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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.


1

Nuclear testing continues  

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

nation's supply had literally been used up ending the war, was to prepare for additional nuclear testing. Earlier we briefly mentioned the first such test after the war. Let's...

2

Preparing Non-nuclear Engineers for the Nuclear Field  

E-Print Network (OSTI)

Preparing Non-nuclear Engineers for the Nuclear Field Elizabeth K. Ervin The University. An understanding of power generation is important for all modern-day engineers, and nuclear energy serves as a good-four universities have nuclear- related programs, including Nuclear or Radiological Engineering, Nuclear Science

Ervin, Elizabeth K.

3

Nuclear testing: Executive summary  

SciTech Connect

The authors have examined the experimental and analytic bases for understanding the performance of each of the weapon types that are currently planned to remain in the US enduring nuclear stockpile. They have also examined whether continued underground tests at various nuclear yield thresholds would add significantly to the confidence in this stockpile in the years ahead. The starting point for this examination was a detailed review of past experience in developing and testing modern nuclear weapons, their certification and recertification processes, their performance margins, and evidence of aging or other trends over time for each weapon type in the enduring stockpile. The findings, as summarized in Conclusions 1 through 6, are consistent with US agreement to enter into a Comprehensive Test Ban Treaty (CTBT) of unending duration, that includes a standard ``supreme national interest`` clause. Recognizing that the challenge of maintaining an effective nuclear stockpile for an indefinite period without benefit of underground tests is an important and also a new one, the US should affirm its readiness to invoke the supreme national interest clause should the need arise as a result of unanticipated technical problems in the enduring stockpile.

Drell, S.; Cornwall, J.; Dyson, F. [and others

1995-08-01T23:59:59.000Z

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

Nuclear weapons testing  

SciTech Connect

The author examines the history of efforts to ban, or at least constrain, nuclear tests. The issue has been marked by shifts in attitude by the superpowers in recent times. The Reagan Administration sees a comprehensive test ban only as a very long-term goal for the U.S. The Soviets, on the other hand, have been pushing extremely hard lately for a ban on all testing. The author discusses the pros and cons of such a ban by examining the arguments of the U.S. Department of Energy, Nobel Laureate Glenn T. Seaborg, and Associate Director for Defense Systems at Lawrence Livermore National Laboratory George H. Miller. Other issues that are discussed include verification, joint testing, and reliability. He concludes with a discussion of the future of the ban.

Heylin, M.

1988-02-15T23:59:59.000Z

6

LEAM Film Development Test Report Prepared by  

E-Print Network (OSTI)

Solar Test Test Item No. l Film Development Tests Test Item No. 2 Film Development Tests Test Item No. 3~~ ··········~~~ LEAM Film Development Test Report Prepared by: R. Sii'r'...ms ~1 rf\\:'3· ~ ij ATM Film Development Test Report -~~'·.· ··..· .··. . ~...=-~ ~ IWitJY~W ' ~· CONTENTS 1. PURPOSE 2. SCOPE

Rathbun, Julie A.

7

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

National Nuclear Security Administration (NNSA)

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

8

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

National Nuclear Security Administration (NNSA)

Testing Resumes | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

9

test and evaluation | National Nuclear Security Administration  

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

test and evaluation | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

10

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

11

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

12

Hollow arguments against nuclear test ban  

Science Journals Connector (OSTI)

... their recent contention that an event near Novaya Zemlya, in northern Russia, was a surreptitious nuclear test. ...

1997-11-06T23:59:59.000Z

13

First Thermonuclear Device Successfully Tested | National Nuclear...  

National Nuclear Security Administration (NNSA)

Thermonuclear Device Successfully Tested | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

14

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

15

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

16

A new era of nuclear test verification  

SciTech Connect

The global network of sensors commissioned to monitor compliance with the Comprehensive Nuclear-Test-Ban Treaty has proven capable of that task and more.

Auer, Matthias; Prior, Mark K.

2014-09-01T23:59:59.000Z

17

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 (more)

Raas, Whitney

2006-01-01T23:59:59.000Z

18

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

19

(Test, calibrate, and prepare a BGO photon detector system)  

SciTech Connect

The traveler spent the year at CERN primarily to test, calibrate, and prepare a BGO photon detector system for use in the August 1990 run of WA80 with sulfur beams and for use in future planned runs with an expanded BGO detector. The BGO was used in test-beam runs in December 1989 and April--May 1990 and in the August data-taking run. The Midrapidity Calorimeters (MIRAC) were also prepared in a new geometry for the August run with a new transverse energy trigger. The traveler also continued to refine and carry out simulations of photon detector systems in present and future planned photon detection experiments. The traveler participated in several WA80 collaboration meetings, which were held at CERN throughout the period of stay. Invited talks were presented at the Workshop on High Resolution Electromagnetic Calorimetry in Stockholm, Sweden, November 9--11, 1989, and at the International Workshop on Software Engineering, Artificial Intelligence, and Expert Systems for High-Energy and Nuclear Physics at Lyon, France, March 19--24, 1990. The traveler participated in an experiment to measure particle--particle correlations at 30-MeV/nucleon incident energies at the SARA facility in Grenoble from November 11--24, 1989.

Awes, T.C.

1990-10-19T23:59:59.000Z

20

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

Office of Environmental Management (EM)

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

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

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

National Nuclear Security Administration (NNSA)

Test and Evaluation | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

22

Court blocks testing of nuclear waste site  

Science Journals Connector (OSTI)

Court blocks testing of nuclear waste site ... WIPP was authorized by Congress in 1979 to provide an R&D facility to demonstrate safe handling, transport, and disposal of "mixed" transuranic wastes (contaminated with radioactive plutonium-239 and hazardous chemicals), which are now stored temporarily at DOE nuclear-weapons-making facilities. ...

RICHARD SELTZER

1992-02-10T23:59:59.000Z

23

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

24

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

National Nuclear Security Administration (NNSA)

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

25

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

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

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...

26

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

27

Method of preparing nuclear wastes for tansportation and interim storage  

DOE Patents (OSTI)

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

28

The administration, Congress and nuclear testing  

SciTech Connect

Against the backdrop of ongoing consultations between Congress and the Clinton administration on the question of whether to resume nuclear testing, the Arms Control Association (ACA) held a news conference June 23 to provide greater information on the technical, political and arms control issues involved, including the wider implications for the non-proliferation regime and the 1995 nuclear Non-Proliferation Treaty Review and Extension Conference.

NONE

1993-07-01T23:59:59.000Z

29

Nuclear Rocket Development Station at the Nevada Test Site |...  

Office of Environmental Management (EM)

Nuclear Rocket Development Station at the Nevada Test Site Nuclear Rocket Development Station at the Nevada Test Site During the 1950s, the United States launched a nuclear rocket...

30

The comprehensive Nuclear Test Ban Treaty and Seismological Research  

Science Journals Connector (OSTI)

...political context of global monitoring of underground nuclear...the Nevada Test Site. Monitoring active nuclear test...that none of them are surreptitious nuclear explosions in...chal- lenges for CTBT monitoring will be to sustain the...

Thorne Lay

31

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

32

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

33

Drop Testing of DOE Spent Nuclear Fuel Canisters  

SciTech Connect

The National Spent Nuclear Fuel Program (NSNFP) at the Idaho National Engineering and Environmental Laboratory INEEL) prepared four representative Department of Energy DOE) spent nuclear fuel (SNF) canisters for the purpose of drop testing. The first two canisters represented a modified 24- inch diameter standardized DOE SNF canister and the second two canisters represented the Hanford Multi-Canister Overpack MCO). The modified canisters and internals were constructed and assembled at the INEEL. The MCO internal weights were fabricated at the INEEL and assembled into two MCOs at Hanford and later shipped to the INEEL for drop test preparation. Drop testing of these four canisters was completed in August 2004 at Sandia National Laboratories. The modified canisters were dropped from 30 feet onto a flat, essentially unyielding surface, with the canisters oriented at 45 degrees and 70 degrees off-vertical at impact. One representative MCO was dropped from 23 feet onto the same flat surface, oriented vertically at impact. The second representative MCO was dropped onto the flat surface from 2 feet oriented at 60 degrees off-vertical. These drop heights and orientations were chosen to meet or exceed the Yucca Mountain repository drop criteria. This paper discusses the comparison of deformations between the actual dropped canisters and those predicted by pre-drop and limited post-drop finite element evaluations performed using ABAQUS/Explicit. Post-drop containment of all four canisters, demonstrated by way of helium leak testing, is also discussed.

S. D. Snow; D. K. Morton; T. E. Rahl; R. K. Blandford; T. J. Hill

2005-07-01T23:59:59.000Z

34

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 People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

35

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

National Nuclear Security Administration (NNSA)

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

36

Sandia completes major overhaul of key nuclear weapons test facilities...  

National Nuclear Security Administration (NNSA)

completes major overhaul of key nuclear weapons test facilities | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering...

37

Laboratory's role in Cold War nuclear weapons testing program...  

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

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...

38

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

National Nuclear Security Administration (NNSA)

Clinton Extends Moratorium on Nuclear Weapons Testing | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile...

39

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

40

Move to test nuclear waste site draws fire  

Science Journals Connector (OSTI)

Move to test nuclear waste site draws fire ... The Department of Energy has stirred up a storm of opposition by taking administrative action, bypassing Congress, that would enable it to start testing an underground nuclear waste repository in New Mexico. ...

RICHARD SELTZER

1991-10-14T23:59:59.000Z

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.


41

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

42

Xenon monitoring and the Comprehensive Nuclear-Test-Ban Treaty  

SciTech Connect

How do you monitor (verify) a CTBT? It is a difficult challenge to monitor the entire world for nuclear tests, regardless of size. Nuclear tests 'normally' occur underground, above ground or underwater. Setting aside very small tests (let's limit our thinking to 1 kiloton or more), nuclear tests shake the ground, emit large amounts of radioactivity, and make loud noises if in the atmosphere (or hydroacoustic waves if underwater)

Bowyer, Theodore W. [Nuclear Explosion Monitoring Program, Pacific Northwest National Laboratory, Richland, Washington 99352 (United States)

2014-05-09T23:59:59.000Z

43

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

44

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

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

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

48

Supporting the Comprehensive Nuclear-Test-Ban Treaty  

SciTech Connect

PNNL operates the only certified laboratory in the U.S. for the Comprehensive Nuclear-Test-Ban Treaty's International Monitoring System (IMS).

Bowyer, Ted

2014-11-20T23:59:59.000Z

49

Supporting the Comprehensive Nuclear-Test-Ban Treaty  

ScienceCinema (OSTI)

PNNL operates the only certified laboratory in the U.S. for the Comprehensive Nuclear-Test-Ban Treaty's International Monitoring System (IMS).

Bowyer, Ted

2014-06-12T23:59:59.000Z

50

Calculated concentrations of any radionuclide deposited on the ground by release from underground nuclear detonations, tests of nuclear rockets, and tests of nuclear ramjet engines  

SciTech Connect

This report presents calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from three types of event that deposited detectable radioactivity outside the Nevada Test Site complex, namely, underground nuclear detonations, tests of nuclear rocket engines and tests of nuclear ramjet engines.

Hicks, H.G.

1981-11-01T23:59:59.000Z

51

The politics of verification: Limiting the testing of nuclear weapons  

SciTech Connect

From 1982 to 1990, the United States and the Soviet Union renegotiated verification arrangements for two unratified arms control agreements that had nevertheless been observed since 1977: the Threshold Test Ban Treaty and the Peaceful Nuclear Explosions Treaty. The negotiations yielded new verification procedures, changed attitudes regarding Soviet compliance, and established useful precedents for further restrictions on nuclear testing. The negotiations also demonstrated how technical arguments can be misused to promote a particular political agenda-in this case, the continued testing of nuclear weapons. By misrepresenting the uncertainties in US monitoring procedures, and then falsely characterizing these uncertainties as a fatal flaw of seismic verification techniques, opponents of a nuclear test ban clouded the sensitive issue of verification enough to delay progress towards a complete ban on nuclear weapons testing. The primary obstacle to further restrictions on nuclear testing was not the feasibility of adequate verification, but rather the unwillingness of several US administrations to address the real question of whether the United States and other nuclear weapon states should, in the interest of global nuclear nonproliferation, end the development of new nuclear weapons designs that require confirmation by underground nuclear tests. 51 refs., 6 figs.

Vink, G.E. van der (IRIS Consortion on Seismology, Arlington, VA (United States)); Paine, C.E. (Natural Reources Defense Council, Washington, DC (United States))

1993-01-01T23:59:59.000Z

52

DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis, Roll Out Training  

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

The Office of Nuclear Safety is performing a series of site visits to provide roll-out training and assistance to Program and Site Offices and their contractors on effective implementation of the new revision to DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis.

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

Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981  

SciTech Connect

This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years.

Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L. (comps.)

1982-08-01T23:59:59.000Z

55

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,

56

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

57

Operation TEAPOT, 1955 continental nuclear weapons test series. Technical report  

SciTech Connect

This report describes the activities of an estimated 11,000 DOD personnel, both military and civilian, in Operation TEAPOT, the fifth atmospheric nuclear weapons testing series conducted in Nevada from 18 February to 15 May 1955. Activities engaging DOD personnel included Exercise Desert Rock VI observer programs, troop tests, and technical service programs; AEC scientific and diagnostic experiments to evaluate the effects of the nuclear device; DOD operational programs; and air support.

Ponton, J.; Maag, C.; Wilkinson, M.; Shepanek, R.F.

1981-11-23T23:59:59.000Z

58

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

SciTech Connect

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

59

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

60

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

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

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

62

Preparation of most promising braided and/or textile-based adsorbents for seawater testing  

SciTech Connect

Progress Report...Prepare the most promising braided and/or textile-based adsorbents for seawater testing. M3FT-14OR0310012

Janke, Chris [ORNL] [ORNL; Sadananda, Das [ORNL] [ORNL; Mayes, Richard [ORNL] [ORNL

2014-02-26T23:59:59.000Z

63

A New Seismic Data System for Determining Nuclear Test Yields At the Nevada Test Site  

SciTech Connect

An important capability in conducting underground nuclear tests is to be able to determine the nuclear test yield accurately within hours after a test. Due to a nuclear test moratorium, the seismic method that has been used in the past has not been exercised since a non-proliferation high explosive test in 1993. Since that time, the seismic recording system and the computing environment have been replaced with modern equipment. This report describes the actions that have been taken to preserve the capability for determining seismic yield, in the event that nuclear testing should resume. Specifically, this report describes actions taken to preserve seismic data, actions taken to modernize software, and actions taken to document procedures. It concludes with a summary of the current state of the data system and makes recommendations for maintaining this system in the future.

LEE, JONATHAN W.

2001-11-01T23:59:59.000Z

64

Survey of hazardous materials used in nuclear testing  

SciTech Connect

The use of hazardous'' materials in routine underground nuclear tests at the Nevada Test Site has been reviewed. In addition the inventory of test yields, originally reported in 1976 has been updated. A trail down-hole inventory'' has been conducted for a selected test. The inorganic hazardous materials introduced during testing (with the exception of lead and the fissionable materials) produce an incremental change in the quantity of such materials already present in the geologic media surrounding the test points. 1 ref., 3 tabs.

Bryant, E.A.; Fabryka-Martin, J.

1991-02-01T23:59:59.000Z

65

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)

66

The Nuclear Non-Proliferation Treaty and the Comprehensive Nuclear-Test-Ban Treaty, the relationship  

SciTech Connect

The Nuclear Non-Proliferation Treaty (NPT) is the most important international security arrangement that we have that is protecting the world community and this has been true for many years. But it did not happen by accident, it is a strategic bargain in which 184 states gave up the right forever to acquire the most powerful weapon ever created in exchange for a commitment from the five states allowed to keep nuclear weapons under the NPT (U.S., U.K., Russia, France and China), to share peaceful nuclear technology and to engage in disarmament negotiations aimed at the ultimate elimination of their nuclear stockpiles. The most important part of this is the comprehensive nuclear test ban (CTBT); the thinking by the 184 NPT non-nuclear weapon states was and is that they understand that the elimination of nuclear weapon stockpiles is a long way off, but at least the NPT nuclear weapon states could stop testing the weapons. The CTBT has been ratified by 161 states but by its terms it can only come into force if 44 nuclear potential states ratify; 36 have of the 44 have ratified it, the remaining eight include the United States and seven others, most of whom are in effect waiting for the United States. No state has tested a nuclear weapon-except for complete outlier North Korea-in 15 years. There appears to be no chance that the U.S. Senate will approve the CTBT for ratification in the foreseeable future, but the NPT may not survive without it. Perhaps it is time to consider an interim measure, for the UN Security Council to declare that any future nuclear weapon test any time, anywhere is a 'threat to peace and security', in effect a violation of international law, which in today's world it clearly would be.

Graham, Thomas Jr. [7609 Glenbrook Rd., Bethesda, MD 20814 (United States)

2014-05-09T23:59:59.000Z

67

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.

Not Available

1993-11-01T23:59:59.000Z

68

A compilation of nuclear weapons test detonation data for U.S. Pacific ocean tests  

SciTech Connect

Prior to December 1993, the explosive yields of 44 of 66 nuclear tests conducted by the United States in the Marshall Islands were still classified. Following a request from the Government of the Republic of the Marshall Islands to the U.S. Department of Energy to release this information, the Secretary of Energy declassified and released to the public the explosive yields of the Pacific nuclear tests. This paper presents a synopsis of information on nuclear test detonations in the Marshall Islands and other locations in the mid-Pacific including dates, explosive yields, locations, weapon placement, and summary statistics. 10 refs., 1 fig., 2 tabs.

Simon, S.L. [Radiation Effects Research, Washington, DC (United States); Robison, W.L. [Lawrence Livermore National Lab., CA (United States)

1997-07-01T23:59:59.000Z

69

Development of magnetic mirror systems for nuclear testing applications  

SciTech Connect

Several system studies have concluded that the small size and steady state nature of magnetic mirror systems provide attractive features for nuclear-testing applications. The principle shortcoming of mirror systems is their small data base relative to that of tokamaks. This paper summarizes the present data base and describes experiments that could be carried out with small modifications of existing facilities to explore plasma physics issues associated with the production of high neutron fluxes in magnetic mirror configurations. The experiments would demonstrate physics principles important to such future applications of fusion power neutrons as blanket testing, tritium production, fissile fuel production, or decontamination of high-level radioactive nuclear-reactor wastes.

Simonen, T.C.; Futch, A.H.; Kaiser, T.B.

1986-08-07T23:59:59.000Z

70

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

71

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

72

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

73

E-Print Network 3.0 - atmospheric nuclear tests Sample Search...  

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

Powered by Explorit Topic List Advanced Search Sample search results for: atmospheric nuclear tests Page: << < 1 2 3 4 5 > >> 1 January 3, 2007 National Nuclear Security...

74

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

SciTech Connect

This Department of Energy (DOE) is approved for use by all components of DOE. It 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 with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs.

NONE

1998-09-01T23:59:59.000Z

75

Analysis of nuclear test TRINITY radiological and meteorological data  

SciTech Connect

This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the TRINITY nuclear test. Inconsistencies in the radiological data and their resolution are discussed. The methods of normalizing the radiological data to a standard time and estimating fallout-arrival times are presented. The meteorological situations on event day and the following day are described. Comparisons of the WSNSO fallout analyses with analyses performed in the 1940s are presented. The radiological data used to derive the WSNSO 1987 fallout patterns are tabulated in appendices.

Quinn, V.E.

1987-09-01T23:59:59.000Z

76

Resettlement of Bikini Atoll U.S. Nuclear Test Site  

SciTech Connect

The US conducted a nuclear testing program at Bikini and Enewetak Atolls in the Marshall Islands from 1946 through 1958. Several atolls, including Bikini, were contaminated as a result of the nuclear detonations. Since 1974 the authors have conducted an extensive research and monitoring program to determine the radiological conditions at the atolls, identify the critical radionuclides and pathways, estimate the radiological dose to current or resettling populations, and develop remedial measures to reduce the dose to atoll populations. This paper describes exposure pathways and radionuclides; composition of atoll soils; radionuclide transport and dose estimates; remedial measures; and reduction in dose from a combined option.

Robinson, W.L.; Conrado, C.L.; Stuart, M.L.; Stoker, A.C.; Hamilton, T.F.

1999-09-09T23:59:59.000Z

77

Bikini, Enewetak, and Rongelap Marshallese, and United States nuclear weapons testing in the Marshall Islands: A bibliography  

SciTech Connect

A considerable literature exists on the Bikini, Enewetak, and Rongelap Marshallese and their atolls; however, this literature consists of a large number of governmental documents that are relatively unknown and difficult to locate. This is particularly true of the documents of the Trust Territory of the Pacific Islands and those related to nuclear weapons testing in the Marshall Islands. Because a comprehensive bibliography on the impact of nuclear weapons testing on the Marshallese and their atolls does not exist, the preparation of a bibliography that includes sufficient information to locate all types of reports seems justified. This document is the bibliography.

Schultz, V. (Washington State Univ., Pullman, WA (USA)); Schultz, S.C. (Oregon Univ., Eugene, OR (USA)); Robison, W.L. (ed.) (Lawrence Livermore National Lab., CA (USA))

1991-05-01T23:59:59.000Z

78

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

79

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

80

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 1Subcommittee 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

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

Test protocol for aluminum based spent nuclear fuel  

SciTech Connect

Aluminum based spent nuclear fuel (Al-SNF) will be treated and then stored in a geological repository. A series of corrosion tests, including coupon, galvanic, and electrochemical, were performed to measure the effects of degradation on U-Al alloys, which simulated various Al-SNF forms. The test solutions were variants of a J-13 well water chemistry. As part of the degradation characteristics, the dissolution of uranium, which is the primary radionuclide, was measured. The degradation and dissolution were changed by the type of water chemistry and the temperature. The alloy composition and fabrication were not significant variables.

Mickalonis, J.I.; Wiersma, B.J.

1999-07-01T23:59:59.000Z

82

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

83

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

84

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

85

E-Print Network 3.0 - above-ground nuclear tests Sample Search...  

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

nuclear tests Search Powered by Explorit Topic List Advanced Search Sample search results for: above-ground nuclear tests Page: << < 1 2 3 4 5 > >> 1 Host use strategies of...

86

Exhaust gas treatment in testing nuclear rocket engines  

Science Journals Connector (OSTI)

With the exception of the last test series of the Rover program Nuclear Furnace 1 test?reactor and rocket engine hydrogen gas exhaust generated during the Rover/NERVA program was released directly to the atmosphere without removal of the associated fission products and other radioactive debris. Current rules for nuclear facilities (DOE Order 5480.6) are far more protective of the general environment; even with the remoteness of the Nevada Test Site introduction of potentially hazardous quantities of radioactive waste into the atmosphere must be scrupulously avoided. The Rocketdyne treatment concept features a diffuser to provide altitude simulation and pressure recovery a series of heat exchangers to gradually cool the exhaust gas stream to 100 K and an activated charcoal bed for adsorption of inert gases. A hydrogen?gas fed ejector provides auxiliary pumping for startup and shutdown of the engine. Supplemental filtration to remove particulates and condensed phases may be added at appropriate locations in the system. The clean hydrogen may be exhausted to the atmosphere and flared or the gas may be condensed and stored for reuse in testing. The latter approach totally isolates the working gas from the environment.

Herbert R. Zweig; Stanley Fischler; William R. Wagner

1993-01-01T23:59:59.000Z

87

Exhaust gas treatment in testing nuclear rocket engines  

SciTech Connect

With the exception of the last test series of the Rover program, Nuclear Furnace 1, test-reactor and rocket engine hydrogen gas exhaust generated during the Rover/NERVA program was released directly to the atmosphere, without removal of the associated fission products and other radioactive debris. Current rules for nuclear facilities (DOE Order 5480.6) are far more protective of the general environment; even with the remoteness of the Nevada Test Site, introduction of potentially hazardous quantities of radioactive waste into the atmosphere must be scrupulously avoided. The Rocketdyne treatment concept features a diffuser to provide altitude simulation and pressure recovery, a series of heat exchangers to gradually cool the exhaust gas stream to 100 K, and an activated charcoal bed for adsorption of inert gases. A hydrogen-gas fed ejector provides auxiliary pumping for startup and shutdown of the engine. Supplemental filtration to remove particulates and condensed phases may be added at appropriate locations in the system. The clean hydrogen may be exhausted to the atmosphere and flared, or the gas may be condensed and stored for reuse in testing. The latter approach totally isolates the working gas from the environment.

Zweig, H.R.; Fischler, S.; Wagner, W.R. (Rocketdyne Division, Rockwell International Corporation, 6633 Canoga Avenue, P.O. Box 7922, Canoga Park, California 91309-7922 (United States))

1993-01-15T23:59:59.000Z

88

"This awesome field"; a history of United States nuclear testing and its influence on nuclear thought, 1945-1963.  

E-Print Network (OSTI)

??The history of U. S. nuclear testing between 1945 and 1963 is not only a vivid and exciting story but also one of profound historical (more)

Blades, D

2013-01-01T23:59:59.000Z

89

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

E-Print Network (OSTI)

nuclear tests J. D. Lowrey,1 S. R. Biegalski,1 A. G. Osborne,1 and M. R. Deinert1 Received 14 September can provide critical information with which to verify that a belowground nuclear test has taken place and decay rate. The xenon signature of a nuclear test is then bounded by the signal from directly produced

Deinert, Mark

90

Seismological Evidence for a Low-Yield Nuclear Test on 12 May 2010 in North Korea  

E-Print Network (OSTI)

E Seismological Evidence for a Low-Yield Nuclear Test on 12 May 2010 in North Korea by Miao Zhang. INTRODUCTION Three nuclear tests (in 2006, 2009, and 2013) conducted by the Democratic People's Republic.g., the U. S. Geological Survey [USGS] and the Comprehensive Nuclear-Test-Ban Treaty Organization [CTBTO

Wen, Lianxing

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

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 electro-refined uranium products exceeded 99%. (authors)

Westphal, B.R.; Wurth, L.A.; Fredrickson, G.L.; Galbreth, G.G.; Vaden, D.; Elliott, M.D.; Price, J.C.; Honeyfield, E.M.; Patterson, M.N. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415 (United States)

2013-07-01T23:59:59.000Z

93

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

94

Current Concentration of Artificial Radionuclides and Estimated Radiation Doses from 137Cs around the Chernobyl Nuclear Power Plant, the Semipalatinsk Nuclear Testing Site, and in Nagasaki  

Science Journals Connector (OSTI)

......137Cs around the Chernobyl Nuclear Power Plant, the Semipalatinsk Nuclear Testing Site, and in Nagasaki...the Chernobyl accident and nuclear tests at SNTS were simultaneously...from sev- eral statistical datasets, as there were no detailed......

Yasuyuki Taira; Naomi Hayashida; Gopalganapathi M. Brahmanandhan; Yuji Nagayama; Shunichi Yamashita; Jumpei Takahashi; Alexander Gutevitc; Alexander Kazlovsky; Marat Urazalin; Noboru Takamura

2011-01-01T23:59:59.000Z

95

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

96

Mortality of veteran participants in the crossroads nuclear test  

SciTech Connect

Operation CROSSROADS, conducted at Bikini Atoll in 1946, was the first post World War II test of nuclear weapons. Mortality experience of 40,000 military veteran participants in CROSSROADS was compared to that of a similar cohort of nonparticipating veterans. All-cause mortality of the participants was slightly increased over nonparticipants by 5% (p < .001). Smaller increases in participant mortality for all malignancies (1.4%, p = 0.26) or leukemia (2.0%, p = 0.9) were not statistically significant. These results do not support a hypothesis that radiation had increased participant cancer mortality over that of nonparticipants. 8 refs.

Johnson, J.C.; Thaul, S.; Page, W.F. [Institute of Medicine, Washington, DC (United States)] [and others

1997-07-01T23:59:59.000Z

97

Present experience of NRI REZ with preparation of spent nuclear fuel shipment to Russian Federation  

SciTech Connect

The Nuclear Research Institute Rez plc (NRI) jointed the Russian Research Reactor Fuel Return (RRRFR) programme under the US-Russian Global Threat Reduction Initiative (GTRI) initiative and started the preparation of the spent nuclear fuel (SNF) shipment from the LVR-15 research reactor back to the Russian Federation (RF). The transport of 16 SKODA VPVR/M casks with EK-10, IRT-2M 80 %, and IRT-2M 36% fuel types is planned for the autumn of 2007. The paper describes the experience gained so far during the preparatory works for the SNF shipment (facility equipment modification, cask licenses) and the actual preparation of the SNF for transport, in particular its checking, repacking in a hot cell, loading into the VPVR/M casks, drying, manipulation, completion of the transport documentation, etc., including its transport to the SNF storage facility at the NRI before it is shipped to the RF. The paper also briefly describes a regulatory framework for these activities with a focus on legislative and methodological aspects of the return of vitrified waste back to the Czech Republic. (author)

Svitak, F.; Broz, V.; Hrehor, M.; Marek, M.; Novosad, P.; Podlaha, J.; Rychecky, J. [Nuclear Research Institute Rez plc, Husinec 130, CZ-25068 (Czech Republic)

2008-07-15T23:59:59.000Z

98

Radioactive ''hot spots'' from nuclear weapons test fallout  

SciTech Connect

In a paper presented on January 8, 1985, at the Health Physics Society Midyear Symposium, Franke and Alvarez claimed that radioactivity observed on the Savannah River Plant site on March 14, 1955, was the result of a reactor accident. The source of the observed radioactivity was, in fact, rainwater containing radioactive products from a nuclear weapon test made two days earlier in Nevada. The weapon test TEAPOT HORNET was shown to be the source of the contamination at the time, and this has been corroborated in two recent papers. The aim of this review is to show that the highly-localized radioactive fallout on the Savannah River Plant site was not unique but part of a widespread phenomenon occurring all over the United States in the 1950s and early 1960s. 18 references, 2 figures, 2 tables.

Sanders, S.M.

1985-02-11T23:59:59.000Z

99

Bikini, Enewetak, and Rongelap Marshallese, and United States nuclear weapons testing in the Marshall Islands: A bibliography  

SciTech Connect

A considerable literature exists on the Bikini, Enewetak, and Rongelap Marshallese and their atolls; however, this literature consists of a large number of governmental documents that are relatively unknown and difficult to locate. This is particularly true of the documents of the Trust Territory of the Pacific Islands and those related to nuclear weapons testing in the Marshall Islands. Because a comprehensive bibliography on the impact of nuclear weapons testing on the Marshallese and their atolls does not exist, the preparation of a bibliography that includes sufficient information to locate all types of reports seems justified. Primary sources of information in preparing this bibliography were bibliographies on Oceania, citations in published papers, CIS Index and Abstracts, Monthly Catalog of United States Government Publications, Nuclear Science Abstracts, Energy Research Abstracts, numerous bibliographies on radiation ecology, and suggestions by many individuals whom we contacted. One goal in this bibliography is to include complete documentation of the source of congressional reports and other government-related publications. In addition, page numbers for material in this bibliography are provided in parentheses when the subject matter of a book or document is not restricted to nuclear weapons testing in the Marshall Islands.

Robison, W.L. (ed.) (Lawrence Livermore National Lab., CA (USA)); Schultz, V. (Washington State Univ., Pullman, WA (USA)); Schultz, S.C. (Oregon Univ., Eugene, OR (USA))

1991-04-01T23:59:59.000Z

100

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

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.


101

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

Boyer, Edmond

102

Interim report spent nuclear fuel retrieval system fuel handling development testing  

SciTech Connect

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

103

Regional observations of the second North Korean nuclear test on 2009 May 25  

Science Journals Connector (OSTI)

......Dreger D.S., 2000. Performance test of an automated moment tensor determination...G., 2007. North Korean nuclear test: seismic discrimination at low yield...W. , 1986. Yield estimates of Nevada test site explosions obtained from seismic......

Jin Soo Shin; Dong-Hoon Sheen; Geunyoung Kim

2010-01-01T23:59:59.000Z

104

Advances in the Hopkinson bar testing of irradiated/non-irradiated nuclear materials and large specimens  

Science Journals Connector (OSTI)

...the twentieth century, research activity in the nuclear field of the Joint Research Centre (JRC) was concentrated on problems of nuclear reactor safety, especially...dynamic material testing programme for the high ductility...

2014-01-01T23:59:59.000Z

105

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

106

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;

107

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;

108

Preparation and characterisation of isotopically enriched Ta$_2$O$_5$ targets for nuclear astrophysics studies  

E-Print Network (OSTI)

The direct measurement of reaction cross sections at astrophysical energies often requires the use of solid targets of known thickness, isotopic composition, and stoichiometry that are able to withstand high beam currents for extended periods of time. Here, we report on the production and characterisation of isotopically enriched Ta$_2$O$_5$ targets for the study of proton-induced reactions at the Laboratory for Underground Nuclear Astrophysics facility of the Laboratori Nazionali del Gran Sasso. The targets were prepared by anodisation of tantalum backings in enriched water (up to 66% in $^{17}$O and up to 96% in $^{18}$O). Special care was devoted to minimising the presence of any contaminants that could induce unwanted background reactions with the beam in the energy region of astrophysical interest. Results from target characterisation measurements are reported, and the conclusions for proton capture measurements with these targets are drawn.

A. Caciolli; D. A. Scott; A. Di Leva; A. Formicola; M. Aliotta; M. Anders; A. Bellini; D. Bemmerer; C. Broggini; M. Campeggio; P. Corvisiero; R. Depalo; Z. Elekes; Zs. Flp; G. Gervino; A. Guglielmetti; C. Gustavino; Gy. Gyrky; G. Imbriani; M. Junker; M. Marta; R. Menegazzo; E. Napolitani; P. Prati; V. Rigato; V. Roca; C. Rolfs; C. Rossi Alvarez; E. Somorjai; C. Salvo; O. Straniero; F. Strieder; T. Szcs; F. Terrasi; H. P. Trautvetter; D. Trezzi

2012-10-01T23:59:59.000Z

109

A case study: using multiple-choice tests at university level courses preparation and supporting infrastructure  

Science Journals Connector (OSTI)

In this paper, we will present a case study of using multiple-choice tests for university level courses such as digital logic and artificial intelligence. It is a well known fact that multiple-choice questions can be used to assess student's knowledge not only student's recall, but also the verification of student's analysis and synthesis abilities. We will give an example of questions for assessment of all three types. We will consider how computers can be used to prepare such tests and what is needed to automatically grade such tests. We will present an open source application that we developed to foster such a process.

M. Cupic

2010-01-01T23:59:59.000Z

110

Final Report - Spent Nuclear Fuel Retrieval System Manipulator System Cold Validation Testing  

SciTech Connect

Manipulator system cold validation testing (CVT) was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin; clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge); remove the contents from the canisters; and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. The FRS is composed of three major subsystems. The Manipulator Subsystem provides remote handling of fuel, scrap, and debris; the In-Pool Equipment subsystem performs cleaning of fuel and provides a work surface for handling materials; and the Remote Viewing Subsystem provides for remote viewing of the work area by operators. There are two complete and identical FRS systems, one to be installed in the K-West basin and one to be installed in the K-East basin. Another partial system will be installed in a cold test facility to provide for operator training.

D.R. Jackson; G.R. Kiebel

1999-08-24T23:59:59.000Z

111

A guide to archival collections relating to radioactive fallout from nuclear weapon testing  

SciTech Connect

This ninth edition of A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing constitutes History Associates Incorporated's (HAI) final report of its document collection, processing, and declassification efforts for the Nevada Field Office of the Department of Energy. The most significant feature of this edition is the updated HAI collection effort information. We confirmed the accuracy of this information using our screening, processing, and transmittal records. Unlike previous editions, funding limitations prevented us from systematically revising the collection descriptions and point-of-contact information for this final edition. This guide has been prepared by professional historians who have a working knowledge of many of the record collections included in the following pages. In describing materials, they have tried to include enough information so that persons unfamiliar with the complexities of large record systems will be able to determine that nature of the information in, and the quality of, each record collection.

Martin, B.W. (ed.)

1992-09-01T23:59:59.000Z

112

A guide to archival collections relating to radioactive fallout from nuclear weapon testing. Ninth edition  

SciTech Connect

This ninth edition of A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing constitutes History Associates Incorporated`s (HAI) final report of its document collection, processing, and declassification efforts for the Nevada Field Office of the Department of Energy. The most significant feature of this edition is the updated HAI collection effort information. We confirmed the accuracy of this information using our screening, processing, and transmittal records. Unlike previous editions, funding limitations prevented us from systematically revising the collection descriptions and point-of-contact information for this final edition. This guide has been prepared by professional historians who have a working knowledge of many of the record collections included in the following pages. In describing materials, they have tried to include enough information so that persons unfamiliar with the complexities of large record systems will be able to determine that nature of the information in, and the quality of, each record collection.

Martin, B.W. [ed.

1992-09-01T23:59:59.000Z

113

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

114

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

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

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

117

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

118

The comprehensive Nuclear Test Ban Treaty and Seismological Research  

Science Journals Connector (OSTI)

...The predominant role for seismology will instead involve screening of all detected events to ensure that none of them are surreptitious nuclear explosions in violation of the Treaty. Applying seismology to detect nuclear explosions anywhere in the world is...

Thorne Lay

119

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

120

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

SciTech Connect

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

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

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions  

E-Print Network (OSTI)

1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium by Controlled-Potential Coulometry Plutonium by Amperometric Titration with Iron(II) Plutonium by Diode Array Spectrophotometry Free Acid by Titration in an Oxalate Solution 8 to 15 Free Acid by Iodate Precipitation-Potentiometric Titration Test Method 16 to 22 Uranium by Arsenazo I Spectrophotometric Test Method 23 to 33 Thorium by Thorin Spectrophotometric Test Method 34 to 42 Iron by 1,10-Phenanthroline Spectrophotometric Test Method 43 to 50 Impurities by ICP-AES Chloride by Thiocyanate Spectrophotometric Test Method 51 to 58 Fluoride by Distillation-Spectrophotometric Test Method 59 to 66 Sulfate by Barium Sulfate Turbidimetric Test Method 67 to 74 Isotopic Composition by Mass Spectrom...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

122

Preparation for the Recovery of Spent Nuclear Fuel (SNF) at Andreeva Bay, North West Russia - 13309  

SciTech Connect

Andreeva Bay is located near Murmansk in the Russian Federation close to the Norwegian border. The ex-naval site was used to de-fuel nuclear-powered submarines and icebreakers during the Cold War. Approximately 22,000 fuel assemblies remain in three Dry Storage Units (DSUs) which means that Andreeva Bay has one of the largest stockpiles of highly enriched spent nuclear fuel (SNF) in the world. The high contamination and deteriorating condition of the SNF canisters has made improvements to the management of the SNF a high priority for the international community for safety, security and environmental reasons. International Donors have, since 2002, provided support to projects at Andreeva concerned with improving the management of the SNF. This long-term programme of work has been coordinated between the International Donors and responsible bodies within the Russian Federation. Options for the safe and secure management of SNF at Andreeva Bay were considered in 2004 and developed by a number of Russian Institutes with international participation. This consisted of site investigations, surveys and studies to understand the technical challenges. A principal agreement was reached that the SNF would be removed from the site altogether and transported to Russia's reprocessing facility at Mayak in the Urals. The analytical studies provided the information necessary to develop the construction plan for the site. Following design and regulatory processes, stakeholders endorsed the technical solution in April 2007. This detailed the processes, facilities and equipment required to safely remove the SNF and identified other site services and support facilities required on the site. Implementation of this strategy is now well underway with the facilities in various states of construction. Physical works have been performed to address the most urgent tasks including weather protection over one of the DSUs, installation of shielding over the cells, provision of radiation protection infrastructure and general preparation of the site for construction of the facilities for the removal of the SNF. This paper describes the development and implementation of the strategy and work to improve the safe and secure management of SNF, preparing it for retrieval and removal from Andreeva Bay. (authors)

Field, D.; McAtamney, N. [Nuvia Limited (United Kingdom)] [Nuvia Limited (United Kingdom)

2013-07-01T23:59:59.000Z

123

Bibliography of reports by US Geological Survey personnel pertaining to underground nuclear testing and radioactive waste disposal at the Nevada Test Site, and radioactive waste disposal at the WIPP Site, New Mexico, January 1, 1979-December 31, 1979  

SciTech Connect

This bibliography presents reports released to the public between January 1, 1979, and December 31, 1979, by personnel of the US Geological Survey. Reports include information on underground nuclear testing and waste management projects at the NTS (Nevada Test Site) and radioactive waste projects at the WIPP (Waste Isolation Pilot Plant) site, New Mexico. Reports on Project Dribble, Tatum Dome, Mississippi, previously prepared as administrative reports and released to the public as 474-series reports during 1979 are also included in this bibliography.

Glanzman, V.M.

1980-01-01T23:59:59.000Z

124

Nuclear proliferation and testing: A tale of two treaties  

SciTech Connect

Despite progress in reducing stockpiles after the end of the Cold War, the disturbing actions of some nations could spread nuclear weapon capabilities and enlarge existing arsenals.

Corden, Pierce S.; Hafemeister, David

2014-04-01T23:59:59.000Z

125

Geologic constraints on clandestine nuclear testing in South Asia  

Science Journals Connector (OSTI)

...confidence in the monitoring of the test ban...central to any monitoring effort directed toward preventing surreptitious testing. We explore...would make the surreptitious disposal of so...area, requires monitoring for potential covert testing...

Dan M. Davis; Lynn R. Sykes

1999-01-01T23:59:59.000Z

126

New cold nuclear fusion theory and experimental tests  

Science Journals Connector (OSTI)

A theory of neutron-induced tritium-deuterium fusion at room temperature is developed, based entirely on previously measured cross-sections of known nuclear reactions. The fusion process involves self-sustaini...

Yeong E. Kim

1990-12-01T23:59:59.000Z

127

Geologic constraints on clandestine nuclear testing in South Asia  

Science Journals Connector (OSTI)

...strict limits on the development of highly compact and easily delivered multistage thermonuclear weapons and other advanced nuclear weaponry. High-yield thermonuclear weapons cannot be triggered by primaries of just a few kilotons (1), so a...

Dan M. Davis; Lynn R. Sykes

1999-01-01T23:59:59.000Z

128

Results from NNWSI [Nevada Nuclear Waste Storage Investigations] Series 2 bare fuel dissolution tests  

SciTech Connect

The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Two bare spent fuel specimens plus the empty cladding hulls were tested in NNWSI J-13 well water in unsealed fused silica vessels under ambient hot cell air conditions (25{degree}C) in the currently reported tests. One of the specimens was prepared from a rod irradiated in the H. B. Robinson Unit 2 reactor and the other from a rod irradiated in the Turkey Point Unit 3 reactor. Results indicate that most radionuclides of interest fall into three groups for release modeling. The first group principally includes the actinides (U, Np, Pu, Am, and Cm), all of which reached solubility-limited concentrations that were orders of magnitude below those necessary to meet the NRC 10 CFR 60.113 release limits for any realistic water flux predicted for the Yucca Mountain repository site. The second group is nuclides of soluble elements such as Cs, Tc, and I, for which release rates do not appear to be solubility-limited and may depend on the dissolution rate of fuel. In later test cycles, {sup 137}Cs, {sup 90}Sr, {sup 99}Tc, and {sup 129}I were continuously released at rates between about 5 {times} 10{sup {minus}5} and 1 {times} 10{sup {minus}4} of inventory per year. The third group is radionuclides that may be transported in the vapor phase, of which {sup 14}C is of primary concern. Detailed test results are presented and discussed. 17 refs., 15 figs., 21 tabs.

Wilson, C.N.

1990-09-01T23:59:59.000Z

129

Limited Test Ban Treaty | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home Limited Test Ban Treaty Limited Test Ban Treaty US Air Force Launches Satellite Carrying...

130

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

SciTech Connect

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

131

Retreating from the Nuclear Path Testing the theory of Prudential Realism to explain Nuclear Forbearance.  

E-Print Network (OSTI)

?? Conventional explanations for a states nuclear policy (acquisition or forbearance) may be found in traditional International Relations (IR) theories such as neorealism, neoliberal institutionalism (more)

Pillai, Anil, Ph.D.

2012-01-01T23:59:59.000Z

132

Evaluating summary statistics used to test for incomplete lineage sorting: mito-nuclear discordance in the reef  

E-Print Network (OSTI)

Evaluating summary statistics used to test for incomplete lineage sorting: mito-nuclear discordance and simulated data when testing drivers of mito-nuclear discordance in a statistical frame- work. While earlier for mitochon- drial COI. Coalescent simulations and neutrality tests suggested that mito-nuclear dis- cordance

Hellberg, Michael E.

133

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

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

support from Y-12. The test apparatus was essentially a uniquely designed thermonuclear test device, none of them were the same-all were unique designs. To keep pace with...

134

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

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

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

137

Status and development of magnetic mirror systems for nuclear testing applications  

SciTech Connect

Several system studies have concluded that the small size and steady-state nature of magnetic mirror systems provide attractive features of nuclear testing applications such as blanket testing, fissile fuel production, tritium production, or decontamination of high-level radioactive nuclear reactor wastes. A summary of the data base is presented, and next-generation experiments that could be carried out to explore plasma physics issues associated with the production of high neutron fluxes in magnetic mirror configurations are described.

Simonen, T.C.; Futch, A.H.; Kaiser, T.B.

1988-09-01T23:59:59.000Z

138

ACCELERATED TESTING OF NEUTRON-ABSORBING ALLOYS FOR NUCLEAR CRITICALITY CONTROL  

SciTech Connect

The US Department of Energy requires nuclear criticality control materials be used for storage of highly enriched spent nuclear fuel used in government programs and the storage of commercial spent nuclear fuel at the proposed High-Level Nuclear Waste Geological Repository located at Yucca Mountain, Nevada. Two different metallic alloys (Ni-Cr-Mo-Gd and borated stainless steel) have been chosen for this service. An accelerated corrosion test program to validate these materials for this application is described and a performance comparison is made.

Ronald E. Mizia

2011-10-01T23:59:59.000Z

139

Nuclear Nonproliferation and Arms Control Primer Prepared for the Blue Ribbon Commission on Americas Nuclear Future  

SciTech Connect

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

140

Test plan for preparing the Rapid Transuranic Monitoring Laboratory for field deployment  

SciTech Connect

This plan describes experimental work that will be performed during fiscal year 1994 to prepare the Rapid Transuranic Monitoring Laboratory (RTML) for routine field use by US Department of Energy (DOE) Environmental Restoration and Waste Management programs. The RTML is a mobile, field-deployable laboratory developed at the Idaho National Engineering Laboratory (INEL) that provides a rapid, cost-effective means of characterizing and monitoring radioactive waste remediation sites for low-level radioactive contaminants. Analytical instruments currently installed in the RTML include an extended-range, germanium photon analysis spectrometer with an automatic sample changer; two, large-area, ionization chamber alpha spectrometers; and four alpha continuous air monitors. The RTML was field tested at the INEL during June 1993 in conjunction with the Buried Waste Integrated Demonstration`s remote retrieval demonstration. The major tasks described in this test plan are to (a) evaluate the beta detectors for use in screening soil samples for {sup 90}Sr, (b) upgrade the alpha spectral analysis software programs, and (c) upgrade the photon spectral analysis software programs.

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.

1994-04-01T23:59:59.000Z

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

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

142

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

143

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 54, NO. 4, AUGUST 2007 1285 Radiographic Testing of Anomalies in Thick  

E-Print Network (OSTI)

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 54, NO. 4, AUGUST 2007 1285 Radiographic Testing-flattening, image processing, nondestructive testing, nuclear imaging, radiography, scattering. I. INTRODUCTION A in the context of primary loop piping inspection in pressurized water nuclear reactors. In a more gen- eral way

Robini, Marc - Pôle de Mathématiques, Institut National des Sciences Appliquées de Lyon

144

Rehabilitation of the former nuclear test sites at Maralinga  

SciTech Connect

The Department of Primary Industries and Energy, Canberra, has commenced tendering procedures for appointment of a Project Management Organisation for the Rehabilitation of the former British atomic weapon test sites at Maralinga and Emu in South Australia. This paper gives a historical background to the atomic tests, and reports scientific and engineering studies conducted by the Technical Assessment Group (TAG) to define practical and economic options for rehabilitation of the former test sites. The rehabilitation option preferred by the Australian Government will focus on removal and burial of soil and fragments highly contaminated with plutonium oxide, and erection of warning fences around areas where permanent residence will not be permitted. The application of in-situ vitrification is under investigation for stabilisation of twenty one disposal pits containing up to twenty kilograms of plutonium at Taranaki.

Costello, J.M.; Davoren, P.J.

1994-12-31T23:59:59.000Z

145

Geologic constraints on clandestine nuclear testing in South Asia  

Science Journals Connector (OSTI)

...monitoring effort directed toward preventing surreptitious testing. We explore conditions in the subcontinent...combination, these factors would make the surreptitious disposal of so much brine unlikely. Because the...activity that could serve as a cover for surreptitious solution mining is lacking. Furthermore...

Dan M. Davis; Lynn R. Sykes

1999-01-01T23:59:59.000Z

146

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

SciTech Connect

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

147

(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

148

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

149

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

150

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

151

Extensive remote handling and conservative plasma conditions to enable fusion nuclear science R&D using a component testing facility  

E-Print Network (OSTI)

nuclear science R&D using a component testing facility Y.K.M. Peng 1), T.W. Burgess 1), A.J. Carroll 1), C. This use aims to test components in an integrated fusion nuclear environment, for the first time@ornl.gov Abstract. The use of a fusion component testing facility to study and establish, during the ITER era

Princeton Plasma Physics Laboratory

152

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...

153

Potential use of the Large Coil Test Facility (LCTF) for testing of ion thrusters for nuclear electric propulsion  

SciTech Connect

Nuclear Electric Propulsion (NEP) is one of several supporting technologies identified as necessary for exploration of the planets. At a workshop held in June 1990, experts from national laboratories and industry identified approximately a dozen reactor concepts to produce electric power to drive ion thrusters which convert the electricity into propulsion. Subsequent to the workshop, a DOE-sponsored facilities panel toured U.S. facilities where the technologies might be developed and tested. The Large Coil Test Facility (LCTF) at Oak Ridge National Laboratory (ORNL) is an attractive option for testing of ion thrusters. This paper reviews the thruster concepts proposed, discusses key features of the LCTF, and outlines how thruster testing could be performed in this facility.

Homan, F.J.; Lubell, M.S.; Schwenterly, S.W.; Whealton, J.H. (Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States))

1993-01-20T23:59:59.000Z

154

Fallout of atmospheric nuclear tests in 1950s and 1960s exposed more people to Iodine-131 than Chernobyl accident  

SciTech Connect

A National Cancer Institute report on I-131 radiation exposure from atmospheric nuclear weapon tests in the USA is summarized. (AIP)

Goodwin, I. [Physics Today, American Center for Physics, One Physics Ellipse, College Park, Maryland 20740-3843 (United States)

1997-09-01T23:59:59.000Z

155

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions  

E-Print Network (OSTI)

1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

American Society for Testing and Materials. Philadelphia

1999-01-01T23:59:59.000Z

156

Testing QCD Plasma Formation by Pion Correlations in Relativistic Nuclear Collisions  

Science Journals Connector (OSTI)

To test the formation of a deconfined QCD plasma in relativistic nuclear collisions, we propose measuring the charge anticorrelations of pions of similar momenta. These anticorrelations will be greatly weakened by plasma formation, and their kinematic characteristics will also change in a predicted way.

Jorge A. Lopez; Jitendra C. Parikh; Philip J. Siemens

1984-09-24T23:59:59.000Z

157

Hydrogen loops in existing reactors for testing fuel elements for nuclear propulsion  

Science Journals Connector (OSTI)

The Space Exploration Initiative (SEI) has revitalized interest in adapting nuclear energy for power and propulsion. Prior to the selection of a nuclear thermal propulsion (NTP) system extensive testing of the various proposed concepts will be required. In todays environmental safety and health culture full size rocket engine tests as were done under the Rover/NERVA program will be extremely difficult and expensive to perform and meet NASAs schedules. A different test strategy uses a hydrogen loop in an existing reactor to test a wide variety of single elements or clusters of elements for fuel qualification. This approach is expected to reduce operating and capital costs and expedite the testing schedule. This paper examines the potential of performing subscale tests in a hydrogen loop in an existing reactor such as the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory or the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory. The HFIR is expected to achieve power densities comparable to those achieved in ATR because of the 85 MWt power level and the high thermal and fast flux levels. The available length and diameter of the test region of FHIR are 60 cm and 10 cm whereas the available length and diameter of the test region of ATR are 120 cm and 12 cm respectively.

Charles S. Olsen; Henry Welland; James Abraschoff; Kenneth Thoms

1993-01-01T23:59:59.000Z

158

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

159

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

2013-01-01T23:59:59.000Z

160

Voices of Four Taiwanese College Students' Experiences with the Test of English for International Communication (TOEIC) Preparation (PREP) Computer Assisted Language Learning (CALL)  

E-Print Network (OSTI)

emerged from the study: (a) students motivations derived from their English learning backgrounds, (b) online learning and flexible scheduling, (c) language test preparation through online learning, and (d) improving performance on the TOEIC test...

Chen, To-Yu

2014-02-19T23:59:59.000Z

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.


161

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

162

Post?installation activities in the Comprehensive Nuclear Test Ban Treaty (CTBT) International Monitoring System (IMS) infrasound network  

Science Journals Connector (OSTI)

The provisional operation and maintenance of IMS infrasound stations after installation and subsequent certification has the objective to prepare the infrasound network for entry into force of the Comprehensive Nuclear?Test?Ban Treaty (CTBT). The goal is to maintain and fine tune the technical capabilities of the network to repair faulty equipment and to ensure that stations continue to meet the minimum specifications through evaluation of data quality and station recalibration. Due to the globally dispersed nature of the network this program constitutes a significant undertaking that requires careful consideration of possible logistic approaches and their financial implications. Currently 11 of the 60 IMS infrasound stations are transmitting data in the post?installation Testing & Evaluation mode. Another 5 stations are under provisional operation and are maintained in post?certification mode. It is expected that 20% of the infrasound network will be certified by the end of 2002. This presentation will focus on the different phases of post?installation activities of the IMS infrasound program and the logistical challenges to be tackled to ensure a cost?efficient management of the network. Specific topics will include Testing & Evaluation and Certification of Infrasound Stations as well as Configuration Management and Network Sustainment.

2002-01-01T23:59:59.000Z

163

R t f N l C t T ti Di i GReport of Nuclear Component Testing Discussion Group National Spherical Torus ProgramNational Spherical Torus Program  

E-Print Network (OSTI)

Office of Science R t f N l C t T ti Di i GReport of Nuclear Component Testing Discussion Group nuclear technology, SG1 leader UCLA DOE contact: Eckstrand, Steve, OFES #12;Nuclear Component Testing (NCT) aims to complement ITER mission and fill many DEMO R&D gaps · Mission of the Nuclear Component Testing

164

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

165

Full-Scale Accident Testing in Support of Used Nuclear Fuel Transportation.  

SciTech Connect

The safe transport of spent nuclear fuel and high-level radioactive waste is an important aspect of the waste management system of the United States. The Nuclear Regulatory Commission (NRC) currently certifies spent nuclear fuel rail cask designs based primarily on numerical modeling of hypothetical accident conditions augmented with some small scale testing. However, NRC initiated a Package Performance Study (PPS) in 2001 to examine the response of full-scale rail casks in extreme transportation accidents. The objectives of PPS were to demonstrate the safety of transportation casks and to provide high-fidelity data for validating the modeling. Although work on the PPS eventually stopped, the Blue Ribbon Commission on Americas Nuclear Future recommended in 2012 that the test plans be re-examined. This recommendation was in recognition of substantial public feedback calling for a full-scale severe accident test of a rail cask to verify evaluations by NRC, which find that risk from the transport of spent fuel in certified casks is extremely low. This report, which serves as the re-assessment, provides a summary of the history of the PPS planning, identifies the objectives and technical issues that drove the scope of the PPS, and presents a possible path for moving forward in planning to conduct a full-scale cask test. Because full-scale testing is expensive, the value of such testing on public perceptions and public acceptance is important. Consequently, the path forward starts with a public perception component followed by two additional components: accident simulation and first responder training. The proposed path forward presents a series of study options with several points where the package performance study could be redirected if warranted.

Durbin, Samuel G.; Lindgren, Eric R.; Rechard, Rob P.; Sorenson, Ken B.

2014-09-01T23:59:59.000Z

166

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

167

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

168

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

169

Analysis of Operation TEAPOT nuclear test BEE radiological and meteorological data  

SciTech Connect

This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the BEE nuclear test of Operation TEAPOT. Inconsistencies in the radiological data and their resolution are discussed. The methods of normalizing the radiological data to a standard time and estimating fallout-arrival times are presented. The meteorological situations on event day and the following day are described. A comparison of the WSNSO fallout analysis with an analysis performed in the 1950's is presented. The radiological data used to derive the WSNSO fallout pattern are tabulated in an appendix.

Quinn, V.E.

1986-08-01T23:59:59.000Z

170

Analysis of operation TEAPOT nuclear test ZUCCHINI radiological and meterological data  

SciTech Connect

This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the ZUCCHINI nuclear test of Operation TEAPOT. Inconsistencies in the radiological data and their resolution are discussed. The methods of normalizing the radiological data to a standard time and estimating fallout-arrival times are presented. The meteorological situations on event day and the following day are described. A comparison of the WSNSO fallout analysis with an analysis performed in the 1950's is presented. The radiological data used to derive the WSNSO 1986 fallout pattern are tabulated in an appendix.

Quinn, V.E.

1987-03-01T23:59:59.000Z

171

GIS surface effects archive of underground nuclear detonations conducted at Yucca Flat and Pahute Mesa, Nevada Test Site, Nevada  

SciTech Connect

This report presents a new comprehensive, digital archive of more than 40 years of geologic surface effects maps produced at individual detonation sites throughout the Yucca Flat and Pahute Mesa nuclear testing areas of the Nevada Test Site, Nye County, Nevada. The Geographic Information System (GIS) surface effects map archive on CD-ROM (this report) comprehensively documents the surface effects of underground nuclear detonations conducted at two of the most extensively used testing areas of the Nevada Test Site. Between 1951 and 1992, numerous investigators of the U.S. Geological Survey, the Los Alamos National Laboratory, the Lawrence Livermore National Laboratory, and the Defense Threat Reduction Agency meticulously mapped the surface effects caused by underground nuclear testing. Their work documented the effects of more than seventy percent of the underground nuclear detonations conducted at Yucca Flat and all of the underground nuclear detonations conducted at Pahute Mesa.

Grasso, D.N.

2001-11-02T23:59:59.000Z

172

Preparation of nuclear libraries with deterministic and stochastic methods for LWR reflectors  

SciTech Connect

The explicit reflector methodology is used in the system of codes CASMO-5 / SIMULATE-3 to include the reflector around the active core into the computational region and avoid adopting any ad-hoc or experimental albedo coefficients as boundary conditions. However, to complete the core calculation, a set of cross sections and discontinuity factors is needed for the reflector nodes and the accuracy of these nuclear parameters influences the final results, in particular along the peripheral regions of the core. In this paper the explicit reflector methodology of CASMO-5 is adopted to evaluate the few-group cross sections and discontinuity factors of the different reflector cases, based on the design of Generation II and III LWR reactors. In addition, in the perspective of using Monte-Carlo codes as a complementary option for lattice calculations of reflector configurations, the stochastic SERPENT code is also included as part of this benchmark. With the latter, the impact of applying 2-D reflector models with homogenized materials instead of explicit representation of the real geometrical structures is moreover evaluated and shown to be limited. (authors)

Canepa, S.; Hursin, M.; Ferroukhi, H.; Pautz, A. [Paul Scherrer Institut PSI, 5232, Villigen PSI (Switzerland)

2013-07-01T23:59:59.000Z

173

Preparation of a soluble antigen from Theileria cervi and its application to various serologic tests  

E-Print Network (OSTI)

. Thirty-four serums obtained from six deer infected with T . cervi were used in the CF and HA tests. Both tests detected the presence of antibody to the parasite . Two precipitin tests; the ring precipitin and the agar gel diffusion tests gave no valid... that of many bacterial diseases where the concept of protective antibody is applicable and accepted . They postulate that the production of the antibody in detectable quantities is dependent on a certain stage of the growth and development cycle...

Corry, George Lowry

2012-06-07T23:59:59.000Z

174

Application of Wald's sequential probability ratio test to nuclear materials control  

SciTech Connect

We have replaced traditional analysis methods for nuclear material control monitoring with hypothesis testing, specifically with Wald's sequential-probability-ratio test. Our evaluation of Walds'd method, applied in both vehicle and pedestrian SNM monitors, is by Monte Carlo calculation to determine the alarm probability and average monitoring times of the monitors. The vehicle monitor with Wald's test has a much shorter monitoring delay than with traditional methods, without serious compensating changes in operating characteristics. The pedestrian monitor with Wald's method also has advantages over traditional single-interval test, in that the Wald method duplicates the advantages of a moving-average technique. We verified the Monte Carlo calculations for the pedestrian monitor by means of a special program for the monitor's microprocessor controller. The observations of false-alarm probability and average monitoring time for over 500,000 tests verified the Monte Carlo results.

Fehlau, P.E.; Coop, K.L.; Markin, J.T.

1984-01-01T23:59:59.000Z

175

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

176

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

177

Microsoft Word - 911133_0 SSC-1 Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for Reactor Control Equipment Prepared by General Atomics For the Battelle Energy...

178

Microsoft Word - 911141_0_SSC-9 RCCS Test Plan.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for the Reactor Cavity Cooling System Prepared by General Atomics For the Battelle...

179

Microsoft Word - 911147_0_SSC-16 RPS IPS and PCDIS Test Plan...  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for RPS, IPS and PCDIS Prepared by General Atomics For the Battelle Energy...

180

Microsoft Word - 911140_0_SCHE Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Shutdown Cooling Heat Exchanger Prepared by General Atomics For the Battelle...

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

Microsoft Word - 911135_0 SSC-4a Reactor Core Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for the Reactor Core Assembly Prepared by General Atomics For the Battelle Energy...

182

Microsoft Word - 911134_0 SSC-2 Control Rod Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Control Rods Prepared by General Atomics For the Battelle Energy Alliance, LLC...

183

Microsoft Word - 911143_0_SSC-11 PCS Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Power Conversion System Equipment for a Direct Combined Cycle Prepared by...

184

Microsoft Word - 911137_0 SSC-5 RPV Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Reactor Pressure Vessel Prepared by General Atomics For the Battelle Energy...

185

Microsoft Word - 911136_0 SSC-4b Reactor Graphite Test Plan_rel...  

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

Services for the Next Generation Nuclear Plant (NGNP) with Hydrogen Production Test Plan for Reactor Graphite Elements Prepared by General Atomics for the Battelle Energy...

186

Microsoft Word - 911138_0_SSC-6 Helium Circulator Test Plan_rel...  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for Helium Circulators (PHTS, SCS, SHTS) Prepared by General Atomics For the...

187

Microsoft Word - 911145_0_SSC-14 FHSS Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Fuel Handling and Storage System Prepared by General Atomics For the Battelle...

188

Microsoft Word - 911144_0_SSC-13 S-I HPS Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan for S-I Hydrogen Production System (HPS) Prepared by General Atomics For the...

189

Microsoft Word - 911139_0_SSC-7 IHX Test Plan_rel.doc  

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

SERVICES FOR THE NEXT GENERATION NUCLEAR PLANT (NGNP) WITH HYDROGEN PRODUCTION Test Plan - Intermediate Heat Exchanger PCHE Type Prepared by General Atomics For the...

190

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

191

Acoustic Emission Monitoring of ASME Section III Hydrostatic Test: Watts Bar Unit 1 Nuclear Reactor  

SciTech Connect

Through the cooperation of the Tennessee Valley Authority, Pacific Northwest Laboratory has installed instrumentation on Watts Bar Nuclear Power Plant Unit 1 for the purpose of test and evaluation of acoustic emission (AE) monitoring of nuclear reactor pressure vessels and piping for flaw detection. This report describes the acoustic emission monitoring performed during the ASME Section III hydrostatic testing of Watts Bar Nuclear Power Plant Unit 1 and the results obtained. Highlights of the results are: Spontaneous AE was detected from a nozzle area during final pressurization. Evaluation of the apparent source of the spontaneous AE using an empirically derived AE/fracture mechanics relationship agreed within a factor of two with an evaluation by ASME Section XI Code procedures. AE was detected from a fracture specimen which was pressure coupled to the 10-inch accumulator nozzle. This provided reassurance of adequate system sensitivity. High background noise was observed when all four reactor coolant pumps were operating. Work is continuing at Watts Bar Unit 1 toward AE monitoring hot functional testing and subsequently monitoring during reactor operation.

Hutton,, P. H.; Taylor,, T. T.; Dawson,, J. F.; Pappas,, R. A.; Kurtz,, R. J.

1982-06-01T23:59:59.000Z

192

Policing the peace: How nations will monitor a nuclear test ban  

SciTech Connect

Steve R. Bratt`s belt started chirping as if on cue, precisely as he was boasting about a new global watchdog system for detecting nuclear tests. Bratt, a seismologist with the US Department of Defense, retrieved the beeper from his hip and studied it for a few seconds. {open_quotes}I`ve got an alert. It`s from Lop Nor. Lop Nor is the Chinese test site,{close_quotes} he explained. Two stations in a worldwide network of seismometers had just picked up vibrations emanating from central Asia, near China`s known nuclear facility. The shock was small, about magnitude 3.5. In bomb equivalents, it would correspond to less than a half kiloton explosion. In this case, however, Bratt suspected the alert was just a minor earthquake. Timing provided an important clue: The shock had originated at 12:19 Greenwich Mean Time, which is not the kind of round, on-the-hour time that countries usually choose for performing a major weapon test. Seismic analysts would later confirm Bratt`s hunch when they determined that the Chinese vibrations actually originated at an unlikely place to stage a test, hundreds of kilometers away from the Lop Nor site. The impromptu demonstration nonetheless made a good advertisement for the new international monitoring system-an ever-figilant network of sensors strung around the globe, listening, sniffing, and waiting. This article describes the problems involved in test ban monitoring and the possibilities for solving them.

Monastersky, R.

1996-05-11T23:59:59.000Z

193

Ultrahlgh?Temperature Hydrogen Exposure Testing of Nuclear Fuel in Russia  

Science Journals Connector (OSTI)

The world's most complete facility for ex?reactor ultrahigh?temperature hydrogen exposure testing is located at the Research Institute of SLA Lutch in Podolsk Moscow Region Russia. This facility has been utilized for a number of years for testing high?temperature nuclear fuels for the now?defunct Soviet space program and recent work was performed there under contract for Babcock & Wilcox. Capabilities of the facility are presented. The work performed for B&W is summarized as one example. (U Zr Nb)C fuel spheres with and without ZrC coatings were exposed to flowing hydrogen at 5 atm for 30 minutes at 3150 K followed by thermal survivability testing at 3500 K in static helium. Both the test facility and the fuel performed superbly.

Robert Evans; Russell Jensen; Marat Tishchenko; Victor Daragan

1994-01-01T23:59:59.000Z

194

Standard test method for analysis of isotopic composition of uranium in nuclear-grade fuel material by quadrupole inductively coupled plasma-mass spectrometry  

E-Print Network (OSTI)

1.1 This test method is applicable to the determination of the isotopic composition of uranium (U) in nuclear-grade fuel material. The following isotopic weight percentages are determined using a quadrupole inductively coupled plasma-mass spectrometer (Q-ICP-MS): 233U, 234U, 235U, 236U, and 238U. The analysis can be performed on various material matrices after acid dissolution and sample dilution into water or dilute nitric (HNO3) acid. These materials include: fuel product, uranium oxide, uranium oxide alloys, uranyl nitrate (UNH) crystals, and solutions. The sample preparation discussed in this test method focuses on fuel product material but may be used for uranium oxide or a uranium oxide alloy. Other preparation techniques may be used and some references are given. Purification of the uranium by anion-exchange extraction is not required for this test method, as it is required by other test methods such as radiochemistry and thermal ionization mass spectroscopy (TIMS). This test method is also described i...

American Society for Testing and Materials. Philadelphia

2000-01-01T23:59:59.000Z

195

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

196

Neptunium Transport Behavior in the Vicinity of Underground Nuclear Tests at the Nevada Test Site  

SciTech Connect

We used short lived {sup 239}Np as a yield tracer and state of the art magnetic sector ICP-MS to measure ultra low levels of {sup 237}Np in a number of 'hot wells' at the Nevada National Security Site (NNSS), formerly known as the Nevada Test Site (NTS). The results indicate that {sup 237}Np concentrations at the Almendro, Cambric, Dalhart, Cheshire and Chancellor sites, are in the range of 3 x 10{sup -5} to 7 x 10{sup -2} pCi/L and well below the MCL for alpha emitting radionuclides (15 pCi/L) (EPA, 2009). Thus, while Np transport is believed to occur at the NNSS, activities are expected to be well below the regulatory limits for alpha-emitting radionuclides. We also compared {sup 237}Np concentration data to other radionuclides, including tritium, {sup 14}C, {sup 36}Cl, {sup 99}Tc, {sup 129}I, and plutonium, to evaluate the relative {sup 237}Np transport behavior. Based on isotope ratios relative to published unclassified Radiologic Source Terms (Bowen et al., 1999) and taking into consideration radionuclide distribution between melt glass, rubble and groundwater (IAEA, 1998), {sup 237}Np appears to be substantially less mobile than tritium and other non-sorbing radionuclides, as expected. However, this analysis also suggests that {sup 237}Np mobility is surprisingly similar to that of plutonium. The similar transport behavior of Np and Pu can be explained by one of two possibilities: (1) Np(IV) and Pu(IV) oxidation states dominate under mildly reducing NNSS groundwater conditions resulting in similar transport behavior or (2) apparent Np transport is the result of transport of its parent {sup 241}Pu and {sup 241}Am isotopes and subsequent decay to {sup 237}Np. Finally, measured {sup 237}Np concentrations were compared to recent Hydrologic Source Term (HST) models. The 237Np data collected from three wells in Frenchman Flat (RNM-1, RNM-2S, and UE-5n) are in good agreement with recent HST transport model predictions (Carle et al., 2005). The agreement provides confidence in the results of the predictive model. The comparison to Cheshire HST model predictions (Pawloski et al, 2001) is somewhat ambiguous due to the low concentration resolution of the particle transport model.

Zhao, P; Tinnacher, R M; Zavarin, M; Williams, R W; Kersting, A B

2010-12-03T23:59:59.000Z

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

Blast induced subsidence in the craters of nuclear tests over coral  

SciTech Connect

The craters from high-yield nuclear tests at the Pacific Proving Grounds are very broad and shallow in comparison with the bowl-shaped craters formed in continental rock at the Nevada Test Site and elsewhere. Attempts to account for the differences quantitatively have been generally unsatisfactory. We have for the first time successfully modeled the Koa Event, a representative coral-atoll test. On the basis of plausible assumptions about the geology and about the constitutive relations for coral, we have shown that the size and shape of the Koa crater can be accounted for by subsidence and liquefaction phenomena. If future studies confirm these assumptions, it will mean that some scaling formulas based on data from the Pacific will have to be revised to avoid overestimating weapons effects in continental geology. 9 refs., 5 figs.

Burton, D.E.; Swift, R.P.; Glenn, H.D.; Bryan, J.B.

1985-02-01T23:59:59.000Z

199

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

SciTech Connect

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

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

1987-01-01T23:59:59.000Z

200

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

2013-01-01T23:59:59.000Z

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.


201

CONTROL TESTING OF THE UK NATIONAL NUCLEAR LABORATORY'S RADBALL TECHNOLOGY AT SAVANNAH RIVER NATIONAL LABORATORY  

SciTech Connect

The UK National Nuclear Laboratory (NNL) has developed a remote, non-electrical, radiation-mapping device known as RadBall (patent pending), which offers a means to locate and quantify radiation hazards and sources within contaminated areas of the nuclear industry. To date, the RadBall has been deployed in a number of technology trials in nuclear waste reprocessing plants at Sellafield in the UK. The trials have demonstrated the successful ability of the RadBall technology to be deployed and retrieved from active areas. The positive results from these initial deployment trials and the anticipated future potential of RadBall have led to the NNL partnering with the Savannah River National Laboratory (SRNL) to further underpin and strengthen the technical performance of the technology. RadBall consists of a colander-like outer shell that houses a radiation-sensitive polymer sphere. It has no power requirements and can be positioned in tight or hard-to reach places. The outer shell works to collimate radiation sources and those areas of the polymer sphere that are exposed react, becoming increasingly less transparent, in proportion to the absorbed dose. The polymer sphere is imaged in an optical-CT scanner which produces a high resolution 3D map of optical attenuation coefficients. Subsequent analysis of the optical attenuation maps provides information on the spatial distribution and strength of the sources in a given area forming a 3D characterization of the area of interest. This study completed at SRNL addresses key aspects of the testing of the RadBall technology. The first set of tests was performed at Savannah River Nuclear Solutions Health Physics Instrument Calibration Laboratory (HPICL) using various gamma-ray sources and an x-ray machine with known radiological characteristics. The objective of these preliminary tests was to identify the optimal dose and collimator thickness. The second set of tests involved a highly contaminated hot cell. The objective of this part of the testing was to characterize a hot cell with unknown radiation sources. The RadBall calibration experiments and hot cell deployment completed at SRNL were successful in that for each trial, the technology was able to locate the radiation sources. The NNL believe that the ability of RadBall to be remotely deployed with no electrical supplies into difficult to access areas of plant and locate and quantify radiation hazards is a unique radiation mapping service. The NNL consider there to be significant business potential associated with this innovative technology.

Farfan, E.

2009-11-23T23:59:59.000Z

202

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

203

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

SciTech Connect

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

204

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

205

Dose assessment, radioecology, and community interaction at former nuclear test sites  

SciTech Connect

The US conducted a nuclear testing program at Bikini and Enewetak Atolls in the Marshall Islands from 1946 through 1958. A total of 66 nuclear devices were tested--23 at Bikini Atoll (total yield of 77 megatons) and 43 at Enewetak Atoll (total yield of 33 megatons). This resulted in contamination of many of the islands at each atoll. The BRAVO test (yield 15 megatons) on March 1, 1954 contaminated several atolls to the east of Bikini Atoll some of which were inhabited. The author has conducted an experimental, monitoring, and dose assessment program at atolls in the northern Marshall Islands for the past 20 years. The goals have been to: (1) determine the radiological conditions at the atolls; (2) provide dose assessments for resettlement options and alternate living patterns; (3) develop and evaluate remedial measures to reduce the dose to people reinhabiting the atolls; and (4) discuss the results with each of the communities and the Republic of the Marshall Islands government officials to help them understand the data as a basis for resettlement decisions. The remaining radionuclides at the atolls that contribute any significant dose are {sup 137}Cs, {sup 90}Sr, {sup 239+240}Pu, and {sup 241}Am.

Robison, W.L.

1994-11-01T23:59:59.000Z

206

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

SciTech Connect

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

207

On the relationship between whole body, extremity and eye lens doses for medical staff in the preparation and application of radiopharmaceuticals in nuclear medicine  

Science Journals Connector (OSTI)

We performed individual dose measurements, in terms of Hp(10) for the whole body, Hp(0,07) for the extremities (hands) and Hp(3) for the eyes, for medical personnel (technical staff, nurses and medical doctors) in three nuclear medicine departments. One conventional diagnostic scintigraphy department, where Tc-99m, I-131 and Sm-153 were applied, and two PET-CT departments where F-18 was applied in preparation and application procedures, were studied. A novel eye lens dosemeter was used, designed to evaluate Hp(3) directly. From our measurements we obtained ratios of Hp(3)/Hp(10) ranging between 0.7 and 1.1 indicating that in nuclear medicine procedures eye lens doses could probably be estimated from Hp(10) values and that exceeding the present annual dose limit to eye lens (150mSv) is very unlikely. The relationship between different individual doses can indicate the quality of radiation protection in a nuclear medicine department.

R. Kopec; M. Budzanowski; A. Budzy?ska; R. Czepczynski; M. Dziuk; J. Sowinski; A. Wyszomirska

2011-01-01T23:59:59.000Z

208

SPACE-R nuclear power system TFE mock-up SC-320 demonstration test  

SciTech Connect

As a result of its 1993{endash}94 work, NII NPO {open_quote}{open_quote}LUCH{close_quote}{close_quote} developed a thermionic fuel element (TFE) SC-320 intended for use as part of a nuclear thermionic reactor-converter known as SPACE-R designed in the US and rated at 40 kW of output electric power. This paper presents the results of the demonstration electric power tests of the SC-320 TFE mock-up conducted in the US at the TSET testing facility located at the University of New Mexico. The data obtained are compared to the calculated characteristics as well as the output parameters of the Topaz-2 NPS TFEs. {copyright} {ital 1996 American Institute of Physics.}

Nikolaev, Y.V.; Eremin, S.A.; Kolesov, V.S.; Lapochkin, N.V.; Izhvanov, O.L.; Semin, R.N.; Androsov, V.N.; Agafonov, V.N. [Research Institute of SIA ``LUCH``, Podolsk (Russian Federation); Koester, J.K. [Space Power Incorporated, 621 River Oaks Parkway, San-Jose, California 95134 (United States)

1996-03-01T23:59:59.000Z

209

Method for testing the strength and structural integrity of nuclear fuel particles  

DOE Patents (OSTI)

An accurate method for testing the strength of nuclear fuel particles. Each particle includes an upper and lower portion, and is placed within a testing apparatus having upper and lower compression members. The upper compression member includes a depression therein which is circular and sized to receive only part of the upper portion of the particle. The lower compression member also includes a similar depression. The compression members are parallel to each other with the depressions therein being axially aligned. The fuel particle is then placed between the compression members and engaged within the depressions. The particle is then compressed between the compression members until it fractures. The amount of force needed to fracture the particle is thereafter recorded. This technique allows a broader distribution of forces and provides more accurate results compared with systems which distribute forces at singular points on the particle.

Lessing, Paul A. (Idaho Falls, ID)

1995-01-01T23:59:59.000Z

210

Method for testing the strength and structural integrity of nuclear fuel particles  

DOE Patents (OSTI)

An accurate method for testing the strength of nuclear fuel particles is disclosed. Each particle includes an upper and lower portion, and is placed within a testing apparatus having upper and lower compression members. The upper compression member includes a depression therein which is circular and sized to receive only part of the upper portion of the particle. The lower compression member also includes a similar depression. The compression members are parallel to each other with the depressions therein being axially aligned. The fuel particle is then placed between the compression members and engaged within the depressions. The particle is then compressed between the compression members until it fractures. The amount of force needed to fracture the particle is thereafter recorded. This technique allows a broader distribution of forces and provides more accurate results compared with systems which distribute forces at singular points on the particle. 13 figs.

Lessing, P.A.

1995-10-17T23:59:59.000Z

211

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 Level 2 proficiency in performing and interpreting cardiac nuclear imaging tests. Progression

Ford, James

212

SPACE-R nuclear power system SC-320 thermionic fuel element performance tests  

SciTech Connect

In 1993 and 1994, the Russian Scientific Research Institute NII NPO ``LUCH`` and Space Power, Inc., (SPI), of San Jose, California, developed a prototype of the single-cell thermionic fuel element (TFE) for the SPACE-R space nuclear power system (NPS). The SPACE-R system was designed as a part of the US Department of Energy`s (DOE) Space Reactor Development Program to develop a long life, space reactor system capable of supplying up to 40 kW(e) output power. The jointly developed SC-320 TFE is a prototype of the next generation thermionic converter for nuclear applications in space. This paper presents the results of the initial demonstration tests and subsequent parametric evaluations conducted on the SC-320 TFE as compared to the calculated performance characteristics. The demonstration tests were conducted jointly by Russian and American specialists at the Thermionic Evaluation Facility (TEF) at the New Mexico Engineering Research Institute (NMERI) of the University of New Mexico in Albuquerque.

Luchau, D.W.; Bruns, D.R. [Team Specialty Services, Inc., Albuquerque, NM (United States); Nikolaev, Y.V. [SIA LUCH Scientific Research Inst., Podolsk (Russian Federation)] [and others

1996-12-31T23:59:59.000Z

213

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

214

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.

215

A micro hot test of the Chalmers-GANEX extraction system on used nuclear fuel  

SciTech Connect

In the present study, a 'micro hot test' has been performed using the Chalmers-GANEX (Group Actinide Extraction) system for partitioning of used nuclear fuel. The test included a pre-extraction step using N,N-di-2- ethylhexyl-butyramide (DEHBA) in n-octanol to remove the bulk part of the uranium. This pre-extraction was followed by a group extraction of actinides using the mixture of TBP and CyMe{sub 4}-BTBP in cyclohexanone as suggested in the Chalmers-GANEX process, and a three stage stripping of the extracted actinides. Distribution ratios for the extractions and stripping were determined based on a combination of ?- and ?-spectrometry, as well as ICP-MS measurements. Successful extraction of uranium, plutonium and the minor actinides neptunium, americium and curium was achieved. However, measurements also indicated that co-extraction of europium occurs to some extent during the separation. These results were expected based on previous experiments using trace concentrations of actinides and lanthanides. Since this test was only performed in one stage with respect to the group actinide extraction, it is expected that multi stage tests will give even better results. (authors)

Bauhn, L.; Hedberg, M.; Aneheim, E.; Ekberg, C.; Loefstroem-Engdahl, E.; Skarnemark, G. [Department of Chemical and Biological Engineering, Nuclear Chemistry, Chalmers University of Technology, Kemivaegen 4, SE-412 96 Goeteborg (Sweden)

2013-07-01T23:59:59.000Z

216

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

217

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

SciTech Connect

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

218

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

SciTech Connect

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

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

2012-07-01T23:59:59.000Z

219

STRONTIUM AND ACTINIDE SEPARATIONS FROM HIGH LEVEL NUCLEAR WASTE SOLUTIONS USING MONOSODIUM TITANATE 1. SIMULANT TESTING  

SciTech Connect

High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 137}Cs, {sup 90}Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for {sup 137}Cs removal, and ion exchange/sorption of {sup 90}Sr and alpha-emitting radionuclides with an inorganic material, monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes {sup 238}Pu, {sup 239}Pu and {sup 240}Pu. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from simulated waste solutions. These tests evaluated the influence of ionic strength, temperature, solution composition and the oxidation state of plutonium.

HOBBS, D. T.; BARNES, M. J.; PULMANO, R. L.; MARSHALL, K. M.; EDWARDS, T. B.; BRONIKOWSKI, M. G.; FINK, S. D.

2005-04-14T23:59:59.000Z

220

Standard test methods for chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide  

E-Print Network (OSTI)

1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide powder and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Total Carbon by Combustion and Gravimetry 7-17 Total Boron by Titrimetry 18-28 Isotopic Composition by Mass Spectrometry 29-38 Chloride and Fluoride Separation by Pyrohydrolysis 39-45 Chloride by Constant-Current Coulometry 46-54 Fluoride by Ion-Selective Electrode 55-63 Water by Constant-Voltage Coulometry 64-72 Impurities by Spectrochemical Analysis 73-81 Soluble Boron by Titrimetry 82-95 Soluble Carbon by a Manometric Measurement 96-105 Metallic Impurities by a Direct Reader Spectrometric Method 106-114

American Society for Testing and Materials. Philadelphia

2004-01-01T23:59:59.000Z

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.


221

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

222

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

223

An Empirical Study on Ultrasonic Testing in Lieu of Radiography for Nuclear Power Plants  

SciTech Connect

Research is being conducted for the U.S. Nuclear Regulatory Commission (NRC) at the Pacific Northwest National Laboratory (PNNL) to assess the capability, effectiveness, and reliability of ultrasonic testing (UT) as a replacement method for radiographic testing (RT) for inspecting nuclear power plant (NPP) components. A primary objective of this work is to evaluate UT techniques to assess their ability to detect, locate, size, and characterize fabrication flaws in typical NPP weldments. This particular study focused on the evaluation of four carbon steel pipe-to-pipe welds on specimens that ranged in thicknesses from 19.05 mm (0.75 in.) to 27.8 mm (1.094 in.) and were 355.6 mm (14.0 in.) or 406.4 mm (16.0 in.) in diameter. The pipe welds contained both implanted (intentional) fabrication flaws as well as bonus (unintentional) flaws throughout the entire thickness of the weld and the adjacent base material. The fabrication flaws were a combination of planar and volumetric flaw types, including incomplete fusion, incomplete penetration, cracks, porosity, and slag inclusions. The examinations were conducted using phased-array UT (PA UT) techniques applied primarily for detection and length sizing of the flaws. Radiographic examinations were also conducted on the specimens with RT detection and length sizing results being used to establish true state. This paper will discuss the comparison of UT and RT (true state) detection results conducted to date along with a discussion on the technical gaps that need to be addressed before these methods can be used interchangeably for repair and replacement activities for NPP components.

Moran, Traci L.; Pardini, Allan F.; Ramuhalli, Pradeep; Prowant, Matthew S.; Mathews, Royce

2012-09-01T23:59:59.000Z

224

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

225

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 Universitys 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 Users 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. Users 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

226

An Assessment of the Current Day Impact of Various Materials Associated with the U.S. Nuclear Test Program in the Marshall Island  

SciTech Connect

Different stable elements, and some natural and man-made radionuclides, were used as tracers or associated in other ways with nuclear devices that were detonated at Bikini and Enewetak Atolls as part of the U.S. nuclear testing program from 1946 through 1958. The question has been raised whether any of these materials dispersed by the explosions could be of sufficient concentration in either the marine environment or on the coral islands to be of a health concern to people living, or planning to live, on the atolls. This report addresses that concern. An inventory of the materials involved during the test period was prepared and provided to us by the Office of Defense Programs (DP) of the United States Department of Energy (DOE). The materials that the DOE and the Republic of the Marshall Islands (RMI) ask to be evaluated are--sulfur, arsenic, yttrium, tantalum, gold, rhodium, indium, tungsten, thallium, thorium-230,232 ({sup 230,232}Th), uranium-233,238 ({sup 233,238}U), polonium-210 ({sup 210}Po), curium-232 ({sup 232}Cu), and americium-241 ({sup 241}Am). The stable elements were used primarily as tracers for determining neutron energy and flux, and for other diagnostic purposes in the larger yield, multistage devices. It is reasonable to assume that these materials would be distributed in a similar manner as the fission products subsequent to detonation. A large inventory of fission product and uranium data was available for assessment. Detailed calculations show only a very small fraction of the fission products produced during the entire test series remain at the test site atolls. Consequently, based on the information provided, we conclude that the concentration of these materials in the atoll environment pose no adverse health effects to humans.

Robison, W L; Noshkin, V E; Hamilton, T F; Conrado, C L; Bogen, K T

2001-05-01T23:59:59.000Z

227

Seismic fragility evaluation of a piping system in a nuclear power plant by shaking table test and numerical analysis  

SciTech Connect

In this study, a seismic fragility evaluation of the piping system in a nuclear power plant was performed. For the evaluation of seismic fragility of the piping system, this research was progressed as three steps. At first, several piping element capacity tests were performed. The monotonic and cyclic loading tests were conducted under the same internal pressure level of actual nuclear power plants to evaluate the performance. The cracks and wall thinning were considered as degradation factors of the piping system. Second, a shaking tale test was performed for an evaluation of seismic capacity of a selected piping system. The multi-support seismic excitation was performed for the considering a difference of an elevation of support. Finally, a numerical analysis was performed for the assessment of seismic fragility of piping system. As a result, a seismic fragility for piping system of NPP in Korea by using a shaking table test and numerical analysis. (authors)

Kim, M. K.; Kim, J. H.; Choi, I. K. [Korea Atomic Energy Research Inst., Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2012-07-01T23:59:59.000Z

228

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 will need to be constructed that can motor the engine and measure power losses using a torque sensor built

Demirel, Melik C.

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.

NONE

1988-12-01T23:59:59.000Z

230

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)

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...

O'Kelly, David Sean

2012-06-07T23:59:59.000Z

231

High-energy nuclear quasielastic reactions: Decisive tests of nuclear-binding/pion models of the European Muon Collaboration effect  

Science Journals Connector (OSTI)

The light-cone nucleon momentum distributions obtained from nonrelativistic spectral functions or given by nuclear-binding/pion models are often used to analyze high-Q2 quasielastic and deep-inelastic (e,e) 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,ep) and (p,pp) color transparency experiments is sufficient to observe these differences.

L. Frankfurt; G. A. Miller; M. Strikman

1992-01-06T23:59:59.000Z

232

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

233

Energy Secretary Moniz's Remarks at the U.S. Institute of Peace Conference-- As Prepared for Delivery  

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

The Secretary's remarks, as prepared for delivery, at the U.S. Institute of Peace Conference "Nuclear Weapons Testing: History, Progress and Challenges" in Washington, D.C. on September 15, 2014.

234

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

SciTech Connect

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

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

236

TESTING DIAGNOSTICS OF NUCLEAR ACTIVITY AND STAR FORMATION IN GALAXIES AT z > 1  

SciTech Connect

We present some of the first science data with the new Keck/MOSFIRE instrument to test the effectiveness of different AGN/SF diagnostics at z {approx} 1.5. MOSFIRE spectra were obtained in three H-band multi-slit masks in the GOODS-S field, resulting in 2 hr exposures of 36 emission-line galaxies. We compare X-ray data with the traditional emission-line ratio diagnostics and the alternative mass-excitation and color-excitation diagrams, combining new MOSFIRE infrared data with previous HST/WFC3 infrared spectra (from the 3D-HST survey) and multiwavelength photometry. We demonstrate that a high [O III]/H{beta} ratio is insufficient as an active galactic nucleus (AGN) indicator at z > 1. For the four X-ray-detected galaxies, the classic diagnostics ([O III]/H{beta} versus [N II]/H{alpha} and [S II]/H{alpha}) remain consistent with X-ray AGN/SF classification. The X-ray data also suggest that 'composite' galaxies (with intermediate AGN/SF classification) host bona fide AGNs. Nearly {approx}2/3 of the z {approx} 1.5 emission-line galaxies have nuclear activity detected by either X-rays or the classic diagnostics. Compared to the X-ray and line ratio classifications, the mass-excitation method remains effective at z > 1, but we show that the color-excitation method requires a new calibration to successfully identify AGNs at these redshifts.

Trump, Jonathan R.; Barro, Guillermo; Koo, David C.; Faber, S. M. [University of California Observatories/Lick Observatory and Department of Astronomy and Astrophysics, University of California, Santa Cruz, CA 95064 (United States); Konidaris, Nicholas P. [Cahill Center for Astronomy and Astrophysics, California Institute of Technology, MC 105-24, 1200 East California Boulevard, Pasadena, CA 91125 (United States); Kocevski, Dale D.; Yan, Renbin [Department of Physics and Astronomy, University of Kentucky, Lexington, KY 40506 (United States); Juneau, Stephanie [Irfu/Service d'Astrophysique, CEA-Saclay, Orme des Merisiers, F-91191 Gif-sur-Yvette Cedex (France); Weiner, Benjamin J. [Steward Observatory, University of Arizona, 933 North Cherry Avenue, Tucson, AZ 85721 (United States); McLean, Ian S. [Department of Physics and Astronomy, UCLA, Los Angeles, CA 90095 (United States); Perez-Gonzalez, Pablo G.; Villar, Victor [Departamento de Astrofisica, Facultad de CC. Fisicas, Universidad Complutense de Madrid, E-28040 Madrid (Spain)

2013-01-20T23:59:59.000Z

237

Nuclear fuels technologies fiscal year 1998 research and development test plan  

SciTech Connect

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

238

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

SciTech Connect

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

239

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

SciTech Connect

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

240

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

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

Test and valuation of portal monitors of nuclear material with the use of plastic scintillators and hand-held radiation detectors. Final report  

SciTech Connect

This report is the final part of work fulfilled under the contract with LANL in the cooperative program of American and Russian nuclear laboratories, aimed at strengthening the system of protection, control, and accountability of nuclear materials. Purpose of this work was to test portal and handheld monitors made by TSA Co. (USA) in order to upgrade the control of unauthorized passout of nuclear and radioactive materials from controlled territory and evaluation of possible application at Russian nuclear facility. Results of tests of PM-700SP pedestrian portal monitors and PRM-470A handheld monitors are given.

Savin, N.I. [Moskovskij Fiziko-Tekhnicheskij Inst., Moscow (Russian Federation)

1995-12-31T23:59:59.000Z

242

Seismic yield determination of Soviet underground nuclear explosions at the Shagan River test site  

Science Journals Connector (OSTI)

......1986a, Yield estimates of Nevada test site explosions obtained from seismic...Nuttli's method to estimate yield of Nevada test site explosions recorded on Lawrence...magnitude and explosion yield for Nevada Test Site explosions. He also applied......

Frode Ringdal; Peter D. Marshall; Ralph W. Alewine

1992-04-01T23:59:59.000Z

243

Preliminary Corrosion Test of a Glass-Ceramic Candidate for a Nuclear Waste Canister  

Science Journals Connector (OSTI)

Preliminary corrosion studies of Corning Glass Works glass-ceramic Code 9617 as a storage canister for spent nuclear fuel rods indicates a corrosion rate of 0.013 cm/1000 yr. when stored in a granite repositor...

J. D. Sundquist

1979-01-01T23:59:59.000Z

244

Test and evaluation of computerized nuclear material accounting methods. Final report  

SciTech Connect

In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700.

NONE

1995-12-31T23:59:59.000Z

245

Implementation of test for quality assurance in nuclear medicine gamma camera  

SciTech Connect

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

246

MANAGEMENT OF RESEARCH AND TEST REACTOR ALUMINUM SPENT NUCLEAR FUEL - A TECHNOLOGY ASSESSMENT  

SciTech Connect

The Department of Energy's Environmental Management (DOE-EM) Program is responsible for the receipt and storage of aluminum research reactor spent nuclear fuel or used fuel until ultimate disposition. Aluminum research reactor used fuel is currently being stored or is anticipated to be returned to the U.S. and stored at DOE-EM storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper assesses the technologies and the options for safe transportation/receipt and interim storage of aluminum research reactor spent fuel and reviews the comprehensive strategy for its management. The U.S. Department of Energy uses the Appendix A, Spent Nuclear Fuel Acceptance Criteria, to identify the physical, chemical, and isotopic characteristics of spent nuclear fuel to be returned to the United States under the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The fuel is further evaluated for acceptance through assessments of the fuel at the foreign sites that include corrosion damage and handleability. Transport involves use of commercial shipping casks with defined leakage rates that can provide containment of the fuel, some of which are breached. Options for safe storage include wet storage and dry storage. Both options must fully address potential degradation of the aluminum during the storage period. This paper focuses on the various options for safe transport and storage with respect to technology maturity and application.

Vinson, D.

2010-07-11T23:59:59.000Z

247

This manuscript has been published as: S Bernard, J Frisn, KL Spalding. A mathematical model for the interpretation of nuclear bomb test derived 14C incorporation in biological systems (2010) Nucl. Instr.  

E-Print Network (OSTI)

for the interpretation of nuclear bomb test derived 14C incorporation in biological systems (2010) Nucl. Instr. and Meth for the interpretation of nuclear bomb test derived 14 C incorporation in biological systems Samuel Bernard1 , Jonas nuclear bomb testing during the cold war (1955-1963). For slowly renewing tissues, this method provides

Boyer, Edmond

248

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

249

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

250

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

SciTech Connect

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

251

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

SciTech Connect

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

252

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

SciTech Connect

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

253

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

254

Preparation of binderless nanopore-isotropic graphite for inhibiting the liquid fluoride salt and Xe135 penetration for molten salt nuclear reactor  

Science Journals Connector (OSTI)

Abstract Mesocarbon microbeads and the isostatic pressing method were used to prepare binderless nanopore-isotropic graphite (NPIG) as a neutron moderator and reflector, to inhibit liquid fluoride salt and Xe135 penetration during use in a molten salt nuclear reactor. The microstructure, thermophysical, and other properties of the NPIG were studied and compared with isostatic graphite (IG-110, TOYO TANSO CO., Ltd., Japan). A high-pressure reactor and a vacuum device were constructed to evaluate the molten salt and Xe135 penetration in the graphite, respectively. The results indicated that NPIG possessed a graphitization degree of 74% and excellent properties such as a high bending strength of 94.12.5MPa, a high compressive strength of 2303MPa, a low porosity of 8.7%, and an average pore diameter of 69nm. The fluoride salt occupation of IG-110 was 13.5wt% under 1.5atm, whereas the salt gain in NPIG remained steady even up to 10atm with an increase of <0.06wt%, demonstrating that the graphite could inhibit the liquid fluoride salt infiltration effectively. The helium diffusion coefficient for NPIG was 8.76נ10?5cm2/s, much less than 1.21נ10?2cm2/s for IG-110. The NPIG could effectively inhibit liquid fluoride salt and Xe135 penetration.

Jinliang Song; Yanling Zhao; Junpeng Zhang; Xiujie He; Baoliang Zhang; Pengfei Lian; Zhanjun Liu; Dongsheng Zhang; Zhoutong He; Lina Gao; Huihao Xia; Xingtai Zhou; Ping Huai; Quangui Guo; Lang Liu

2014-01-01T23:59:59.000Z

255

Bruce Nuclear Generating Station B rapid cooldown test and validation of simulation model  

SciTech Connect

The SOPHT code was assessed against Bruce Nuclear Generating Station B commissioning data from a heat transport system rapid cooldown. It was found that (a) under a rapid upstream depressurization, the steam relief valves, like orifices, had a lower discharge coefficient than the corresponding steadystate value and (b) the flashing of water in the steam generators during depressurization causes the at-power boiling heat transfer correlations to overpredict the steam generator heat transfer.

Chang, Y.F.; Langan, M.D.; Sermer, P.; Watson, P.C.

1985-09-01T23:59:59.000Z

256

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

257

Automated Test Coverage Measurement for Reactor Protection System Software  

E-Print Network (OSTI)

Automated Test Coverage Measurement for Reactor Protection System Software Implemented in Function- ing a case study using test cases prepared by domain experts for reactor protection system software) are widely used to implement safety- critical systems such as nuclear reactor protection systems, testing

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

Spent Nuclear Fuel (SNF) Storage Project Fuel Basket Handling Grapple Design Development Test Report  

SciTech Connect

Acceptance testing of the SNF Fuel Basket Lift Grapple was accomplished to verify the design adequacy. This report shows the results affirming the design. The test was successful in demonstrating the adequacy of the grapple assembly's inconel actuator shaft and engagement balls for in loads excess of design basis loads (3200 pounds), 3X design basis loads (9600 pounds), and 5X design basis loads (16,000 pounds). The test data showed that no appreciable yielding for the inconel actuator shaft and engagement balls at loads in excess of 5X Design Basis loads. The test data also showed the grapple assembly and components to be fully functional after loads in excess of 5X Design Basis were applied and maintained for over 10 minutes. Following testing, each actuator shaft (Item 7) was liquid penetrant inspected per ASME Section 111, Division 1 1989 and accepted per requirements of NF-5350. This examination was performed to insure that no cracking had occurred. The test indicated that no cracking had occurred. The examination reports are included as Appendix C to this document. From this test, it is concluded that the design configuration meets or exceeds the requirements specified in ANSI N 14 6 for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More.

CHENAULT, D.M.

2000-01-06T23:59:59.000Z

260

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

SciTech Connect

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

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.


261

The Linkage Between Non-Proliferation, Deterrence Policy, Nuclear Testing and the Arms Race  

Science Journals Connector (OSTI)

A major focal point for strengthening the Non-Proliferation Treaty (NPT), which is the central legal and political basis of the non-proliferation regime has been negotiation of a comprehensive test ban (CTB). ...

Lawrence Scheinman

1990-01-01T23:59:59.000Z

262

Updated Review Finds Little U.S. Military Risk in Nuclear Test Ban  

Science Journals Connector (OSTI)

...and that treaty-monitoring technologies now make...Organization's International Monitoring System (IMS) is so capable...build a network of 337 monitoring stations across...parts of the world. Surreptitious tests small enough to...

Daniel Clery

2012-04-06T23:59:59.000Z

263

Preliminary studies and tests of semiconductors for their use as nuclear radiation detectors  

E-Print Network (OSTI)

of the semiconductors which were used in the tests~ and from Hughes Ines of Culver City, California, who provided a set of diodes of a type that had been sucessfully used as a radiation detector. 1 1 See article by Salzberg and Siegal of Airborne Instru- ments... that each semiconductor junction has a different breakdown point and has a different thermal noise pulse versus temperature characteristic. Silicon diodes were selected for tests because of their low thermal noise char- acteristics. The experimenter...

Willis, Giles Whitehurst

2012-06-07T23:59:59.000Z

264

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.

265

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

266

Modeling Groundwater Flow and Transport of Radionuclides at Amchitka Island's Underground Nuclear Tests: Milrow, Long Shot, and Cannikin  

SciTech Connect

Since 1963, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive material in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site (NTS), but a limited number of experiments were conducted in other locations. One of these locations, Amchitka Island, Alaska is the subject of this report. Three underground nuclear tests were conducted on Amchitka Island. Long Shot was an 80-kiloton-yield test conducted at a depth of 700 meters (m) on October 29, 1965 (DOE, 2000). Milrow had an announced yield of about 1,000 kilotons, and was detonated at a depth of 1,220 m on October 2, 1969. Cannikin had an announced yield less than 5,000 kilotons, and was conducted at a depth of 1,790 m on November 6, 1971. The purpose of this work is to provide a portion of the information needed to conduct a human-health risk assessment of the potential hazard posed by the three underground nuclear tests on Amchitka Island. Specifically, the focus of this work is the subsurface transport portion, including the release of radionuclides from the underground cavities and their movement through the groundwater system to the point where they seep out of the ocean floor and into the marine environment. This requires a conceptual model of groundwater flow on the island using geologic, hydrologic, and chemical information, a numerical model for groundwater flow, a conceptual model of contaminant release and transport properties from the nuclear test cavities, and a numerical model for contaminant transport. Needed for the risk assessment are estimates of the quantity of radionuclides (in terms of mass flux) from the underground tests on Amchitka that could discharge to the ocean, the time of possible discharge, and the location in terms of distance from shoreline. The radionuclide data presented here are all reported in terms of normalized masses to avoid presenting classified information. As only linear processes are modeled, the results can be readily scaled by the true classified masses for use in the risk assessment. The modeling timeframe for the risk assessment was set at 1,000 years, though some calculations are extended to 2,000 years. This first section of the report endeavors to orient the reader with the environment of Amchitka and the specifics of the underground nuclear tests. Of prime importance are the geologic and hydrologic conditions of the subsurface. A conceptual model for groundwater flow beneath the island is then developed and paired with an appropriate numerical modeling approach in section 2. The parameters needed for the model, supporting data for them, and data uncertainties are discussed at length. The calibration of the three flow models (one for each test) is then presented. At this point the conceptual radionuclide transport model is introduced and its numerical approach described in section 3. Again, the transport parameters and their supporting data and uncertainties are the focus. With all of the processes and parameters in place, the first major modeling phase can be discussed in section 4. In this phase, a parametric uncertainty analysis is performed to determine the sensitivity of the transport modeling results to the uncertainties present in the parameters. This analysis is motivated by the recognition of substantial uncertainty in the subsurface conditions on the island and the need to incorporate that uncertainty into the modeling. The conclusion of the first phase determines the parameters to hold as uncertain through the main flow and transport modeling. This second, main phase of modeling is presented in section 5, with the contaminant breakthrough behavior of each test site addressed. This is followed by a sensitivity analysis in section 6, regarding the importance of additional processes that could not be supported in the main modeling effort due to lack of data. Finally, the results for the individual sites are compared, the sensitivities discussed,

Ahmed Hassan; Karl Pohlmann; Jenny Chapman

2002-11-19T23:59:59.000Z

267

Precision physics of simple atoms: QED tests, nuclear structure and fundamental constants  

E-Print Network (OSTI)

Quantum electrodynamics is the first successful and still the most successful quantum field theory. Simple atoms, being essentially QED systems, allow highly accurate theoretical predictions. Because of their simple spectra, such atoms have been also efficiently studied experimentally frequently offering the most precisely measured quantities. Our review is devoted to comparison of theory and experiment in the field of precision physics of light simple atoms. In particular, we consider the Lamb shift in the hydrogen atom, the hyperfine structure in hydrogen, deuterium, helium-3 ion, muonium and positronium, as well as a number of other transitions in positronium. Additionally to a spectrum of unperturbed atoms, we consider annihilation decay of positronium and the g factor of bound particles in various two-body atoms. Special attention is paid to the uncertainty of the QED calculations due to the uncalculated higher-order corrections and effects of the nuclear structure. We also discuss applications of simple atoms to determination of several fundamental constants.

Savely G. Karshenboim

2005-09-01T23:59:59.000Z

268

Radiation monitoring around United States nuclear test areas, calendar year 1989  

SciTech Connect

This report describes the Offsite Radiation Safety Program conducted during 1989 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 the testing is in compliance with existing radiation protection standards, and 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 both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. 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 NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs.

Not Available

1990-05-01T23:59:59.000Z

269

ORISE: REAC/TS trains emergency responders in preparation for...  

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

REACTS trains emergency responders in preparation for Pan American Games Workshop in Mexico helps medical professionals prepare for treating victims of radiological or nuclear...

270

Screening tests of representative nuclear power plant components exposed to secondary environments created by fires  

SciTech Connect

This report presents results of screening tests to determine component survivability in secondary environments created by fires, specifically increased temperatures, increased humidity, and the presence of particulates and corrosive vapors. Additionally, chloride concentrations were measured in the exhaust from several of the tests used to provide fire environments. Results show actual failure or some indication of failure for strip chart recorders, electronic counters, an oscilloscope amplifier, and switches and relays. The chart recorder failures resulted from accumulation of particulates on the pen slider mechanisms. The electronic counter experienced leakage current failures on circuit boards after the fire exposure and exposure to high humidity. The oscillosocpe amplifier experienced thermal-related drift as high as 20% before thermal protective circuitry shut the unit down. In some cases, switches and relays experienced high contact resistances with the low voltages levels used for the mesurements. Finally, relays tested to thermal failure experienced various failures, all at temperatures ranging from 150/sup 0/C to above 350/sup 0/C. The chloride measurements show that most of the hydrogen chloride generated in the test fires is combined with particulate by the time it reaches the exhaust duct, indicating that hydrogen chloride condensation may be less likely than small scale data implies. 13 refs., 36 figs.

Jacobus, M.J.

1986-06-01T23:59:59.000Z

271

Civilian Nuclear Programs, SPO-CNP: LANL  

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

Nuclear Office of Science Civilian Nuclear Programs Home Advanced Nuclear Energy Programs Yucca Mountain and Nevada Test Site Programs WIPP and Actinide Science Programs Nuclear...

272

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

SciTech Connect

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

273

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

274

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

275

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

276

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

SciTech Connect

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

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

278

Ultrasonic Intrinsic Tagging for Nuclear Disarmament: A Proof-of-Concept Test  

SciTech Connect

The Office of Nonproliferation Policy of the Department of Energy (DOE/NA-241) requested Pacific Northwest National Laboratory (PNNL) to evaluate ultrasonic intrinsic tag (UIT) technology as a potential means to uniquely identify weapon components during dismantlement activities. PNNL performed a blind test to uniquely identify an item, solely based on UIT signatures out of a population of five inert trainers. A conclusion was that a high confidence exists that the ultrasonic intrinsic tag system is able to perform well as either a confidence building measure or an authenticating technology to assure an item is genuine. UIT signatures are intrinsic to the material and location on an item; therefore, external markings on an item were unnecessary. A fixture that mated to the lifting lugs of the B61 trainer was used to consistently place the UIT reader to the same location on an item to acquire a meaningful UIT signature.

Good, Morris S.; Simpkins, Bret E.; Kirihara, Leslie J.; Skorpik, James R.; Willett, Jesse A.

2003-12-01T23:59:59.000Z

279

S. 2466: This Act may be cited as the National Atmospheric Nuclear Testing Compensation Act of 1990. Introduced in the Senate of the United States, One Hundredth First Congress, Second Session, April 19, 1990  

SciTech Connect

This bill would amend Title XXI of the Public Health Service Act to provide for the establishment of an atmospheric nuclear testing compensation program to compensate civilians living down wind of the Nevada Test Site during above-ground testing of nuclear weapons and miners exposed in underground uranium mines supplying uranium for the primary use and benefit of the nuclear weapons program. The bill describes technical assistance and information, administrative procedures for filing a petition, determination of eligibility, and amount of compensation.

Not Available

1990-01-01T23:59:59.000Z

280

E-Print Network 3.0 - astronomy nuclear transition Sample Search...  

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

Nuclear Physics and Nuclear Engineering Summary: EPSRCSTFC Review of Nuclear Physics and Nuclear Engineering A report prepared for EPSRC and STFC... of the scope of RCUK funded...

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

Standard test method for determination of impurities in nuclear grade uranium compounds by inductively coupled plasma mass spectrometry  

E-Print Network (OSTI)

1.1 This test method covers the determination of 67 elements in uranium dioxide samples and nuclear grade uranium compounds and solutions without matrix separation by inductively coupled plasma mass spectrometry (ICP-MS). The elements are listed in Table 1. These elements can also be determined in uranyl nitrate hexahydrate (UNH), uranium hexafluoride (UF6), triuranium octoxide (U3O8) and uranium trioxide (UO3) if these compounds are treated and converted to the same uranium concentration solution. 1.2 The elements boron, sodium, silicon, phosphorus, potassium, calcium and iron can be determined using different techniques. The analyst's instrumentation will determine which procedure is chosen for the analysis. 1.3 The test method for technetium-99 is given in Annex A1. 1.4 The values stated in SI units are to be regarded as standard. 1.5 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 ...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

282

Radiation Testing of a Low Voltage Silicone Nuclear Power Plant Cable.  

SciTech Connect

This report summarizes the results generated in FY13 for cable insulation in support of DOE's Light Water Reactor Sustainability (LWRS) Program, in collaboration with the US- Argentine Binational Energy Working Group (BEWG). A silicone (SiR) cable, which was stored in benign conditions for ~30 years, was obtained from Comision Nacional de Energia Atomica (CNEA) in Argentina. Physical property testing was performed on the as-received cable. This cable was artificially aged to assess behavior with additional analysis. SNL observed appreciable tensile elongation values for all cable insulations received, indicative of good mechanical performance. Of particular note, the work presented here provides correlations between measured tensile elongation and other physical properties that may be potentially leveraged as a form of condition monitoring (CM) for actual service cables. It is recognized at this point that the polymer aging community is still lacking the number and types of field returned materials that are desired, but SNL -- along with the help of others -- is continuing to work towards that goal. This work is an initial study that should be complimented with location- mapping of environmental conditions of CNEA plant conditions (dose and temperature) as well as retrieval, analysis, and comparison with in-service cables.

Bernstein, Robert

2014-08-01T23:59:59.000Z

283

Radiation Testing of a Low Voltage Silicone Nuclear Power Plant Cable.  

SciTech Connect

This report summarizes the results generated in FY13 for cable insulation in support of the Department of Energy's Light Water Reactor Sustainability (LWRS) Program, in collaboration with the US-Argentine Binational Energy Working Group (BEWG). A silicone (SiR) cable, which was stored in benign conditions for ~30 years, was obtained from Comision Nacional de Energia Atomica (CNEA) in Argentina with the approval of NA-SA (Nucleoelectrica Argentina Sociedad Anonima). Physical property testing was performed on the as-received cable. This cable was artificially aged to assess behavior with additional analysis. SNL observed appreciable tensile elongation values for all cable insulations received, indicative of good mechanical performance. Of particular note, the work presented here provides correlations between measured tensile elongation and other physical properties that may be potentially leveraged as a form of condition monitoring (CM) for actual service cables. It is recognized at this point that the polymer aging community is still lacking the number and types of field returned materials that are desired, but Sandia National Laboratories (SNL) -- along with the help of others -- is continuing to work towards that goal. This work is an initial study that should be complimented with location-mapping of environmental conditions of Argentinean plant conditions (dose and temperature) as well as retrieval, analysis, and comparison with in- service cables.

White II, Gregory Von; Schroeder, John Lee.; Sawyer, Patricia Sue.; Wichhart, Derek; Mata, Guillermo Adrian; Zorrilla, Jorge; Bernstein, Robert

2014-09-01T23:59:59.000Z

284

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

285

Tests of the nuclear equation of state and superfluid and superconducting gaps using the Cassiopeia A neutron star  

E-Print Network (OSTI)

The observed rapid cooling of the Cassiopeia A neutron star can be interpreted as being caused by neutron and proton transitions from normal to superfluid and superconducting states in the stellar core. Here we present two new Chandra ACIS-S Graded observations of this neutron star and measurements of the neutron star mass M and radius R found from consistent fitting of both the X-ray spectra and cooling behavior. This comparison is only possible for individual nuclear equations of state. We test phenomenological superfluid and superconducting gap models which mimic many of the known theoretical models against the cooling behavior. Our best-fit solution to the Cassiopeia A data is one in which the (M,R) = (1.43 Msun,12.6 km) neutron star is built with the BSk21 equation of state, strong proton superconductor and moderate neutron triplet superfluid gap models, and a pure iron envelope or a thin carbon layer on top of an iron envelope, although there are still large observational and theoretical uncertainties.

Ho, Wynn C G; Heinke, Craig O; Potekhin, Alexander Y

2014-01-01T23:59:59.000Z

286

Standard guide for establishing surveillance test program for boron-based neutron absorbing material systems for use in nuclear spent fuel storage racks  

E-Print Network (OSTI)

1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear spent fuel storage racks in a pool environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program to verify the presence of sufficient neutron absorbing material within the storage racks. The performance of a surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear spent fuel. 1.2 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2007-01-01T23:59:59.000Z

287

Technical evaluation of the noise and isolation testing of the safety features actuation system at the Davis Besse Nuclear Power Station, Unit 1  

SciTech Connect

This report documents the technical evaluation of the noise and isolation testing of the safety features actuation system at the Davis Besse Nuclear Power Station, Unit 1. The tests were to verify that faults on the non-Class 1E circuits would not propagate to the Class 1E circuits and degrade them below acceptable levels. The tests conducted demonstrated that the safety features actuation system did not degrade below acceptable levels nor was the system's ability to perform its protective functions affected.

Selan, J.C.

1981-07-01T23:59:59.000Z

288

$?$-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

289

NUCLEAR POWER in CALIFORNIA  

E-Print Network (OSTI)

NUCLEAR POWER in CALIFORNIA: 2007 STATUS REPORT CALIFORNIA ENERGY COMMISSION October 2007 CEC-100, California Contract No. 700-05-002 Prepared For: California Energy Commission Barbara Byron, Senior Nuclear public workshops on nuclear power. The Integrated Energy Policy Report Committee, led by Commissioners

290

Causal relationship between nuclear energy consumption and economic growth in G6 countries: Evidence from panel Granger causality tests  

Science Journals Connector (OSTI)

Abstract Looking at the recent nuclear accident in Fukushima, Japan, the consequences were not just environmental or economic. The accident was a big hit to the reputation and trust in nuclear power generation making a number of countries reconsider the nuclear energy as an option. The recent financial crisis might have limited even more the developed countries from the necessary capital to invest in expensive power options but this might change in the future if the positive environmental effects of the nuclear power can be proven substantial. The purpose of this paper is to analyse the causal link between nuclear energy consumption and economic growth for six developed countries over the period from 1971 to 2011. Granger causality procedure based on Meta-analysis in heterogeneous mixed panels is used to allow for cross-sectional dependency and heterogeneity across countries. The empirical findings for the overall panel support the presence of unidirectional causality running from economic growth to nuclear energy consumption across the G-6 countries. However, in the case of UK we find a bidirectional causality running from nuclear energy consumption to economic growth; while the results for Germany confirm the growth hypothesis and for the rest of the countries the neutrality hypothesis.

T. Chang; F. Gatwabuyege; R. Gupta; R. Inglesi-Lotz; N.C. Manjezi; B.D. Simo-Kengne

2014-01-01T23:59:59.000Z

291

NUCLEAR POWER IN CALIFORNIA: 2007 STATUS REPORT  

E-Print Network (OSTI)

NUCLEAR POWER IN CALIFORNIA: 2007 STATUS REPORT Prepared For: California Energy Commission Prepared No. 700-05-002 Prepared For: California Energy Commission Barbara Byron, Senior Nuclear Policy;Abstract This consultant report examines how nuclear power issues have evolved since publication

292

CIP Preparation Course Summer 2008  

E-Print Network (OSTI)

CIP Preparation Course Summer 2008 Project Lead: Susan Rose, Ph.D. Office for the Protection, and support needed to prepare for and successfully pass the Certified IRB Professional (CIP) examination, State Law (Marlene) Week 9 (8/11/08) *Pre-post practice test, Q&A, CIP Discussion, Test Strategies

Biederman, Irving

293

Test Plan to Demonstrate Removal of Iodine and Tritium from Simulated Nuclear Fuel Recycle Plant Off-gas Streams using Adsorption Processes  

SciTech Connect

This letter documents the completion of the FCR&D Level 4 milestone for the Sigma Team Off-Gas - ORNL work package (FT-14OR031202), Co-absorption studies - Design system complete/test plan complete (M4FT-14OR0312022), due November 15, 2013. The objective of this test plan is to describe research that will determine the effectiveness of silver mordenite and molecular sieve beds to remove iodine and water (tritium) from off-gas streams arising from used nuclear fuel recycling processes, and to demonstrate that the iodine and water can be recovered separately from one another.

Bruffey, Stephanie H. [ORNL] [ORNL; Spencer, Barry B. [ORNL] [ORNL; Jubin, Robert Thomas [ORNL] [ORNL

2013-12-11T23:59:59.000Z

294

"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.

295

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

296

Laboratory and Field Testing of Commercially Available Detectors for the Identification of Chemicals of Interest in the Nuclear Fuel Cycle for the Detection of Undeclared Activities  

SciTech Connect

Traditionally, IAEA inspectors have focused on the detection of nuclear indicators as part of infield inspection activities. The ability to rapidly detect and identify chemical as well as nuclear signatures can increase the ability of IAEA inspectors to detect undeclared activities at a site. Identification of chemical indicators have been limited to use in the analysis of environmental samples. Although IAEA analytical laboratories are highly effective, environmental sample processing does not allow for immediate or real-time results to an IAEA inspector at a facility. During a complementary access inspection, under the Additional Protocol, the use of fieldable technologies that can quickly provide accurate information on chemicals that may be indicative of undeclared activities can increase the ability of IAEA to effectively and efficiently complete their mission. The Complementary Access Working Group (CAWG) is a multi-laboratory team with members from Brookhaven National Laboratory, Idaho National Laboratory, Los Alamos National Laboratory, and Sandia National Laboratory. The team identified chemicals at each stage of the nuclear fuel cycle that may provide IAEA inspectors with indications that proliferation activities may be occurring. The group eliminated all indicators related to equipment, technology and training, developing a list of by-products/effluents, non-nuclear materials, nuclear materials, and other observables. These proliferation indicators were prioritized based on detectability from a conduct of operations (CONOPS) perspective of a CA inspection (for example, whether an inspector actually can access the S&O or whether it is in process with no physical access), and the IAEAs interest in the detection technology in conjunction with radiation detectors. The list was consolidated to general categories (nuclear materials from a chemical detection technique, inorganic chemicals, organic chemicals, halogens, and miscellaneous materials). The team then identified commercial off the shelf (COTS) chemical detectors that may detect the chemicals of interest. Three chemical detectors were selected and tested both in laboratory settings and in field operations settings at Idaho National Laboratory. The instruments selected are: Thermo Scientific TruDefender FT (FTIR), Thermo Scientific FirstDefender RM (Raman), and Bruker Tracer III SD (XRF). Functional specifications, operability, and chemical detectability, selectivity, and limits of detection were determined. Results from the laboratory and field tests will be presented. This work is supported by the Next Generation Safeguards Initiative, Office of Nonproliferation and International Security, National Nuclear Security Administration.

Carla Miller; Mary Adamic; Stacey Barker; Barry Siskind; Joe Brady; Warren Stern; Heidi Smartt; Mike McDaniel; Mike Stern; Rollin Lakis

2014-07-01T23:59:59.000Z

297

Sandia National Laboratories: Mechanical Testing  

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

EnergyNuclear Energy Systems Laboratory (NESL) Brayton LabMechanical Testing Mechanical Testing Mechanical Testing Overview Mechanical 1-2 (2008). Standard Test Methods for...

298

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

299

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

300

Preparing Your  

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

Preparing Your Applications for Future NERSC Machines Jack Deslippe NERSC User Services 1082013 What HPC Will Look Like at NERSC in 2017 The Future Will Have Many-Cores...

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

Testing the direct ion storage dosemeter for personal dosimetry in a nuclear research centre and a hospital  

Science Journals Connector (OSTI)

......dosimetry in a nuclear research centre and a hospital F. Vanhavere 1 * P. Covens 2 * Corresponding...in several departments of a university hospital. The conclusions are that the DIS has...be beneficial for large institutes or hospitals where the workers are spread over large......

F. Vanhavere; P. Covens

2010-03-01T23:59:59.000Z

302

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

303

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.

304

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.

305

Approval of Existent Waste Packages and New Package Designs in Preparation for the Konrad Repository  

SciTech Connect

Low and intermediate level radioactive waste from German nuclear and other industries, research facilities and increasingly decommissioned nuclear installations is handled and prepared for interim storage and later disposal in the licensed KONRAD repository. This paper presents aspects, experiences and perspectives of container design testing and qualification procedures. Several new container designs, in particular different types of steel plate containers, have been tested and licensed; some are handled at present or just applied. Examples from typical qualification procedures including drop tests from 0.8 and 5 m height with prototype containers are presented. On the other hand several thousand waste packages are currently stored in interim storage facilities, many of them for more than 10 or 15 years. Based on existing package documentation applications and safety assessments for KONRAD are prepared and have to be evaluated. The paper discusses aspects, difficulties and strategies to demonstrate sufficient compliance to the current KONRAD repository requirements for the large number of existent waste packages. (authors)

Volzke, H.; Nieslony, G.; Hagenow, P. [BAM Bundesanstalt fur Materialforschung und - prufung, Federal Institute for Materials Research and Testing, Berlin (Germany)

2008-07-01T23:59:59.000Z

306

Application of the NNWSI [Nevada Nuclear Waste Storage Investigations] unsaturated test method to actinide doped SRL [Savannah River Laboratory] 165 type glass  

SciTech Connect

The results of tests done using the Unsaturated Test Method are presented. These tests, done to determine the suitability of glass in a potential high-level waste repository as developed by the Nevada Nuclear Waste Storage Investigations Project, simulate conditions anticipated for the post-containment phase of the repository when only limited contact between the waste form and water is expected. The reaction of glass occurs via processes that are initiated due to glass/water vapor and glass/liquid water contact. Vapor interaction results in the initiation of an exchange process between water and the more mobile species (alkalis and boron) in the glass. The liquid reaction produces interactions similar to those seen in standard leaching tests, except due to the limited amount of water present and the presence of partially sensitized 304L stainless steel, the formation of reaction products greatly exceeds that found in MCC-1 type leach tests. The effect of sensitized stainless steel on the reaction is to enhance breakdown of the glass matrix thereby increasing the release of the transuranic elements from the glass. However, most of the Pu and Am released is entrained by either the metal components of the test or by the reaction phases, and is not released to solution. 16 refs., 20 figs., 17 tabs.

Bates, J.K.; Gerding, T.J.

1990-08-01T23:59:59.000Z

307

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

308

Approaches to Quantify Potential Contaminant Transport in the Lower Carbonate Aquifer from Underground Nuclear Testing at Yucca Flat, Nevada National Security Site, Nye County, Nevada - 12434  

SciTech Connect

Quantitative modeling of the potential for contaminant transport from sources associated with underground nuclear testing at Yucca Flat is an important part of the strategy to develop closure plans for the residual contamination. At Yucca Flat, the most significant groundwater resource that could potentially be impacted is the Lower Carbonate Aquifer (LCA), a regionally extensive aquifer that supplies a significant portion of the water demand at the Nevada National Security Site, formerly the Nevada Test Site. Developing and testing reasonable models of groundwater flow in this aquifer is an important precursor to performing subsequent contaminant transport modeling used to forecast contaminant boundaries at Yucca Flat that are used to identify potential use restriction and regulatory boundaries. A model of groundwater flow in the LCA at Yucca Flat has been developed. Uncertainty in this model, as well as other transport and source uncertainties, is being evaluated as part of the Underground Testing Area closure process. Several alternative flow models of the LCA in the Yucca Flat/Climax Mine CAU have been developed. These flow models are used in conjunction with contaminant transport models and source term models and models of contaminant transport from underground nuclear tests conducted in the overlying unsaturated and saturated alluvial and volcanic tuff rocks to evaluate possible contaminant migration in the LCA for the next 1,000 years. Assuming the flow and transport models are found adequate by NNSA/NSO and NDEP, the models will undergo a peer review. If the model is approved by NNSA/NSO and NDEP, it will be used to identify use restriction and regulatory boundaries at the start of the Corrective Action Decision Document Corrective Action Plan (CADD/CAP) phase of the Corrective Action Strategy. These initial boundaries may be revised at the time of the Closure Report phase of the Corrective Action Strategy. (authors)

Andrews, Robert W.; Birdie, Tiraz [Navarro-INTERA LLC, Las Vegas, Nevada 89030 (United States); Wilborn, Bill; Mukhopadhyay, Bimal [National Nuclear Security Administration/Nevada Site Office, Las Vegas, Nevada 89030 (United States)

2012-07-01T23:59:59.000Z

309

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

SciTech Connect

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

310

Dual Axis Radiographic Hydrodynamic Test Facility | National...  

National Nuclear Security Administration (NNSA)

Dual Axis Radiographic Hydrodynamic Test Facility | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear...

311

Nuclear Energy  

Science Journals Connector (OSTI)

Nuclear Energy ... A brief summary of the history and key concepts of nuclear energy. ... Nuclear / Radiochemistry ...

Charles D. Mickey

1980-01-01T23:59:59.000Z

312

Nuclear batteries  

Science Journals Connector (OSTI)

Nuclear batteries ... Describes the structure, operation, and application of nuclear batteries. ... Nuclear / Radiochemistry ...

Alfred B. Garrett

1956-01-01T23:59:59.000Z

313

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

SciTech Connect

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

314

Radioxenon detections in the CTBT International Monitoring System likely related to the announced nuclear test in North Korea conducted on February 12, 2013  

SciTech Connect

Abstract: Observations of the radioxenon isotopes 133Xe and 131mXe collected at the IMS stations RN38 and RN58 on April 7-8, and April 12-13 2013, respectively, are unique with respect to the measurement history of these stations. Comparison of measured data with calculated isotopic ratios as well as analysis using atmospheric transport modeling indicate that it is likely that the xenon measured was created in the underground nuclear test conducted by North Korea on February 12, 2013, and released 7 weeks later. More than one release is required to explain all observations. The 131mXe source terms for each release were calculated to 7x1011 Bq, corresponding to about 1-10% of the total xenon inventory for a 10-kt explosion, depending on fractionation and release scenario. The observed ratios could not be used to obtain any information regarding the fissile material that was used in the test.

Ringbom, Anders; Axelssson, A.; Aldener, M.; Auer, M.; Bowyer, Ted W.; Fritioff, T.; Hoffman, Ian; Khrustalev, Kirill; Nikkinen, Mika; Popov, Vladimir Y.; Popov, Y.; Ungar, R. Kurt; Wotawa, G.

2014-02-01T23:59:59.000Z

315

ORNL staff help students prepare for FIRST LEGO League competition...  

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

staff help students prepare for FIRST LEGO League competition Brian Peters, right, a design engineer for nuclear systems with US ITER at Oak Ridge National Laboratory, works with...

316

Limited Test Ban Treaty  

National Nuclear Security Administration (NNSA)

Detection System (USNDS), which monitors compliance with the international Limited Test Ban Treaty (LTBT). The LTBT, signed by 108 countries, prohibits nuclear testing in the...

317

Abstracting Preparation  

E-Print Network (OSTI)

Guidelines & Review Manuscript Preparation Submit Your Manuscript Book Reviews Movies & Videos Contact of Biological and Chemical Sciences. Queen Mary, University of London, Mile End Road, London, UK. Abstract Two motive force for energy conversion, providing for metabolism, for active transport, and for synthesis

Allen, John F.

318

State-of-the-art of non-destructive testing methods and technologies for application to nuclear power plant safety-related concrete structures  

SciTech Connect

The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: locating steel reinforcement and identification of its cover depth locating tendon ducts and identification of the condition of the grout materials detection of cracking, voids, delamination, and honeycombing in concrete structures detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner methods capable of identification of corrosion occurrence on the concrete side of the containment liner.

Wiggenhauser, Herbert [BAM - Federal Institute for Materials Research and Testing, Berlin, D (Germany); Naus, Dan J. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

2014-02-18T23:59:59.000Z

319

State-of-the-Art of Non-Destructive Testing Methods and Technologies for Application to Nuclear Power Plant Safety-Related Concrete Structures  

SciTech Connect

The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: locating steel reinforcement and identification of its cover depth locating tendon ducts and identification of the condition of the grout materials detection of cracking, voids, delamination, and honeycombing in concrete structures detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner methods capable of identification of corrosion occurrence on the concrete side of the containment liner

Wiggenhauser, Dr. Herbert [Federal Institute for Materials Research and Testing (BAM)] [Federal Institute for Materials Research and Testing (BAM); Naus, Dan J [ORNL] [ORNL

2014-01-01T23:59:59.000Z

320

Microsoft Word - STWA Test Report - FINAL  

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

3292012 - G. Hughes & J. BUELT ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS STWA, INC. VISCOSITY REDUCTION TECHNOLOGY Prepared for: Industry Publication Prepared by:...

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

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

322

Nuclear Forensics  

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

nuclear forensics Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear...

323

EIS-0426: Notice of Intent to Prepare an Environmental Impact...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Operation of the Department of EnergyNational Nuclear Security Administration Nevada Test Site and Off-Site Locations in the State of Nevada The National Nuclear Security...

324

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.

325

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 (more)

O'Kelly, David Sean

2012-01-01T23:59:59.000Z

326

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

327

Validation of nuclear design method by measured data obtained in the physics test at a small fast reactor  

SciTech Connect

The present paper discusses applicability of the measured data of Joyo cores from a view point of integral validation for the 4S nuclear design methodology. Through the evaluation of isothermal reactivity coefficients and reactivity losses due to burnup, the results confirm that those MK-I and MK-II database are effective in order to increase the dataset for uncertainty estimation for the prediction. Discussions on the 4S design method validation are also done through the analyses of criticality, power distributions and reactivity loss due to burn-up. The C/E values for criticality and reaction rate distributions are confirmed to be consistent with those obtained from the physics benchmark experiments. Through an analysis of burnup coefficient of the MK-I core by the detailed Monte Carlo calculations, the C/E value is 1.1, which is close to 1.06 obtained by the deterministic transport analysis. (authors)

Nagata, A.; Tsuboi, Y. [Advanced Energy Design and Engineering Dep., Toshiba Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Moriki, Y. [Power and Industrial Systems Research and Development Center, Toshiba Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Kawashima, M. [Nuclear Technology Application Dept., Toshiba Nuclear Engineering Services Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan)

2012-07-01T23:59:59.000Z

328

Nuclear Radius and Nuclear Forces  

Science Journals Connector (OSTI)

The difference between the radius of the nuclear matter distribution and the nuclear force radius, RN?1.4A1310-13 cm, for heavy nuclei (A>100) is interpreted as a consequence of the finite range of nuclear forces. Assuming that the nuclear matter distribution coincides with the charge distribution as determined at Stanford (RC=1.12A1310-13 cm is the distance at which the charge density falls to one half value) we sum up the nuclear interactions of an incident nucleon for various proposed internucleon potentials, V(r). We also evaluate contributions from the spin, charge, and matter polarizations induced in the nuclear distributions by the incident nucleon as a test of the convergence of these calculations. The aim here is to infer some features of nuclear forces which satisfy saturation requirements and at the same time give rise to an appreciable nuclear attraction for an incident nucleon at RN. Analyses of the scattering of neutrons and protons by heavy nuclei suggest a nuclear attraction ?14 Mev at a distance RN.These considerations are primarily sensitive to the long range behavior of the direct, central part of V(r). The key point which emerges from them is that the nuclear forces must contain long range (~ meson Compton wavelength) direct, central attractions which will be felt by an incident nucleon at RN before the shorter range repulsions (hard cores, many-body forces, or exchange interactions), which are responsible for saturation, become effective. Such interactions can be constructed phenomenologically, but are not found in recent meson-theoretically deduced potentials.

S. D. Drell

1955-10-01T23:59:59.000Z

329

Experimental investigations on decay heat removal in advanced nuclear reactors using single heater rod test facility: Air alone in the annular gap  

SciTech Connect

During a loss of coolant accident in nuclear reactors, radiation heat transfer accounts for a significant amount of the total heat transfer in the fuel bundle. In case of heavy water moderator nuclear reactors, the decay heat of a fuel bundle enclosed in the pressure tube and outer concentric calandria tube can be transferred to the moderator. Radiation heat transfer plays a significant role in removal of decay heat from the fuel rods to the moderator, which is available outside the calandria tube. A single heater rod test facility is designed and fabricated as a part of preliminary investigations. The objective is to anticipate the capability of moderator to remove decay heat, from the reactor core, generated after shut down. The present paper focuses mainly on the role of moderator in removal of decay heat, for situation with air alone in the annular gap of pressure tube and calandria tube. It is seen that the naturally aspirated air is capable of removing the heat generated in the system compared to the standstill air or stagnant water situations. It is also seen that the flowing moderator is capable of removing a greater fraction of heat generated by the heater rod compared to a stagnant pool of boiling moderator. (author)

Bopche, Santosh B.; Sridharan, Arunkumar [Department of Mechanical Engineering, Indian Institute of Technology Bombay, Powai, Mumbai 400 076 (India)

2010-11-15T23:59:59.000Z

330

Plutonium-aerosol emission rates and human pulmonary deposition calculations for Nuclear Site 201, Nevada Test Site  

SciTech Connect

This study determined the plutonium-aerosol fluxes from the soil to quantify (1) the extent of potential human exposure by deep-lung retention of alpha-emitting particles; (2) the source term should there be any significant, long-term, transport of plutonium aerosols; and (3) the resuspension factor and rate so that, for the first time at any nuclear site, one may calculate how long it will take for wind erosion to carry away a significant amount of the contaminated soil. High-volume air samplers and cascade impactors were used to characterize the plutonium aerosols. Meteorological flux-profile methods were used to calculate dust and plutonium aerosol emission rates. A floorless wind tunnel (10-m long) was used to examine resuspension under steady-state, high wind speed. The resuspension factor was two orders of magnitude lower than the other comparable sites at NTS and elsewhere, and the average resuspension rate of 5.3 x 10/sup -8//d was also very low, so that the half-time for resuspension by wind erosion was about 36,000 y.

Shinn, J.H.; Homan, D.N.

1982-06-21T23:59:59.000Z

331

Citizens' social media use and homeland security information policy: Some evidences from Twitter users during the 2013 North Korea nuclear test  

Science Journals Connector (OSTI)

Abstract In the era of Web 2.0, managing risk communication on social networking sites has increasingly become crucial and complicated issues in the field of homeland security. The response to the 2013 nuclear test in North Korea was largely based on a coordinated effort by Korea's Ministry of Defense, the United Nations, and many countries from around the globe. By analyzing risk communication networks emerged from Twitter users for the period from January 30 to February 24, 2013, this study investigates the way in which citizens' risk communication is formulated through social media and how they transmit risk information in homeland security. Analysis results show the dynamic evolution of risk communication networks based on influential actors with critical information who played pivotal roles in distributing this information to other actors.

Kyujin Jung; Han Woo Park

2014-01-01T23:59:59.000Z

332

Can we remove iodine-131 from tap water in Japan by boiling? Experimental testing in response to the Fukushima Daiichi Nuclear Power Plant accident  

Science Journals Connector (OSTI)

Iodine-131 concentrations in tap water higher than 100BqL?1 were reported by several local governments in Japan following the Fukushima Daiichi Nuclear Power Plant accident. Some individuals in the emergency-response community recommended the boiling of tap water to remove iodine-131. However, the tap water boiling tests in this study showed no iodine-131 loss from the tap water with either short-term boiling (110min) or prolonged boiling (up to 30min) resulting in up to 3-fold volume reductions. In this situation, boiling was shown to be not effective in removing iodine-131 from tap water; indeed even higher concentrations may result from the liquid-volume reduction accompanying this process.

K. Tagami; S. Uchida

2011-01-01T23:59:59.000Z

333

World nuclear outlook 1995  

SciTech Connect

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

334

Nuclear Waste Storage in Gel-Derived Materials  

Science Journals Connector (OSTI)

For long life nuclear wastes (essentially actinides) research is in progress ... a process to prepare silica glass embedding the nuclear waste. Porous silica (gel) is used as a host matrix for nuclear waste. Neod...

T. Woignier; J. Reynes; J. Phalippou

2000-12-01T23:59:59.000Z

335

REAC/TS | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

serves as the premier technical leader in responding to and successfully resolving nuclear and radiological threats worldwide. When the need arises, NNSA is prepared to respond...

336

Preparation of Nonreactor Nuclear Facility Documented Safety...  

Energy Savers (EERE)

of such hazards might include the generation of flammableexplosive hydrogen gas by electrolysis of uranium in water or a spill of sodium hydroxide used in radioactive waste...

337

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

SciTech Connect

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, Mexicoto the Government of Mexico (GOM).

Hughes, Jamie D.

2012-05-30T23:59:59.000Z

338

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

339

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

340

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

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

Plan for integrated testing for NNWSI [Nevada Nuclear Waste Storage Investigations] non EQ3/6 data base portion  

SciTech Connect

The purposes of the Integrated Testing Task are to develop laboratory data on thermodynamic properties for actinide and fission product elements for use in the EQ3/6 geochemical modelling code; to determine the transport properties of radionuclides in the near-field environment; and develop and validate a model to describe the rate of release of radionuclides from the near-field environment. Activities to achieve the firs item have been described in the Scientific Investigation Plan for EQ3/6, where quality assurance levels were assigned to the acitivities. This Scientific Investigation Plan describes activities to achieve the second and third purposes. The information gathered in these activities will be used to assess compliance with the performance objective for the Engineered Barrier System (EBS) to control the rate of release of radionuclides if the repository license application includes part of the host rock; to provide a source term for release of radionuclides from the waste package near-field environment to the system performance assessment task for use in showing compliance with the Environmental Protection Agency requirements; and to provide a source term for release of radionculides from the waste package near-field environment to the system performance assessment task for use in doing calculations of cumulative releases of radionuclides from the repository over 100,000 years as required by the site evaluation process. 5 refs.

Oversby, V.M.

1987-05-29T23:59:59.000Z

342

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

343

Plutonium Pits | National Nuclear Security Administration  

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

To ensure the reliability, safety, and security of nuclear weapons without underground nuclear testing; weapons go through a surveillance process, where they are regularly taken...

344

Dismantlement and Disposition | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

Maintaining the safety, security and effectiveness of the nuclear deterrent without nuclear testing - especially at lower numbers - requires increased investments across the...

345

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

SciTech Connect

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

346

Chemical decontamination specification preparation  

SciTech Connect

Since the first low-concentration chemical decontamination in the United States at Vermont Yankee in 1979, > 75 decontamination applications have been made at > 20 nuclear electrical generating stations. Chemical decontamination has become a common technique for reducing person-rem exposures. Two vendors are currently offering low-concentration chemical decontamination reagents for application in boiling water reactor and pressurized water reactor systems. All technical aspects associated with the chemical decontamination technology have been commercially tested and are well advanced beyond the research and development stage. Extensive corrosion and material compatibility testing has been performed on the major solvent systems with satisfactory results. The material compatibility testing for the three main solvent systems, CANDECON, CITROX, and LOMI, has been documented in numerous Electric Power Research Institute reports.

Miller, M.A.; Remark, J.F.; Vandergriff, D.M.

1988-01-01T23:59:59.000Z

347

Combating nuclear terrorism | Y-12 National Security Complex  

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

uranium in multiple forms and enrichments to test nuclear detection devices. Y-12's Nuclear Detection and Sensor Testing Center and other site programs are invaluable in...

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

Standard test methods for chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade aluminum oxide and aluminum oxide-boron carbide composite pellets  

E-Print Network (OSTI)

1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade aluminum oxide and aluminum oxide-boron carbide composite pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Boron by Titrimetry 7 to 13 Separation of Boron for Mass Spectrometry 14 to 19 Isotopic Composition by Mass Spectrometry 20 to 23 Separation of Halides by Pyrohydrolysis 24 to 27 Fluoride by Ion-Selective Electrode 28 to 30 Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 31 to 33 Trace Elements by Emission Spectroscopy 34 to 46 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. (F...

American Society for Testing and Materials. Philadelphia

1994-01-01T23:59:59.000Z

350

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

351

Testing Software with Pexpect 1 Testing Computer Algebra Systems  

E-Print Network (OSTI)

Testing Software with Pexpect 1 Testing Computer Algebra Systems testing software preparing the test suite replacing print with assert statements 2 Automating Tests with Pexpect testing SymPy in Sage with Pexpect running the test on SymPy in Sage applying Pexpect to test the factorizations MCS 507 Lecture 39

Verschelde, Jan

352

Nuclear Energy  

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

Research Programs >> Nuclear Energy Error Error Nuclear Energy Home - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Energy Home - RCC * Increasing...

353

Testing and Performance Validation of a Sensitive Gamma Ray Camera Designed for Radiation Detection and Decommissioning Measurements in Nuclear Facilities-13044  

SciTech Connect

This paper describes the measurements, testing and performance validation of a sensitive gamma ray camera designed for radiation detection and quantification in the environment and decommissioning and hold-up measurements in nuclear facilities. The instrument, which is known as RadSearch, combines a sensitive and highly collimated LaBr{sub 3} scintillation detector with an optical (video) camera with controllable zoom and focus and a laser range finder in one detector head. The LaBr{sub 3} detector has a typical energy resolution of between 2.5% and 3% at the 662 keV energy of Cs-137 compared to that of NaI detectors with a resolution of typically 7% to 8% at the same energy. At this energy the tungsten shielding of the detector provides a shielding ratio of greater than 900:1 in the forward direction and 100:1 on the sides and from the rear. The detector head is mounted on a pan/tile mechanism with a range of motion of 180 degrees (pan) and 90 degrees (tilt) equivalent to 4 ? steradians. The detector head with pan/tilt is normally mounted on a tripod or wheeled cart. It can also be mounted on vehicles or a mobile robot for access to high dose-rate areas and areas with high levels of contamination. Ethernet connects RadSearch to a ruggedized notebook computer from which it is operated and controlled. Power can be supplied either as 24-volts DC from a battery or as 50 volts DC supplied by a small mains (110 or 230 VAC) power supply unit that is co-located with the controlling notebook computer. In this latter case both power and Ethernet are supplied through a single cable that can be up to 80 metres in length. If a local battery supplies power, the unit can be controlled through wireless Ethernet. Both manual operation and automatic scanning of surfaces and objects is available through the software interface on the notebook computer. For each scan element making up a part of an overall scanned area, the unit measures a gamma ray spectrum. Multiple radionuclides may be selected by the operator and will be identified if present. In scanning operation the unit scans a designated region and superimposes over a video image the distribution of measured radioactivity. For the total scanned area or object RadSearch determines the total activity of operator selected radionuclides present and the gamma dose-rate measured at the detector head. Results of hold-up measurements made in a nuclear facility are presented, as are test measurements of point sources distributed arbitrarily on surfaces. These latter results are compared with the results of benchmarked MCNP Monte Carlo calculations. The use of the device for hold-up and decommissioning measurements is validated. (authors)

Mason, John A.; Looman, Marc R.; Poundall, Adam J.; Towner, Antony C.N. [ANTECH, A. N. Technology Ltd., Unit 6, Thames Park, Wallingford, Oxfordshire, OX10 9TA (United Kingdom)] [ANTECH, A. N. Technology Ltd., Unit 6, Thames Park, Wallingford, Oxfordshire, OX10 9TA (United Kingdom); Creed, Richard; Pancake, Daniel [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States)] [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States)

2013-07-01T23:59:59.000Z

354

Nuclear Debate  

Science Journals Connector (OSTI)

Nuclear Debate ... This month, the Senate will consider the nominations of two women to serve on the Nuclear Regulatory Commission. ... Svinicki is a nuclear engineer with experience in the Department of Energys nuclear energy programs. ...

JEFF JOHNSON

2012-06-11T23:59:59.000Z

355

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,

356

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network (OSTI)

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington are pleased to transmit a technical report prepared by the Nuclear Waste Technical Review Board (Board. Based on its review of data gathered by the DOE and the Center for Nuclear Waste Regulatory Analyses

357

Spent Nuclear Fuel Fact Sheets  

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

management needs. By coordinating common needs for research, technology development, and testing programs, the National Spent Nuclear Fuel Program is achieving cost efficiencies...

358

Surface effects of underground nuclear explosions  

SciTech Connect

The effects of nuclear explosions have been observed and studied since the first nuclear test (code named Trinity) on July 16, 1945. Since that first detonation, 1,053 nuclear tests have been conducted by the US, most of which were sited underground at the Nevada Test Site (NTS). The effects of underground nuclear explosions (UNEs) on their surroundings have long been the object of much interest and study, especially for containment, engineering, and treaty verification purposes. One aspect of these explosion-induced phenomena is the disruption or alteration of the near-surface environment, also known as surface effects. This report was prepared at the request of the Los Alamos National Laboratory (LANL), to bring together, correlate, and preserve information and techniques used in the recognition and documentation of surface effects of UNEs. This report has several main sections, including pertinent background information (Section 2.0), descriptions of the different types of surface effects (Section 3.0), discussion of their application and limitations (Section 4.0), an extensive bibliography and glossary (Section 6.0 and Appendix A), and procedures used to document geologic surface effects at the NTS (Appendix C). Because a majority of US surface-effects experience is from the NTS, an overview of pertinent NTS-specific information also is provided in Appendix B. It is not within the scope of this report to explore new relationships among test parameters, physiographic setting, and the types or degree of manifestation of surface effects, but rather to compile, summarize, and capture surface-effects observations and interpretations, as well as documentation procedures and the rationale behind them.

Allen, B.M.; Drellack, S.L. Jr.; Townsend, M.J.

1997-06-01T23:59:59.000Z

359

Preparation and orientation of solid  

Science Journals Connector (OSTI)

We have prepared solid 3He crystals under constant volume conditions and characterized them by neutron diffraction and transmission. The ultimate aim of the work was the preparation of samples suitable for neutron diffraction investigations of the antiferromagnetic nuclear ordering of solid 3He below 1mK. We describe results from different sample cells, and we have derived the relevant design parameters with respect to (a) the neutron signal and background requirements, (b) the requirements of experiments at ultra-low temperature and (c) the mechanical properties for work at high pressure. The techniques of the 3He crystal growth at pressure between 4 and 6MPa and at low temperature are described, together with a strategy for the crystal orientation and background reduction. As a result, large 3He single crystals of good quality were obtained. With such samples, neutron experiments on magnetic order in solid 3He at ultra-low temperature shift to the experimentally feasible regime.

V Boiko; S Matas; K Siemensmeyer

2008-01-01T23:59:59.000Z

360

Advanced Test Reactor Tour  

SciTech Connect

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2011-01-01T23:59:59.000Z

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

Advanced Test Reactor Tour  

ScienceCinema (OSTI)

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2013-05-28T23:59:59.000Z

362

Tag: nuclear deterrence  

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

The group toured facilities at the site, including production buildings and Y-12's Nuclear Detection and Sensor Testing Center.

363

EIS-0350-S1: Notice of Intent to Prepare a Supplemental Environmental...  

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

Prepare a Supplemental Environmental Impact Statement Nuclear Facility Portion of the Chemistry and Metallurgy Research Building Replacement Project at Los Alamos National...

364

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

365

Nuclear Safety Information | Department of Energy  

Office of Environmental Management (EM)

Safety Information Nuclear Safety Information Idaho National Laboratory's Advanced Test Reactor (ATR) | April 8, 2009 Idaho National Laboratory's Advanced Test Reactor (ATR) |...

366

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

367

E-Print Network 3.0 - alternative nuclear energy Sample Search...  

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

Powered by Explorit Topic List Advanced Search Sample search results for: alternative nuclear energy Page: << < 1 2 3 4 5 > >> 1 Preparing Non-nuclear Engineers for the Nuclear...

368

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

369

Nuclear Returns  

Science Journals Connector (OSTI)

Nuclear Returns ... For the first time since 1978, the Nuclear Regulatory Commission has given the green light for a new U.S. nuclear power plant. ... NRC granted a license to Southern Co. to build and operate twin 1,100-MW reactors adjacent to two operating nuclear power plants at its Vogtle nuclear facility, near Waynesboro, Ga. ...

JEFF JOHNSON

2012-02-19T23:59:59.000Z

370

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

371

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 formsalkali-aluminosilicate hydroceramic cement, Ceramicrete phosphate-bonded ceramic, and DuraLith alkali-aluminosilicate geopolymerwere 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

372

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

SciTech Connect

The purpose of the Independent Verification and Validation (IV&V) role in the evaluation of the SAPHIRE 8 Software Acceptance Test Plan is to assess the approach to be taken for intended testing activities. The plan typically identifies the items to be tested, the requirements being tested, the testing to be performed, test schedules, personnel requirements, reporting requirements, evaluation criteria, and any risks requiring contingency planning. The IV&V team began this endeavor after the software engineering and software development of SAPHIRE had already been in production.

Kent Norris

2010-03-01T23:59:59.000Z

373

AIChE issues nuclear waste conclusions  

Science Journals Connector (OSTI)

AIChE issues nuclear waste conclusions ... Long and extensive research, development, and demonstration activities in the U.S. and abroad have made possible the safe, permanent disposal of high-level commercial nuclear waste. ... Titled "The U.S. High-Level Nuclear Waste Management Program," it was prepared by an AIChE nuclear engineering division task force for the institute's government programs steering committee. ...

1986-02-10T23:59:59.000Z

374

Nuclear Propulsion in Space (1968)  

ScienceCinema (OSTI)

Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

None

2014-06-17T23:59:59.000Z

375

Nuclear Propulsion in Space (1968)  

SciTech Connect

Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

None

2012-06-23T23:59:59.000Z

376

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

377

Nuclear Fusion  

Science Journals Connector (OSTI)

Although not yet developed at the commercial stage, nuclear fusion technology is still being considered as a ... used in nuclear warfare. Since research in nuclear fusion for the production of energy started abou...

Ricardo Guerrero-Lemus; Jos Manuel Martnez-Duart

2013-01-01T23:59:59.000Z

378

Nuclear Nonproliferation  

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

Nuclear Nonproliferation As more countries embrace nuclear power as a cost-effective and clean alternative to fossil fuels, the need exists to ensure that the nuclear fuel cycle is...

379

Nevada National Security Site Groundwater Program Prepares for...  

Energy Savers (EERE)

the site in preparation for an independent peer review of the historic underground test area, Frenchman Flat. In August 2010, the peer review panel found model projections to...

380

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

Office of Environmental Management (EM)

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...

Note: This page contains sample records for the topic "nuclear test prepared" from the National Library of EnergyBeta (NLEBeta).
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to obtain the most current and comprehensive results.


381

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network (OSTI)

Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

Kemner, Ken

382

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.

383

Y-12 and the National Nuclear Security Administration make continuing...  

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

the safety, security and performance of the U.S. nuclear weapons stockpile without nuclear testing; reduces the global danger from weapons of mass destruction; provides the...

384

Passing good judgment, part 1: weapons designers with nuclear...  

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

2014 All Issues submit Passing good judgment, part 1: weapons designers with nuclear testing experience The nuclear weapons designers who developed their skills during...

385

Welcome to the Los Alamos Field Office | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

security, reliability and performance of the U.S. nuclear weapons stockpile without nuclear testing; works to reduce global danger from weapons of mass destruction; provides...

386

NUCLEAR REACTORS.  

E-Print Network (OSTI)

??Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain (more)

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

387

nuclear reactor  

Science Journals Connector (OSTI)

...a complex atomic apparatus used to obtain energy from nuclear fission chain reaction. Used to produce nuclear energy, radioactive isotopes, and artificial elements.... atomic pile ...

2009-01-01T23:59:59.000Z

388

Nuclear Energy  

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

Nuclear Energy Idaho National Laboratory is the Department of Energy's lead nuclear energy research and development facility. Building upon its legacy responsibilities,...

389

Nuclear Hydrogen  

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

Error Error Nuclear Hydrogen - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Hydrogen - RCC * Increasing your portlet timeout setting. *...

390

Nuclear Physics  

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

Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

391

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

392

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

393

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

394

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

395

Whats Next for Nuclear Waste  

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

WHAT'S NEXT FOR NUCLEAR WASTE? A New Strategy for the CSRA September 2009 PREFACE This White Paper was prepared by the Savannah River Site Community Reuse Organization (SRSCRO) to...

396

Nuclear choices  

SciTech Connect

This book contains part of the series New Liberal Arts, which is intended to make science and technology more accessible to students of the liberal arts. Volume in hand provides a comprehensive, multifaceted examination of nuclear energy, in nontechnical terms. Wolfson explains the basics of nuclear energy and radiation, nuclear power..., and nuclear weapons..., and he invites readers to make their own judgments on controversial nuclear issues. Illustrated with photos and diagrams. Each chapter contains suggestions for additional reading and a glossary. For policy, science, and general collections in all libraries. (ES) Topics contained include Atoms and nuclei. Effects and uses of radiation. Energy and People. Reactor safety. Nuclear strategy. Defense in the nuclear age. Nuclear power, nuclear weapons, and nuclear futures.

Wolfson, R.

1991-01-01T23:59:59.000Z

397

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.

398

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.

399

Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830  

E-Print Network (OSTI)

PNNL-21950 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Recommended Job Code V6237 U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research Washington, D

400

Plowshare Program - American Atomic Bomb Tests For Industrial Applications  

SciTech Connect

The United States Atomic Energy Commission (AEC) established the Plowshare Program as a research and development activity to explore the technical and economic feasibility of using nuclear explosives for industrial applications. The reasoning was that the relatively inexpensive energy available from nuclear explosions could prove useful for a wide variety of peaceful purposes. The Plowshare Program began in 1958 and continued through 1975. Between December 1961 and May 1973, the United States conducted 27 Plowshare nuclear explosive tests comprising 35 individual detonations. Conceptually, industrial applications resulting from the use of nuclear explosives could be divided into two broad categories: 1) large-scale excavation and quarrying, where the energy from the explosion was used to break up and/or move rock; and 2) underground engineering, where the energy released from deeply buried nuclear explosives increased the permeability and porosity of the rock by massive breaking and fracturing. Possible excavation applications included: canals, harbors, highway and railroad cuts through mountains, open pit mining, construction of dams, and other quarry and construction-related projects. Underground nuclear explosion applications included: stimulation of natural gas production, preparation of leachable ore bodies for in situ leaching, creation of underground zones of fractured oil shale for in situ retorting, and formation of underground natural gas and petroleum storage reservoirs.

None

2012-04-22T23:59:59.000Z

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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401

Preparation of acetaldehyde  

DOE Patents (OSTI)

Disclosed is a process for the preparation of acetaldehyde by the hydrogenation of ketene in the presence of a transition metal hydrogenation catalyst.

Tustin, Gerald Charles (Kingsport, TN); Depew, Leslie Sharon (Kingsport, TN)

1997-10-21T23:59:59.000Z

402

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

403

Preparation of an In Vivo radiobioassay program for accreditation  

E-Print Network (OSTI)

The Nevada Test Site was operated by the Department of Energy's Nevada Operations Office (DOE/NV), through 1992, as a test facility for nuclear weapons. This resulted in an environment with many unique hazards, including areas that when disturbed...

Hoyt, Joel Rainer

2012-06-07T23:59:59.000Z

404

defense nuclear security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

nuclear security | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

405

Chernobyl Nuclear Accident | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Chernobyl Nuclear Accident | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

406

Countering Nuclear Terrorism and Trafficking | National Nuclear...  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism and Trafficking | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

407

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

PETRO-PLUG PETRO-PLUG BENTONITE PLUGGING JANUARY 27, 1998 Report No. RMOTC/97PT22 ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS PETRO-PLUG BENTONITE PLUGGING Prepared for: INDUSTRY PUBLICATION Prepared by: Michael R. Tyler RMOTC Project Manager January 27, 1998 Report No. RMOTC/96ET4 CONTENTS Page Technical Description ...................................................................................................... 1 Problem ............................................................................................................................ 1 Solution ............................................................................................................................ 2 Operation..........................................................................................................................

408

Testing, Training, and Signature Devices | Y-12 National Security...  

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

Testing, Training, and ... Testing, Training, and Signature Devices Y-12 manufactures specialized uranium testing, training, and signature devices to support the nuclear detection...

409

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

410

E-Print Network 3.0 - atomic weapon tests Sample Search Results  

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

By dissembling random nuclear weapons in the stockpile and closely inspecting and testing... explosives and nuclear materials at the Nevada Test Site to gather diagnostic...

411

EV America Skid Test Procedure  

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

6 6 Revision 2 Effective October 1, 2007 Braking Test Prepared by Electric Transportation Applications Prepared by: _______________________________ Date: _________ Roberta Brayer Approved by: _________________________________________________ Date: _______________ Donald Karner Procedure ETA-HTP06 Revision 2 i TABLE OF CONTENTS 1. Objectives 1 2. Purpose 1 3. Documentation 1 4. Initial Conditions and Prerequisites 1 5. Testing Activity Requirements 3 5.3 Dry Controlled Test 4 6. Glossary 5 7. References 7 Appendices Appendix A - Handling Pad Test Data Sheet 8

412

First Subcritical Experiment Conducted at Nevada Test Site |...  

National Nuclear Security Administration (NNSA)

Subcritical Experiment Conducted at Nevada Test Site | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear...

413

Cost analysis of revisions to 10 CFR Part 50, Appendix J, leak tests for primary and secondary containments of light-water-cooled nuclear power plants  

SciTech Connect

The report examines the differences between the existing and proposed Appendix J and identifies eleven substantive areas where quantifiable impacts will likely result. The analysis indicated that there are four areas of change which tend to dominate all others in terms of cost impacts. The applicable paragraph numbers from Draft E2 of the Appendix J revision and the nature of the change follows: III.A(4) and III.A(6) - Test Pressure and Testing at Reduced Pressure No Longer Allowed; III.A(7)(b)(i) Acceptance Criteria 1.0 L/sub a/ Acceptable ''As Found'' Leakage; III.A(8)(2) Retesting Following Failure of ''As Found'' Type A Test - Corrective Action Plan, and III.A(8)(b)(ii) Option To Do More Frequent Type B and C Testing Rather Than More Type A Penalty Tests. The best estimate is that the proposed Appendix J would result in a cost savings ranging from about $100 million to $160 million, and increase routing occupational exposure on the order of 10,000 person-rem. These estimates capture the total impact to industry and the NRC over the assumed operating life of all existing and planned future power reactors. All dollar impacts projected to occur in future years have been present worthed at discount rates ranging from 5% to 10%.

Sciacca, F.; Nelson, W.; Simpkins, B.; Riordan, B.; Godfrey, P.; Cohen, S.; Beal, S.; Goldin, D.

1985-09-01T23:59:59.000Z

414

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

415

High Temperature Test Laboratory Accomplishments  

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

Knudson, K. Condie, and B. Sencer, "In-situ Creep Testing Capability for the Advanced Test Reactor," Nuclear Technology, 179, 3, September 2012, pp 413-428. B. Geslot, T. Unruh,...

416

Mitch S. Daugherty Nuclear Engineering and Planning Manager  

E-Print Network (OSTI)

Mitch 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. Daugherty also headed the Nuclear Refueling Division, the Nuclear Test Engineering Division, and the Nuclear

417

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

418

Nuclear reactions  

Science Journals Connector (OSTI)

Much reference has been made in the last chapter to nuclear energy levels and their various properties (e.g ... ways of doing this the use of nuclear reactions, and studies of how excited nuclei...

R. J. Blin-Stoyle FRS

1991-01-01T23:59:59.000Z

419

nuclear security  

National Nuclear Security Administration (NNSA)

3%2A en Shaping the future of nuclear detection http:nnsa.energy.govblogshaping-future-nuclear-detection

420

Y-12, the Cold War, and nuclear weapons dismantlement ? Or:...  

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

a huge mission for Y-12 bringing about substantial growth and continued to do so until nuclear testing ended in 1992. The United States tested nuclear weapons from July 16, 1945...

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.


421

Nuclear Ukraine  

Science Journals Connector (OSTI)

... SIR - Your article (Nature 365, 599; 1993) on the US-Ukraine stalemate over nuclear weapons prompts the following remarks. The United States made a mistake ... nuclear weapons prompts the following remarks. The United States made a mistake in not recognizing Ukraine as a legitimate successor state to the Soviet nuclear arsenal and is still insisting that ...

Arno Arrak

1994-01-13T23:59:59.000Z

422

Nevada Test Site Environmental Summary Report 2006  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2006 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and its satellite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

Cathy Wills

2007-10-01T23:59:59.000Z

423

Nevada Test Site Summary 2006 (Volume 2)  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security-related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2006 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and its satellite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

Cathy Wills

2007-10-01T23:59:59.000Z

424

Nuclear Engineer (Nuclear Safety Specialist)  

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

A successful candidate of this position will serve as a Nuclear Engineer (Nuclear Safety Specialist) responsible for day-to-day technical monitoring, and evaluation of aspects of authorization...

425

Nuclear Reactor Safety Design Criteria  

Directives, Delegations, and Requirements

The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Certified 11-18-10.

1993-01-19T23:59:59.000Z

426

INT Summer School Proposal Lattice QCD for Nuclear Physics  

E-Print Network (OSTI)

INT Summer School Proposal Lattice QCD for Nuclear Physics Organizers Huey-Wen Lin Department of Nuclear Physics, Johann-Joachim-Becher-Weg 45 55099 Mainz, Germany meyerh@kph.uni-mainz.de David Richards techniques to the study of nuclear physics. The goal of this summer school is to educate and prepare the next

Washington at Seattle, University of - Department of Physics, Electroweak Interaction Research Group

427

Alexey Anisyonkov Budker Institute of Nuclear Physics  

E-Print Network (OSTI)

Alexey Anisyonkov Budker Institute of Nuclear Physics (BINP, Novosibirsk) ATLAS Grid Information policy List of Activities and its properties (Functional Tests, re(Processing), Data distribution, ..

428

Sandia National Laboratories: National Security Missions: Nuclear...  

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

& Technology National labs provide the science and technology to maintain and certify the nuclear stockpile in the absence of full-scale weapons testing. The facilities and...

429

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

430

Order Module--DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR FACILITY  

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

DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS Order Module--DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS The familiar level of this module is divided into two sections that are intended to provide only an overview of the material contained in DOE-STD-1104-2009, which should be consulted for complete information. The first section covers the introduction, applicability, and chapters 1 and 2. The second section covers chapters 3, 4, and 5. We have provided examples throughout the module to help familiarize you with the material. The examples will also help prepare you for the practice at the end of this module and for the criterion test.

431

Advances in Metallic Nuclear Fuel  

Science Journals Connector (OSTI)

Metallic nuclear fuels have generated renewed interest for advanced ... operations is excellent. Ongoing irradiation tests in Argonne-Wests Idaho-based Experimental Breeder Reactor ... fast reactor (IFR) concept...

B. R. Seidel; L. C. Walters; Y. I. Chang

1987-04-01T23:59:59.000Z

432

Being Prepared to Borrow  

E-Print Network (OSTI)

Almost all farmers and ranchers rely on credit at times. Before approaching a lender, certain information must be gathered and decisions made. The 12 questions in this publication lead the prospective borrower through this preparation process....

Klinefelter, Danny A.

2003-01-06T23:59:59.000Z

433

BPA prepares for Jan  

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

is a Statement of Intent? A Statement of Intent, or SOI, is a statement, prepared by BPA and signed by an eligible customer, that describes the approach and cost structure that...

434

PROCEDURE FOR PREPARING  

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

PROCEDURE FOR PREPARING PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) Revision 1 November 1, 2007 Records Management Division, IM-23 PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) 1. If the records have not yet been inventoried, see "Procedure for Conducting a Records Inventory." An inventory must be completed prior to preparing the RIDS. 2. The Records Inventory and Disposition Schedules (RIDS) should be reviewed and updated at least annually on DOE F 1324.10 and DOE F 1324.9. The RIDS covers all record, administrative and programmatic, as well as non- record material. The RIDS must include: a. Complete and detailed information identifying the organization (s) responsible for the records.

435

Rough Ride Test Procedure  

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

NTP005 NTP005 Revision 2 Effective December 1, 2004 Electric Vehicle Rough Road Course Test Prepared by Electric Transportation Applications Prepared by: _______________________________ Date:__________ Ryan Harkins Approved by: _________________________________________________ Date: _______________ Donald B. Karner ©2004 Electric Transportation Applications All Rights Reserved Procedure ETA-NTP005 Revision 2 2 TABLE OF CONTENTS 1.0 Objectives 3 2.0 Purpose 3 3.0 Documentation 3 4.0 Initial Conditions and Prerequisites 4 5.0 Testing Activity Requirements 6 6.0 Glossary 12 7.0 References 14 Appendices Appendix A - Electric Vehicle Rough Road Test Data Sheet 15

436

Preparing for the Future  

E-Print Network (OSTI)

tx H2O | pg. 12 Preparing for the Future Story by Kathy Wythe Preparing for the Future University establishes water management degree program Texas A&M University launched an interdisci-plinary water management degree programduring the fall... 2005 semester with 12 stu-dents seeking either master?s or doctorate degrees in water management and hydrologic sciences. The degree program, the first in Texas, includes 42 faculty members in 12 departments from four differ- ent colleges, said Ron...

Wythe, Kathy

2006-01-01T23:59:59.000Z

437

Yeast Immunofluorescence Prepare Cells  

E-Print Network (OSTI)

slide. Resuspend in up to 250 µl SPC buffer to prepare up to 5 slides. #12;Prepare Slide: 11. Use clean 15-well slide(s). Start with 25 µl of 2 mg/ml poly-D-lysine (Sigma P-1024) per slide. Pipet on and then off, leaving a thin film on slide well. Hold at room temperature for 1 minute. Wash slide using

Aris, John P.

438

Nevada Test Site annual site environmental report for calendar year 1998  

SciTech Connect

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring Programs conducted by the US Environmental Protection Agency's (EPA) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this tenth combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Black, S.C.; Townsend, Y.E.

1999-10-01T23:59:59.000Z

439

Nevada Test Site Annual Site Environmental Report for Calendar Year - 1999  

SciTech Connect

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the U.S. Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring programs conducted by the U.S. Environmental Protection Agency's (EPA's) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this eleventh combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Townsend, Y.E.; Grossman, R.F.

2000-10-01T23:59:59.000Z

440

Advanced Heat Exchanger Development for Molten Salts in Nuclear and Non Nuclear Systems  

SciTech Connect

This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better define the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.

Piyush Sabharwall; Denis Clark; Kumar Sridharan; Guiqiu Zheng; Mark Anderson

2014-10-01T23:59:59.000Z

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.


441

ROCKY MOUNTAIN OILFIELD TESTING CENTER PROJECT TEST RESULTS  

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

D-JAX PUMP-OFF CONTROLLER D-JAX PUMP-OFF CONTROLLER APRIL 4,1995 FC9510 / 95PT4 ROCKY MOUNTAIN OILFIELD TESTING CENTER D-JAX PUMP-OFF CONTROLLER PROJECT TEST RESULTES Prepared for: Industry Publication Prepared by: MICHAEL R. TYLER RMOTC Field Engineer April 4, 1995 55103/9510:jb CONTENTS Page Introduction........................................................................................1 NPR-3 Map........................................................................................2 Benefits of D-JAX Pump-Off Controller.....................................................3 Test Results.......................................................................................3 Production Information..........................................................................4

442

NRC - regulator of nuclear safety  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

NONE

1997-05-01T23:59:59.000Z

443

Nuclear Medicine | More Science | ORNL  

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

Nuclear Medicine Nuclear Medicine SHARE Nuclear Medicine The Medical Isotope Program is focused on the development of: improved reactor production and processing methods to provide medical radioisotopes; new radionuclide generator systems; design and evaluation of new radiopharmaceuticals for applications in nuclear medicine and oncology; and association with Medical Cooperative Programs throughout the world for the further pre-clinical testing and clinical evaluation of agents developed at ORNL. In the United States, only ORNL has the combined resources of a stable isotope inventory, the High Flux Isotope Reactor (HFIR), hot cell processing capabilities, and a wide range of support functions required for such research. These collective resources provide unique capabilities for

444

Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010  

SciTech Connect

The Lawrence Livermore National Laboratory uses neutron activation elements in a Panasonic TLD holder as a personnel nuclear accident dosimeter (PNAD). The LLNL PNAD has periodically been tested using a Cf-252 neutron source, however until 2009, it was more than 25 years since the PNAD has been tested against a source of neutrons that arise from a reactor generated neutron spectrum that simulates a criticality. In October 2009, LLNL participated in an intercomparison of nuclear accident dosimeters at the CEA Valduc Silene reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison of nuclear accident dosimeters at CEA Valduc. The reactor generated neutron irradiations for the 2010 exercise were performed at the Caliban reactor. The Caliban results are described in this report. The procedure for measuring the nuclear accident dosimeters in the event of an accident has a solid foundation based on many experimental results and comparisons. The entire process, from receiving the activated NADs to collecting and storing them after counting was executed successfully in a field based operation. Under normal conditions at LLNL, detectors are ready and available 24/7 to perform the necessary measurement of nuclear accident components. Likewise LLNL maintains processing laboratories that are separated from the areas where measurements occur, but contained within the same facility for easy movement from processing area to measurement area. In the event of a loss of LLNL permanent facilities, the Caliban and previous Silene exercises have demonstrated that LLNL can establish field operations that will very good nuclear accident dosimetry results. There are still several aspects of LLNL's nuclear accident dosimetry program that have not been tested or confirmed. For instance, LLNL's method for using of biological samples (blood and hair) has not been verified since the method was first developed in the 1980's. Because LLNL and the other DOE participants were limited in what they were allowed to do at the Caliban and Silene exercises and testing of various elements of the nuclear accident dosimetry programs cannot always be performed as guests at other sites, it has become evident that DOE needs its own capability to test nuclear accident dosimeters. Angular dependence determination and correction factors for NADs desperately need testing as well as more evaluation regarding the correct determination of gamma doses. It will be critical to properly design any testing facility so that the necessary experiments can be performed by DOE laboratories as well as guest laboratories. Alternate methods of dose assessment such as using various metals commonly found in pockets and clothing have yet to be evaluated. The DOE is planning to utilize the Godiva or Flattop reactor for testing nuclear accident dosimeters. LLNL has been assigned the primary operational authority for such testing. Proper testing of nuclear accident dosimeters will require highly specific characterization of the pulse fields. Just as important as the characterization of the pulsed fields will be the design of facilities used to process the NADs. Appropriate facilities will be needed to allow for early access to dosimeters to test and develop quick sorting techniques. These facilities will need appropriate laboratory preparation space and an area for measurements. Finally, such a facility will allow greater numbers of LLNL and DOE laboratory personnel to train on the processing and interpretation of nuclear accident dosimeters and results. Until this facility is fully operational for test purposes, DOE laboratories may need to continue periodic testing as guests of other reactor facilities such as Silene and Caliban.

Hickman, D P; Wysong, A R; Heinrichs, D P; Wong, C T; Merritt, M J; Topper, J D; Gressmann, F A; Madden, D J

2011-06-21T23:59:59.000Z

445

RMOTC TEST REPORT  

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

MUD DEVIL - DEAERATOR MIXER MUD DEVIL - DEAERATOR MIXER MARCH 30, 1995 RMOTC TEST REPORT Mud Devil - Deaerator Mixer Project Test Results Prepared for: INDUSTRY PUBLICATION Prepared by: MICHAEL R. TYLER RMOTC Field Engineer March 30, 1995 551103/9507:jb ABSTRACT The Rocky Mountain Oilfield Testing Center (RMOTC) conducted a field test on the MUD DEVIL - Deaerator Mixer (MDDM), at the Naval Oil Shale Reserve No. 3 (NOSR-3) located west of Rifle, Colorado. Industrial Screen and Maintenance of Casper, Wyoming, manufactures the MDDM high-shear pin mixing system used to blend products in drilling fluid systems. The test was a comparison between DOE Well 1 -M-1 8 drilled without the MDDM and a sidetrack Well 1-M-18 ST drilled with the MDDM. Test results show that the MDDM, when properly used, reduced the usage of drilling fluid products, decreased water

446

Nuclear Systems Modeling and Design Analysis - Nuclear Engineering Division  

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

Nuclear Systems Nuclear Systems Modeling and Design Analysis CAPABILITIES Overview Nuclear Systems Modeling and Design Analysis Nuclear Systems Technologies Risk and Safety Assessments Nonproliferation and National Security Materials Testing Engineering Computation & Design Engineering Experimentation Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Capabilities Nuclear Systems Modeling and Design Analysis Bookmark and Share Reactor Physics and Fuel Cycle Analysis Reactor Physics and Fuel Cycle Analysis We have played a major role in the design and analysis of most existing and past reactor types and of many

447

Review: Preparing for Climate Change  

E-Print Network (OSTI)

Review: Preparing for Climate Change By Michael D.Stephen, Preparing for Climate Change. A Boston Review Book.alkaline paper. Climate change is inevitable, but disaster

Kunnas, Jan

2013-01-01T23:59:59.000Z

448

Nuclear relations in South Asia  

SciTech Connect

The strategic landscape of South Asia changed dramatically in 1998. With the reciprocal testing of nuclear weapons, India and Pakistan emerged from the world of threshold status to an overt posture which has yet to be fully defined. Each claims the status of a nuclear weapon state, yet the contours of that status are unclear. A number of important strategic issues have been raised by these dramatic events. This paper will attempt to examine the implications of this new posture for each country and for the region. First and foremost, the decisions to test nuclear weapons are a product of each individual state making a sovereign decision about its national security needs. Both have made clear for a number of years that their attitudes toward nuclear weapons-and by default, toward nuclear nonproliferation-will not be directed by outsiders. They have rejected the global norms that oppose the further proliferation of nuclear weapons, embodied in the Treaty on the Non- Proliferation of Nuclear Weapons (NPT), and that embrace the ultimate elimination of nuclear weapons, captured in Article VI of that treaty. The decisions reached in New Delhi and lslamabad have been questioned by many, but the tests cannot be undone and it now falls on both countries to make further decisions about what strategies will best serve them, and what obligations they must now assume. Issues such as strategic planning, weaponization, deployment, and command and control, which heretofore were relegated to the back burner, may no longer be deferred.

Joeck, N.

1998-12-18T23:59:59.000Z

449

A Safer Nuclear Enterprise  

Science Journals Connector (OSTI)

...2012 at the Nuclear Security...leadership in nuclear enterprise...multinational assessment of emerging risks and consequences...to assess nuclear risks in...or nuclear terrorism. States...and nuclear power. Since 1945...nuclear power plant can mean...

Sidney D. Drell; George P. Shultz; Steven P. Andreasen

2012-06-08T23:59:59.000Z

450

Nuclear astrophysics  

SciTech Connect

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-12-31T23:59:59.000Z

451

Nuclear astrophysics  

SciTech Connect

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-01-01T23:59:59.000Z

452

Nuclear Counterterrorism  

Directives, Delegations, and Requirements

The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information.) Appendices A and B are Official Use Only. Point of contact is Adam Boyd (NA-82), 202-586-0010. Cancels DOE O 457.1 and DOE M 457.1-1.

2013-08-26T23:59:59.000Z

453

Superallowed 0(+)-> 0(+) nuclear beta decays: A new survey with precision tests of the conserved vector current hypothesis and the standard model  

E-Print Network (OSTI)

published measurements and eliminated 9 references, either because they have been superseded by much more precise modern results or because there are now reasons to consider them fatally flawed...of particular importance, the new data include a number of high-precision Penning-trap measurements of decay energies. Second, we have used the recently improved isospin symmetry-breaking corrections, which were motivated by these new Penning-trap results. Third, our calculation of the statistical rate function f now accounts for possible excitation in the daughter atom, a small effect but one that merits inclusion at the present level of experimental precision. Finally, we have re-examined the systematic uncertainty associated with the isospin symmetry-breaking corrections by evaluating the radial-overlap correction using Hartree-Fock radial wave functions and comparing the results with our earlier calculations, which used Saxon-Woods wave functions...the provision for systematic uncertainty has been changed as a consequence. The new "corrected" Ft values are impressively constant and their average, when combined with the muon lifetime, yields the up-down quark-mixing element of the Cabibbo-Kobayashi-Maskawa (CKM) matrix, V(ud)=0.97425 +/- 0.00022. The unitarity test on the top row of the matrix becomes |V(ud)|(2)+|V(us)|(2)+|V(ub)|(2)=0.99995 +/- 0.00061. Both V(ud) and the unitarity sum have significantly reduced uncertainties compared with our previous survey, although the new value of V(ud) is statistically consistent with the old one. From these data we also set limits on the possible existence of scalar interactions, right-hand currents, and extra Z bosons. Finally, we discuss the priorities for future theoretical and experimental work with the goal of making the CKM unitarity test even more definitive....

Hardy, John C.; Towner, I. S.

2009-01-01T23:59:59.000Z

454

Nuclear Power  

Science Journals Connector (OSTI)

Nuclear Power ... THIS WEEKS issue contains six letters on nuclear power, a representative sample of the letters C&EN received in response to the editorial, Resist Hysteria, I wrote shortly after the earthquake and tsunami in Japan devastated the Fukushima Daiichi Nuclear Power Station (C&EN, March 21, page 5). ... Four of the six letters take sharp issue with the primary point I made in the editorial, which was that, despite the severity of the situation in Japan, nuclear power remains an essential component of our overall energy mix for the near to mid-term because it will help us avert the worst impacts of global climate disruption. ...

RUDY M. BAUM

2011-05-09T23:59:59.000Z

455

NUCLEAR STUDIES  

Science Journals Connector (OSTI)

Japanese nuclear power plant crisis sparks examination of U.S. REACTORS ... Calls are particularly zeroing in on reactors similar in location and design to those in Japan. ...

JEFF JOHNSON

2011-04-04T23:59:59.000Z

456

U.S. DEPARTMEhT OF ENERGY NATIONAL NUCLEAR SECURITY ADMINISTRATION  

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

DEPARTMEhT OF ENERGY DEPARTMEhT OF ENERGY NATIONAL NUCLEAR SECURITY ADMINISTRATION FINDING OF NO SIGNIFICANT IMPACT ATLAS RELOCATION AND OPERATION AT THE NEVADA TEST SITE The National Nuclear Secuxity Administration (NNSA) prepared an Environmental Assessment (EA) (DOEIEA-1381) to analyze the proposed action to relocate the Atlas pulse power machine from Los Alamos National Laboratory (LANL) to the Nevada Test Site (NTS). At the NTS, Atlas would be reassembled in a newly constructed building within a designated Industrial, Research, and Support site in Area 6. After reassembly, Atlas would be commissioned to ensure proper operation and then used to conduct approximately 40 pulsed power experiments per year, with a potential to increase to approximately 100 experiments per year, should the Stockpile Stewardship Program

457

Will our nuclear weapons work?  

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

Will our nuclear weapons work? Will our nuclear weapons work? National Security Science magazine Latest Issue:April 2013 All Issues » submit Supercomputers are essential for assessing the health of the U.S. nuclear stockpile Supercomputers provide assurance by simulating nuclear weapons performance March 25, 2013 Graphic of a missile being tested through computer simulation Los Alamos uses supercomputers to make high-resolution 3D simulations that help to assess the health of nuclear weapons like this B-61 bomb. Contact Managing Editor Clay Dillingham Email The nuclear weapons in the U.S. stockpile were designed and built to be replaced with new designs and builds every 10 to 15 years. These weapons have lived beyond their expected lifespans. Supercomputers provide the high-resolution 3D simulations needed for

458

Nuclear Fuels | Department of Energy  

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

Nuclear Fuels Nuclear Fuels Nuclear Fuels A reactor's ability to produce power efficiently is significantly affected by the composition and configuration of its fuel system. A nuclear fuel assembly consists of hundreds of thousands of uranium pellets, stacked and encapsulated within tubes called fuel rods or fuel pins which are then bundled together in various geometric arrangements. There are many design considerations for the material composition and geometric configuration of the various components comprising a nuclear fuel system. Future designs for the fuel and the assembly or packaging of fuel will contribute to cleaner, cheaper and safer nuclear energy. Today's process for developing and testing new fuel systems is resource and time intensive. The process to manufacture the fuel, build an assembly,

459

NPT Compliance | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Compliance | National Nuclear Security Administration Compliance | 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 NPT Compliance Home > Our Mission > Managing the Stockpile > NPT Compliance NPT Compliance Maintaining the safety, security and effectiveness of the nuclear deterrent without nuclear testing - especially at lower numbers - requires

460

Resumption of Transient Testing | Department of Energy  

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

Initiatives » Nuclear Facility Operations » Resumption of Initiatives » Nuclear Facility Operations » Resumption of Transient Testing Resumption of Transient Testing April 15, 2013 - 11:11am Addthis Resumption of Transient Testing Capability The Department of Energy (DOE) is proposing to re-establish the capability to conduct transient testing of nuclear fuels. Transient testing involves placing fuel or material into the core of a nuclear reactor and subjecting it to short bursts of intense, high-power radiation. After the experiment is completed, the fuel or material is analyzed to determine the effects of the radiation. The resulting information is then used to guide the development and improvement of advanced nuclear fuel designs, and to validate computer models of fuel and core behavior required for U.S. Nuclear Regulatory Commission (NRC) evaluation of nuclear power reactor

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461

Resumption of Transient Testing | Department of Energy  

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

Initiatives » Nuclear Facility Operations » Resumption of Initiatives » Nuclear Facility Operations » Resumption of Transient Testing Resumption of Transient Testing April 15, 2013 - 11:11am Addthis Resumption of Transient Testing Capability The Department of Energy (DOE) is proposing to re-establish the capability to conduct transient testing of nuclear fuels. Transient testing involves placing fuel or material into the core of a nuclear reactor and subjecting it to short bursts of intense, high-power radiation. After the experiment is completed, the fuel or material is analyzed to determine the effects of the radiation. The resulting information is then used to guide the development and improvement of advanced nuclear fuel designs, and to validate computer models of fuel and core behavior required for U.S. Nuclear Regulatory Commission (NRC) evaluation of nuclear power reactor

462

Nuclear radiation electronic gear  

Science Journals Connector (OSTI)

Nuclear radiation electronic gear ... Examines the line of nuclear radiation instrumentation offered by Nuclear-Chicago Corporation and Victoreen Instrument Company. ... Nuclear / Radiochemistry ...

S. Z. Lewin

1961-01-01T23:59:59.000Z

463

Nuclear Weapons Journal  

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

Nuclear Weapons Journal Nuclear Weapons Journal x The Nuclear Weapons Journal ceased publication after Issue 2, 2009. Below are Nuclear Weapons Journal archived issues. Issue 2,...

464

Nuclear Forces and Nuclear Systems  

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

Forces and Nuclear Systems Forces and Nuclear Systems Our goal is to achieve a description of nuclear systems ranging in size from the deuteron to nuclear matter and neutron stars using a single parameterization of the nuclear forces. Our work includes both the construction of two- and three-nucleon potentials and the development of many-body techniques for computing nuclear properties with these interactions. Detailed quantitative, computationally intense studies are essential parts of this work. In the last decade we have constructed several realistic two- and three-nucleon potential models. The NN potential, Argonne v18, has a dominant charge-independent piece plus additional charge-dependent and charge-symmetry-breaking terms, including a complete electromagnetic interaction. It fits 4301 pp and np elastic scattering data with a chi**2

465

Evaluation of critical pathways, radionuclides, and remedial measures for reducing the radiological dose to returning populations at a former nuclear test site  

SciTech Connect

Bikini Island, the major residence island at Bikini Atoll, was contaminated with radioactive fallout as a result of the BRAVO test conducted on March 1, 1954. We have identified the critical radionuclides and supplied radiological data needed to develop dose estimates for all possible exposure pathways. These estimates show that the major dose to returning populations would result from ingestion of cesium-137 (137 Cs) in locally grown terrestrial foods where the predicted population average effective dose exceeds current federal guidelines. Consequently, we designed several long-term field experiments to develop and evaluate methods to reduce the 137 Cs content in locally grown foods.This paper gives a general outline of the remediation experiments with a more detailed description of a preferred combined option. Our comparative evaluation on various remedial methods show that the combined option--potassium treatment of the entire islands with limited excavation of soil in village an d housing areas--will be effective in reducing the dose to about 10% of pretreatment levels, and offers very significant benefits with respect to adverse environmental impacts as well as savings in overall costs, time, and required expert resources.

Robison, W. L., LLNL

1997-11-01T23:59:59.000Z

466

Preparing for the Unexpected  

E-Print Network (OSTI)

information on family disaster plans, see the Get Prepared section at www.ready.gov/index.html. #24; Deciding to stay or go You may be faced with the decision to evacuate or shelter-in-place. Evacuation means moving from an unsafe place to a safe place in a... information on family disaster plans, see the Get Prepared section at www.ready.gov/index.html. #24; Deciding to stay or go You may be faced with the decision to evacuate or shelter-in-place. Evacuation means moving from an unsafe place to a safe place in a...

Harris, Janie; Norman, Lisa; Lesikar, Bruce J.; Smith, David

2007-03-26T23:59:59.000Z

467

Nuclear Systems Modeling, Simulation & Validation | Nuclear Science...  

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

Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation...

468

Nuclear Materials Management & Safeguards System | National Nuclear...  

National Nuclear Security Administration (NNSA)

System Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards...

469

Nuclear options  

Science Journals Connector (OSTI)

... sad if transient commercial expediency led the country to take risks now by adopting nuclear reactor designs from abroad which are in some respects technically less sound than those produced at ... much lower priority. It can be anticipated, however; that although the types of nuclear reactor selected as the best that Britain could build next may be suitable for unit designs ...

G. R. Bainbridge

1974-06-21T23:59:59.000Z

470

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than  

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

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of "TRU" Success: SRS Recovery 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 Meters of Nuclear Waste to WIPP With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues to safely treat and dispose of radioactive waste created while producing materials for nuclear weapons throughout the Cold War. The DOE site in Aiken, S.C., is safely, steadily, and cost-effectively making progress to analyze, measure, and then carefully cleanup or dispose of legacy transuranic (TRU) waste remaining at SRS after the lengthy nuclear arms race. "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than

471

EIS-0250: Notice of Intent to Prepare a Supplement to the Final...  

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

Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada Notice of Intent to prepare a Supplement to the Final...

472

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than  

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

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of "TRU" Success: SRS Recovery 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 Meters of Nuclear Waste to WIPP With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues to safely treat and dispose of radioactive waste created while producing materials for nuclear weapons throughout the Cold War. The DOE site in Aiken, S.C., is safely, steadily, and cost-effectively making progress to analyze, measure, and then carefully cleanup or dispose of legacy transuranic (TRU) waste remaining at SRS after the lengthy nuclear arms race. "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than

473

Secretary Directs FPO to Prepare Strategic Plan  

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

January 2004 Volume 1, Number 2 January 2004 Volume 1, Number 2 In This Issue * Executive Order Update * $1 Million for Manhattan Project Preservation * 2004 DOE Cultural Resources Forum * ES&H Cultural Resources Update * FPO Site Visits * Oak Ridge Historic Preservation Update * Featured Site: Pantex * Save America's Treasures * Manhattan Project Interactive Website * Goucher College: HP Education Opportunity * Atomic Testing Museum Moves Forward Secretary Directs FPO to Prepare Strategic Plan On December 2, 2003, Secretary of Energy Spencer Abraham directed DOE's Federal Preservation Officer, Chief Historian F. G. Gosling, to prepare a strategic plan for the Department's history and historic preservation/cultural resource management programs. The Secretary (right) gave Gosling 90