ahmad Al-Daouk Manager, National Security Department (NSD) National Nuclear Security Administration (NNSA) Service Center - Albuquerque, NM May 11, 2011 - Page 2 National Transportation Stakeholders Forum (NTSF) * Introduction * NNSA Certifying Official Role * Offsite Source Recovery Project * Waste Shipments * Nuclear Materials Management Planning * Summary May 11, 2011 - Page 3 NNSA Plays a Critical Role: Ensuring our Nation's Security * Maintaining the safety, security and effectiveness of the nuclear weapons stockpile without nuclear testing * Reducing the global danger from the proliferation of nuclear weapons and materials * Provide safe and effective nuclear propulsion for the

398

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

been restricted core. Nuclear tests are not scheduled untilnuclear NRC, the non-nuclear tests are proceedingInstitute test reactor - megawatts - megawatts - Nuclear

Nero, A.V.

2010-01-01T23:59:59.000Z

399

Nuclear Reactions  

NLE Websites -- All DOE Office Websites (Extended Search)

Reactions Nuclear reactions and nuclear scattering are used to measure the properties of nuclei. Reactions that exchange energy or nucleons can be used to measure the energies of...

400

Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE))

Nuclear Safety information site that provides assistance and resources to field elements in implementation of requirements and resolving nuclear safety, facility safety, and quality assurance issues.

Note: This page contains sample records for the topic "nuclear test prepared" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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401

Nuclear Materials  

Science Conference Proceedings (OSTI)

Materials and Fuels for the Current and Advanced Nuclear Reactors III ... response of oxide ceramics for nuclear applications through experiment, theory, and ...

402

Chemical processing in geothermal nuclear chimney  

DOE Patents (OSTI)

A closed rubble filled nuclear chimney is provided in a subterranean geothermal formation by detonation of a nuclear explosive device therein, with reagent input and product output conduits connecting the chimney cavity with appropriate surface facilities. Such facilities will usually comprise reagent preparation, product recovery and recycle facilities. Proccsses are then conducted in the nuclear chimney which processes are facilitated by temperature, pressure, catalytic and other conditions existent or which are otherwise provided in the nuclear chimney. (auth)

Krikorian, O.H.

1973-10-01T23:59:59.000Z

403

Nuclear power plant construction activity, 1988  

SciTech Connect

Nuclear Power Plant Construction Activity 1988 presents cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1988. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors.

1989-06-14T23:59:59.000Z

404

Summary of nuclear fuel reprocessing activities around the world  

SciTech Connect

This review of international practices for nuclear fuel reprocessing was prepared to provide a nontechnical summary of the current status of nuclear fuel reprocessing activities around the world. The sources of information are widely varied.

Mellinger, P.J.; Harmon, K.M.; Lakey, L.T.

1984-11-01T23:59:59.000Z

405

Coronary Disease in Emergency Department Chest Pain Patients with Recent Negative Stress Testing  

E-Print Network (OSTI)

only stress tests or nuclear stress tests was available. Theon record, so some nuclear stress tests and ECG-only studiesor nuclear imaging. Official stress test reports provided at

Walker, Jonathan; Galuska, Michael; Vega, David

2010-01-01T23:59:59.000Z

406

Nuclear Matter and Nuclear Dynamics  

E-Print Network (OSTI)

Highlights on the recent research activity, carried out by the Italian Community involved in the "Nuclear Matter and Nuclear Dynamics" field, will be presented.

M Colonna

2009-02-26T23:59:59.000Z

407

FINAL (PNNL-20432) Nuclear Nonproliferation and Arms Control Primer  

E-Print Network (OSTI)

.g., North Korea, Pakistan). Fissile materials, nuclear reactors, reprocessing and enrichment technologyFINAL (PNNL-20432) 1 Nuclear Nonproliferation and Arms Control Primer Prepared for the Blue Ribbon Commission on America's Nuclear Future Although the list of U.S. nuclear nonproliferation and arms control

408

EIS-0387: Notice of Intent to Prepare a Site-Wide Environmental...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Notice of Intent to Prepare a Site-Wide Environmental Impact Statement Y-12 National Security Complex The National Nuclear Security Administration (NNSA) announces its intent...

409

RADIOACTIVE FALLOUT FROM NUCLEAR EXPLOSIONS  

SciTech Connect

A nontechnical description of the mechanisms of local and world-wide fall-out from nuclear explosions is given. The relative importance of local fall-out in a nuclear war is discussed. The effects upon man of world-wide fall-out from past nuclear testing is discussed. It is pointed out that doses to man frcm testing are quite small when compared to the natural radiation background. (auth)

Parker, E.N.

1960-03-23T23:59:59.000Z

410

from Savannah River Nuclear Solutions, LLC NEWS SRNS Education...  

NLE Websites -- All DOE Office Websites (Extended Search)

the CSRA AIKEN, S.C. (August 23, 2012) - As another school year begins, Savannah River Nuclear Solutions, LLC Education Outreach Programs (EOP) prepares for another year of...

411

International Programs | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Programs | National Nuclear Security Administration Programs | 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 The National Nuclear Security Administration International Programs Home > About Us > Our Programs > Emergency Response > International Programs International Programs NNSA prepares for nuclear and radiological emergencies across the globe.

412

Atomic Energy Commission Explores Peaceful Uses of Nuclear Explosions...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Explosions As part of the Plowshare program seeking to develop peaceful uses for nuclear explosives, the Atomic Energy Commission conducts the Sedan test at the Nevada...

413

THE NUCLEAR SURFACE D. F. JACKSON  

E-Print Network (OSTI)

in calculations of more fundamental properties or in analyses of other data; (ii) to test theories of the nuclearTHE NUCLEAR SURFACE D. F. JACKSON Dept. of Physics, University of Surrey, Guildford, U.K. Abstract. -- Nuclear scattering and reactions which give information on the nuclear surface are described

Paris-Sud XI, Université de

414

Fusion Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research...

415

Dual Axis Radiographic Hydrodynamic Test Facility  

NLE Websites -- All DOE Office Websites (Extended Search)

DARHT Facility: A critical component of stockpile stewardship DARHT Facility: A critical component of stockpile stewardship A new research frontier awaits! Our door is open and we thrive on mutually beneficial partnerships, collaborations that drive innovations and new technologies. April 12, 2012 Dominic Tafoya and Dave Honaberger prepare a refurbished DARHT (Dual Axis Radiographic Hydrotest Facility) 2nd axis accelerator cell for magnetic axis alignment measurements. Contact Group Leader Terry Priestley (505) 665-1330 Email Deputy Group Leader Tim Ferris (505) 665-2179 Email Hydrotests are critical in assessing nuclear weapons in nation's stockpile Dual Axis Radiographic Hydrodynamic Test facility 4:17 How DARHT Works The weapons programs at Los Alamos have one principal mission: ensure the safety, security, and effectiveness of nuclear weapons in our nation's

416

Test Automation Test Automation  

E-Print Network (OSTI)

Test Automation Test Automation Mohammad Mousavi Eindhoven University of Technology, The Netherlands Software Testing 2013 Mousavi: Test Automation #12;Test Automation Outline Test Automation Mousavi: Test Automation #12;Test Automation Why? Challenges of Manual Testing Test-case design: Choosing inputs

Mousavi, Mohammad

417

Guidebook for preparing players' handbooks  

SciTech Connect

This Addendum to the Guidebook for Preparing Players' Handbooks contains several documents that can be inserted into handbooks for future test exercises. Descriptions of these documents are provided in Section 4 of the Guidebook. While the documents are general enough to be included in handbooks with little or no editing, it is recommended the handbook preparers review the documents to determine whether the language is appropriate for a specific future exercise. Some of the documents refer to specific sections or tab numbers which may be inappropriate if future handbooks are organized differently from past handbooks.

Not Available

1989-09-01T23:59:59.000Z

418

Nuclear Analytical Chemistry Portal  

Science Conference Proceedings (OSTI)

NIST Home > Nuclear Analytical Chemistry Portal. Nuclear Analytical Chemistry Portal. ... see all Nuclear Analytical Chemistry news ... ...

2010-08-02T23:59:59.000Z

419

Low Temperature Waste Immobilization Testing Vol. I  

SciTech Connect

The Pacific Northwest National Laboratory (PNNL) is evaluating low-temperature technologies to immobilize mixed radioactive and hazardous waste. Three waste forms—alkali-aluminosilicate hydroceramic cement, “Ceramicrete” phosphate-bonded ceramic, and “DuraLith” alkali-aluminosilicate geopolymer—were selected through a competitive solicitation for fabrication and characterization of waste-form properties. The three contractors prepared their respective waste forms using simulants of a Hanford secondary waste and Idaho sodium bearing waste provided by PNNL and characterized their waste forms with respect to the Toxicity Characteristic Leaching Procedure (TCLP) and compressive strength. The contractors sent specimens to PNNL, and PNNL then conducted durability (American National Standards Institute/American Nuclear Society [ANSI/ANS] 16.1 Leachability Index [LI] and modified Product Consistency Test [PCT]) and compressive strength testing (both irradiated and as-received samples). This report presents the results of these characterization tests.

Russell, Renee L.; Schweiger, Michael J.; Westsik, Joseph H.; Hrma, Pavel R.; Smith, D. E.; Gallegos, Autumn B.; Telander, Monty R.; Pitman, Stan G.

2006-09-14T23:59:59.000Z

420

Emergency Management Limited Scope Performance Test Inspectors Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Emergency Management Emergency Management Oversight (HS-63) Emergency Management Limited Scope Performance Test Inspectors Guide March 2008 Emergency Management Performance Test Inspectors Guide Preface i Preface As part of an effort to enhance the appraisal process, the Office of Independent Oversight and the Office of Emergency Management Oversight (HS-63) have prepared a series of documents that collectively provide comprehensive guidance and tools for the evaluation of emergency management programs across the Department of Energy /National Nuclear Security Administration (DOE/NNSA) complex. The Independent Oversight Appraisal Process Protocols describe the philosophy, scope, and general procedures applicable to all independent oversight appraisal activities. The HS-63 Emergency

Note: This page contains sample records for the topic "nuclear test prepared" from the National Library of EnergyBeta (NLEBeta).
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421

Countdown on the Comprehensive Test Ban  

E-Print Network (OSTI)

Africa India Pakistan 3. Where are nuclear tests conducted?Pakistan, and any other would-be proliferator refrain from continuing or beginning a nuclearand Pakistan). But an agreement to stop testing nuclear

Joeck, Neil

1986-01-01T23:59:59.000Z

422

Future of Nuclear Data for Nuclear Astrophysics  

Science Conference Proceedings (OSTI)

Nuclear astrophysics is an exciting growth area in nuclear science. Because of the enormous nuclear data needs of this field

Michael S. Smith

2005-01-01T23:59:59.000Z

423

Countering Nuclear Terrorism | National Nuclear Security Administratio...  

NLE Websites -- All DOE Office Websites (Extended Search)

Countering Nuclear Terrorism | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

424

Nuclear Detonation Detection | National Nuclear Security Administratio...  

National Nuclear Security Administration (NNSA)

Nuclear Nonproliferation Program Offices > Office of Nonproliferation Research & Development > Nuclear Detonation Detection Nuclear Detonation Detection Develop, Demonstrate, and...

425

Chernobyl Nuclear Accident | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

Chernobyl Nuclear Accident | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

426

Nuclear Material Management Abstract  

Science Conference Proceedings (OSTI)

Nevada Test Site (NTS) has transitioned from its historical and critical role of weapons testing to another critical role for the nation. This new role focuses on being a integral element in solving the multiple challenges facing the National Nuclear Security Administration (NNSA) with nuclear material management. NTS is positioned to be a solution for other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to consolidate and modernize the production complex . With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through disposition and consolidation. This includes moving material from other sites to NTS. State of the art nuclear material management and control practices at NTS are essential for NTS to ensure that assigned activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS activities and challenges will be addressed.

Jesse C. Schreiber

2007-07-10T23:59:59.000Z

427

Coupled thermohydromechanical analysis of a heater test in unsaturated clay and fractured rock at Kamaishi Mine  

E-Print Network (OSTI)

Instrumentation. Power reactor and nuclear fiel developmentexperiment area. Power reactor and nuclear fbel developmentHydraulic tests. Power reactor and nuclear fiel development

Rutqvist, J.

2011-01-01T23:59:59.000Z

428

Nuclear Security Conference 2010 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Security Conference 2010 Nuclear Security Conference 2010 Nuclear Security Conference 2010 April 14, 2010 - 12:00am Addthis The Role of the Private Sector in Securing Nuclear Materials U.S. Secretary of Energy Steven Chu Wednesday, April 14, 2010 Secretary Steven Chu spoke this morning at the Nuclear Security Conference 2010: the Role of the Private Sector in Securing Nuclear Materials. Below are his remarks as prepared for delivery: I would like to thank the Nuclear Energy Institute for hosting this important conference on the role of the private sector in securing nuclear materials. I would also like to thank all of you for your participation today. Your industry lies at the intersection of two of the most pressing issues of our time: the energy challenge and the threat of nuclear proliferation.

429

Nuclear Security Conference 2010 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Security Conference 2010 Nuclear Security Conference 2010 Nuclear Security Conference 2010 April 14, 2010 - 12:00am Addthis The Role of the Private Sector in Securing Nuclear Materials U.S. Secretary of Energy Steven Chu Wednesday, April 14, 2010 Secretary Steven Chu spoke this morning at the Nuclear Security Conference 2010: the Role of the Private Sector in Securing Nuclear Materials. Below are his remarks as prepared for delivery: I would like to thank the Nuclear Energy Institute for hosting this important conference on the role of the private sector in securing nuclear materials. I would also like to thank all of you for your participation today. Your industry lies at the intersection of two of the most pressing issues of our time: the energy challenge and the threat of nuclear proliferation.

430

Nuclear World Order and Nonproliferation  

SciTech Connect

The decision by India and Pakistan in May 1998 to conduct nuclear weapon tests and declare themselves as nuclear weapon states challenged South Asian regional stability calculations, US nonproliferation policy, and prevailing assumptions about international security. A decade later, the effects of those tests are still being felt and policies are still adjusting to the changed global conditions. This paper will consider non- and counter-proliferation policy options for the United States and Pakistan as they work as partners to prevent the transfer of nuclear technology and further nuclear proliferation.

Joeck, N

2007-02-05T23:59:59.000Z

431

Nuclear Science  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Science Science and Engineering Education Sourcebook 2013 American Nuclear Society US Department of Energy Nuclear Science & Engineering Education Sourcebook 2013 North American Edition American Nuclear Society Education, Training, and Workforce Division US Department of Energy Office of Nuclear Energy Editor and Founder John Gilligan Professor of Nuclear Engineering North Carolina State University Version 5.13 Welcome to the 2013 Edition of the Nuclear Science and Engineering Education (NS&EE) Sourcebook. We have evolved and improved! The core mission of the Sourcebook has not changed, however. Our purpose is to facilitate interaction among faculty, students, industry, and government agencies to accomplish nuclear research, teaching and service activities. Since 1986 we have compiled critical information on nuclear

432

Nuclear Fuels II - Programmaster.org  

Science Conference Proceedings (OSTI)

Oct 19, 2011 ... Materials Science Challenges for Nuclear Applications: Nuclear Fuels II ... reactivity and/or to flatten the radial power profile in a research or test reactor. ... Laboratory; 2Y-12 National Security Complex; 3University of Idaho

433

test02  

Gasoline and Diesel Fuel Update (EIA)

6 Tables 6 Tables May 1996 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. Contacts The annual publication Cost and Quality of Fuels for Electric Utility Plants (C&Q) is no longer published by the EIA. The tables presented in this document are intended to replace that annual publication. Questions regarding the availability of these data should be directed to: Coal and Electric Data and Renewables Division

434

Nuclear forces  

Science Conference Proceedings (OSTI)

These lectures present an introduction into the theory of nuclear forces. We focus mainly on the modern approach

2013-01-01T23:59:59.000Z

435

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Technology Technology Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Bookmark and Share The NE system engineering activities involve the conceptual design, through the manufacturing and qualification testing of the Mk-IV and Mk-V electrorefiner and the cathode processor. These first-of-a-kind large scale

436

Nuclear weapons, nuclear effects, nuclear war  

SciTech Connect

This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

Bing, G.F.

1991-08-20T23:59:59.000Z

437

EIS-0310: Notice of Intent to Prepare a Supplement Analysis  

Energy.gov (U.S. Department of Energy (DOE))

Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the United States, Including the Role of the Fast Flux Test Facility

438

EIS-0426: Notice of Intent to Prepare an Environmental Impact...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Impact Statement Continued Operation of the Department of EnergyNational Nuclear Security Administration Nevada Test Site and Off-Site Locations in the State of...

439

Early science runs prepare Sequoia for national security missions |  

National Nuclear Security Administration (NNSA)

Early science runs prepare Sequoia for national security missions | Early science runs prepare Sequoia for national security missions | 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 > Early science runs prepare Sequoia for national ... Early science runs prepare Sequoia for national security missions Posted By Office of Public Affairs

440

An Improved Nuclear Vector Replacement Algorithm for Nuclear Magnetic Resonance Assignment  

E-Print Network (OSTI)

An Improved Nuclear Vector Replacement Algorithm for Nuclear Magnetic Resonance Assignment to the Nuclear Vector Replacement (NVR) algorithm [24] for high-throughput Nuclear Magnetic Resonance (NMR% accu- racy) on the same test suite examined in [24], and runs in O(n5/2 log (cn)) time where n

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441

Nuclear Fuel Cycle | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Cycle Cycle Nuclear Fuel Cycle This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. The mission of NE-54 is primarily focused on activities related to the front end of the nuclear fuel cycle which includes mining, milling, conversion, and enrichment. Uranium Mining Both "conventional" open pit, underground mining, and in situ techniques are used to recover uranium ore. In general, open pit mining is used where deposits are close to the surface and underground mining is used

442

Nuclear Deterrence  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Deterrence Nuclear Deterrence Nuclear Deterrence LANL's mission is to develop and apply science and technology to ensure the safety, security, and effectiveness of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. April 12, 2012 A B-2 Spirit bomber refuels from a KC-135 Stratotanker A B-2 Spirit bomber refuels from a KC-135 Stratotanker. Contact Operator Los Alamos National Laboratory (505) 667-5061 Charlie McMillan, Director: "For the last 70 years there has not been a world war, and I have to think that our strong deterrent has something to do with that fact." Mission nuclear weapons Charlie McMillan, Director of Los Alamos National Laboratory 1:06 Director McMillan on nuclear deterrence While the role and prominence of nuclear weapons in U.S. security policy

443

Internal Audit Preparation Worksheet  

NLE Websites -- All DOE Office Websites (Extended Search)

2 Internal Audit Preparation Job Aid 11_0304 Page 1 of 5 2 Internal Audit Preparation Job Aid 11_0304 Page 1 of 5 EOTA - Business Form Document Title: Internal Audit Preparation Job Aid Document Number: F-012 Rev. 11_0304 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: P-007, Internal Audit Process Notify of Changes: Internal Auditors Referenced Document(s): F-011 Internal Audit Report F-012 Internal Audit Preparation Job Aid 11_0304 Page 2 of 5 Revision History: Rev. Description of Change A Initial Release 11_0304 Change title from Worksheet to Job Aid and changed revision from alpha to numeric for consistency. F-012 Internal Audit Preparation Job Aid 11_0304 Page 3 of 5 Internal Audit Preparation Worksheet F-012 Internal Audit Preparation Job Aid 11_0304 Page 4 of 5

444

Mitch S. Daugherty Nuclear Engineering and Planning Manager  

E-Print Network (OSTI)

. Daugherty also headed the Nuclear Refueling Division, the Nuclear Test Engineering Division, and the NuclearMitch S. Daugherty Nuclear Engineering and Planning Manager Naval Sea Systems Command, Norfolk Naval Shipyard Mitch Daugherty is the Nuclear Engineering and Planning Manager and the senior civilian

445

Nuclear data needs for application in nuclear criticality safety programs  

SciTech Connect

In nuclear criticality safety applications, a number of important uncertainties have to be addressed to establish the required criticality safety margin of a nuclear system. One source of these uncertainties is the basic nuclear data used to calculate the effective multiplication factor of the system. Before criticality safety calculations are performed, the bias and uncertainties of the codes and cross sections that are used must be determined. Cross-section data are measured, evaluated, and tested prior to their inclusion in nuclear data libraries. Traditionally, nuclear data evaluations are performed to support the analysis and design of thermal and fast reactors. The neutron spectra characteristic of the thermal and fast systems used for data testing are predominantly in the low- and high-energy ranges, with a relatively minor influence from the intermediate-energy range. In the area of nuclear criticality safety, nuclear systems involving spent fuel elements from reactors can lead to situations very different from those most commonly found in reactor analysis and design. These systems are not limited to thermal or fast neutron spectra and may have their most significant influence from the intermediate energy range. This requires extending the range of applicability of the nuclear data evaluation beyond thermal and fast systems. The aim here is to focus on the evaluated nuclear data pertaining to applications in nuclear criticality safety.

Leal, L.C.; Westfall, R.M.; Jordan, W.C.; Wright, R.Q. [Oak Ridge National Lab., TN (United States). Computational Physics and Engineering Div.

1995-09-01T23:59:59.000Z

446

EIS-0302: Notice of Intent to Prepare an Environmental Impact...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Impact Statement EIS-0302: Notice of Intent to Prepare an Environmental Impact Statement Transfer of the Heat Source Radioisotope Themoelectric Generator Assembly and Test...

447

International perspectives on coal preparation  

SciTech Connect

The report consists of the vugraphs from the presentations which covered the following topics: Summaries of the US Department of Energy`s coal preparation research programs; Preparation trends in Russia; South African coal preparation developments; Trends in hard coal preparation in Germany; Application of coal preparation technology to oil sands extraction; Developments in coal preparation in China; and Coal preparation in Australia.

1997-12-31T23:59:59.000Z

448

Preparation of biliquid foam compositions  

DOE Green Energy (OSTI)

Technology developed by the late Dr. Felix Sebba of the VPI Chemical Engineering Department by which an oil phase can be broken up into small droplets and encapsulated in a continuous water phase led to research on the possible merits of a fuel prepared by this procedure. The resulting mixture is called a polyaphron. Part 1 of this report describes the testing of polyaphronated gasoline in an automobile engine. Nitrogen oxides (NO{sub x}) emissions, total hydrocarbon (HC) emissions, and exhaust temperature were determined for various load and RPM combinations. Difficulties with viscosity and separation of the water phase have prevented complete testing at road load conditions. Rather than continue with engine testing, some bench tests of polyaphrons were performed to see the effect of various filtering processes on fuel stability as well as measuring viscosity and density. These results are reported in Part 2 of this paper. 6 figs., 4 tabs.

Jaasma, D.R.; Osucha, D.C.; Scheuren, J.

1990-12-12T23:59:59.000Z

449

Nuclear data interface retrospective  

SciTech Connect

The Nuclear Data Interface (NDI) code library and data formats are the standards for multigroup nuclear data at Los Alamos National Laboratory. NDI's analysis, design, implementation, testing, integration, and maintenance required a ten person-year and ongoing effort by the Nuclear Data Team. Their efforts provide a unique, contemporary experience in producing a standard component library. In reflection upon that experience at NDI's decennial, we have identified several factors critical to NDI's success: it addressed real problems with appropriate simplicity, it fully supported all users, it added extra value through the code to the raw nuclear data, and its team went the distance from analysis through maintenance.