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Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Unclassified Controlled Nuclear Information  

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

To prevent unauthorized dissemination of Unclassified Controlled Nuclear Information (UCNI). Cancels DOE 5635.4 and DOE 5650.3A

1995-09-25T23:59:59.000Z

2

Protection of Unclassified Controlled Nuclear Information  

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

To establish Department of Energy (DOE) policy and procedures for the protection of Unclassified Controlled Nuclear Information (UNCI). Canceled by DOE O 471.1 of 9-25-1995.

1992-04-24T23:59:59.000Z

3

Protection of Unclassified Controlled Nuclear Information  

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

To establish Department of Energy (DOE) policy and procedures for the protection of Unclassified Controlled Nuclear Information (UCNI). This directive does not cancel another directive. Chg 1 dated 4-24-92.

1988-02-03T23:59:59.000Z

4

Identification of Unclassified Controlled Nuclear Information  

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

To establish policy and procedures for identifying Unclassified Controlled Nuclear Information (UNCI) and for reviewing and marking documents and material containing UNCI. Cancels DOE O 5650.3. Canceled by DOE O 471.1 of 9-25-95.

1992-06-08T23:59:59.000Z

5

Identification and Protection of Unclassified Controlled Nuclear Information Manual  

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

This Manual provides detailed requirements to supplement DOE O 471.1A, Identification and Protection of Unclassified Controlled Nuclear Information. Change 1, dated 10/23/01, was added to the Manual to clarify when and how encryption requirements for Unclassified Controlled Nuclear Information may be waived. Canceled by DOE O 471.1B.

2000-06-30T23:59:59.000Z

6

Identification and Protection of Unclassified Controlled Nuclear Information  

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

The Order provides requirements and responsibilities for identifying and protecting the unauthorized dissemination of Unclassified Controlled Nuclear Information. Cancels DOE O 471.1A and DOE M 471.1-1.

2010-03-01T23:59:59.000Z

7

Identification and Protection of Unclassified Controlled Nuclear Information  

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

The Order provides requirements and responsibilities for identifying and protecting the unauthorized dissemination of Unclassified Controlled Nuclear Information. Extended until 7-7-06 by DOE N 251.64, dated 7-7-05. Cancels DOE O 471.1. Canceled by DOE O 471.1B dated 3-1-10.

2000-06-30T23:59:59.000Z

8

UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards...  

National Nuclear Security Administration (NNSA)

UNCLASSIFIED Nuclear Materials Management & Safeguards System CONTACT INFORMATION UPDATE REPORTING IDENTIFICATION SYMBOL (RIS) RIS: Address: Facility Name: CONTACTS Name Email:...

9

Unclassified Controlled Nuclear Information (UCNI) | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIAUltrafastaminoindazole,sediments. |

10

HQFMSP Chapter 13, Controlled Unclassified Information  

Broader source: Energy.gov [DOE]

2014 Headquarters Facilities Master Security Plan - Chapter 13, Controlled Unclassified Information Describes DOE Headquarters procedures for protecting Controlled Unclassified Information (CUI).

11

Controlled Unclassified Information  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTieCelebrate EarthEnergy Contractor&3-1 Chapter 13 Controlled

12

UNCLASSIFIED  

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

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13

UNCLASSIFIED  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof EnergyLeaseEnergyUNCLASSIFIED 2 1 2 : 0 - -, i m

14

UNCLASSIFIED  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof EnergyLeaseEnergyUNCLASSIFIED 2 1 2 : 0 - -, i m.

15

Chapter_13_Controlled_Unclassified_Information_10_28_2014  

Office of Environmental Management (EM)

3 Controlled Unclassified Information This chapter describes the security procedures adopted by DOE HQ to implement the requirements of the following DOE regulations and...

16

UNCLASSIFIED UNCLASSIFIED  

E-Print Network [OSTI]

G. Jones, and Andrew Huizinga Space and Naval Warfare Systems Center San Diego, CA William S, STEVENSON, McDONALD, GRANGER, SULLIVAN, JONES, HUIZINGA ET AL. UNCLASSIFIED 672 further processing of field

Frandsen, Jannette B.

17

UNCLASSIFIED UNCLASSIFIED  

E-Print Network [OSTI]

separation, wave momentum input · Sea spray influence · Waves · Stress vector vs wind vector (2-D wave number: Sc = v/Di · v is the molecular viscosity, Di is the diffusion coefficient #12;UNCLASSIFIED

Chu, Peter C.

18

Security Controls for Unclassified Information Systems Manual  

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

The Manual establishes minimum implementation standards for cyber security technical, management, and operational controls that will be followed in all information systems operated by DOE and the information systems. Does not cancel other directives. Canceled by DOE O 205.1B

2009-01-05T23:59:59.000Z

19

Security Controls for Unclassified Information Systems Manual  

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

The Manual establishes minimum implementation standards for cyber security technical, management, and operational controls that will be followed in all information systems operated by DOE and the information systems. Admin Chg 1 dated 9-1-09. Canceled by DOE O 205.1B.

2009-01-05T23:59:59.000Z

20

Security Controls for Unclassified Information Systems Manual  

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

The Manual establishes minimum implementation standards for cyber security technical, management, and operational controls that will be followed in all information systems operated by DOE and the information systems. Admin Chg 1 dated 9-1-09; Admin Chg 2 dated 12-22-09. Canceled by DOE O 205.1B.

2009-01-05T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Unclassified Controlled Nuclear Information General Guideline | Department  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy Usage »of EnergyTheTwo New EnergyofDEVELOPMENTEnergy LowUmatilla Tribes toof

22

MOX Services Unclassified Information System PIA, National Nuclear...  

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

System PIA, National Nuclear Services Administration More Documents & Publications TRAIN-PIA.pdf Occupational Medicine - Assistant PIA, Idaho National Laboratory Manchester...

23

A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats  

SciTech Connect (OSTI)

This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

Nelson, K; Sokkappa, P

2008-10-29T23:59:59.000Z

24

Identification and Protection of Unclassified Controlled Nuclear Information Manual  

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

The Manual provides detailed requirements to supplement the Order. Extended by DOE N 251.58, dated 07/06/2004, until 06/30/2005. Canceled by: DOE O 471.B. Does not cancel other directives.

2000-06-30T23:59:59.000Z

25

Unclassified Controlled Nuclear Information Training | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists' Research Petroleum ReserveDepartment of EnergyDepartmentSankar SambasivanTraining

26

Unclassified Distribution  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIAUltrafastaminoindazole,sediments. |63 1

27

Controlled Unclassified Information  

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

meeting this requirement are available in the self-service supply stores. Bulk paper, plastic, and metal waste (not including hard drives - see note below) containing CUI must be...

28

nuclear controls  

National Nuclear Security Administration (NNSA)

the Office of Nonproliferation and International Security (NIS) is to prevent the proliferation of nuclear weapons, materials, technology, and expertise. NIS applies technical...

29

Unclassified Foreign Visits and Assignments  

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

International cooperation and collaboration is an important element in the effective planning and implementation of many Department of Energy (DOE) programs. DOE and its international partners benefit from the exchange of information that results from a managed process of unclassified visits and assignments by foreign nationals. These visits and assignments must be conducted in a manner consistent with U.S. and DOE national security policies, requirements, and objectives including export control laws and regulations. Canceled by DOE O 142.3. Does not cancel other directives.

1999-07-14T23:59:59.000Z

30

Unclassified Foreign Visits and Assignments  

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

To define a program for unclassified foreign national access to Department of Energy sites, information, and technologies. This Order cancels DOE P 142.1, Unclassified Foreign Visits and Assignments, dated 7-14-99; DOE N 142.1, Unclassified Foreign Visits and Assignments, dated 7-14-99; Secretarial Memorandum Unclassified Foreign Visits and Assignments, dated 7-14-99; Memorandum from Francis S. Blake, Departmental Use of Foreign Access Central Tracking System, dated 11-05-01; Memorandum from Kyle E. McSlarrow, Interim Guidance for Implementation of the Department's Unclassified Foreign Visits and Assignments Program, dated 12-17-02; and Secretarial Memorandum, Policy Exclusion for Unclassified Foreign National's Access to Department of Energy Facilities in Urgent or Emergency Medical Situations, dated 4-10-01. Cancels: DOE P 142.1 and DOE N 142.1

2004-06-18T23:59:59.000Z

31

Unclassified Foreign Visits and Assignments  

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

To provide interim Department of Energy (DOE) requirements and responsibilities for unclassified visits and assignment by foreign nationals to DOE facilities for unclassified activities. This Notice supplements DOE P 142.1 dated 7-14-99, which sets overall Departmental policy on unclassified foreign visits and assignments. It is a complement to existing counterintelligence and security orders and policies. DOE N 251.53, dated 05/14/03, extends this directive until canceled. Cancels: DOE 1240.2B

1999-07-14T23:59:59.000Z

32

NUCLEAR PLANT AND CONTROL  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: software require- ments, safety analysis, formal for the digital protection systems of a nuclear power plant. When spec- ifying requirements for software and CRSA processes are described using shutdown system 2 of the Wolsong nuclear power plants as the digital

33

PIA - WEB Unclassified Business Operations General Support System...  

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

Unclassified Business Operations General Support System PIA - WEB Unclassified Business Operations General Support System PIA - WEB Unclassified Business Operations General Support...

34

Nuclear reactor control apparatus  

SciTech Connect (OSTI)

Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additonal magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

Sridhar, B.N.

1981-08-28T23:59:59.000Z

35

Nuclear reactor control apparatus  

DOE Patents [OSTI]

Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additional magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

Sridhar, Bettadapur N. (Cupertino, CA)

1983-11-01T23:59:59.000Z

36

UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards System  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Reviewwill help prepareA Review Scientific

37

Nuclear reactor control  

SciTech Connect (OSTI)

A liquid metal cooled fast breeder nuclear reactor has power setback means for use in an emergency. On initiation of a trip-signal a control rod is injected into the core in two stages, firstly, by free fall to effect an immediate power-set back to a safe level and, secondly, by controlled insertion. Total shut-down of the reactor under all emergencies is avoided. 4 claims.

Ingham, R.V.

1980-01-01T23:59:59.000Z

38

Nuclear reactor control  

DOE Patents [OSTI]

1. In a nuclear reactor incorporating a plurality of columns of tubular fuel elements disposed in horizontal tubes in a mass of graphite wherein water flows through the tubes to cool the fuel elements, the improvement comprising at least one control column disposed in a horizontal tube including fewer fuel elements than in a normal column of fuel elements and tubular control elements disposed at both ends of said control column, and means for varying the horizontal displacement of the control column comprising a winch at the upstream end of the control column and a cable extending through the fuel and control elements and attached to the element at the downstream end of the column.

Cawley, William E. (Phoenix, AZ); Warnick, Robert F. (Pasco, WA)

1982-01-01T23:59:59.000Z

39

Nuclear reactor control  

SciTech Connect (OSTI)

In a nuclear reactor incorporating a plurality of columns of tubular fuel elements disposed in horizontal tubes in a mass of graphite wherein water flows through the tubes to cool the fuel elements, the improvement comprising at least one control column disposed in a horizontal tube including fewer fuel elements than in a normal column of fuel elements and tubular control elements disposed at both ends of said control column, and means for varying the horizontal displacement of the control column comprising a winch at the upstream end of the control column and a cable extending through the fuel and control elements and attached to the element at the downstream end of the column.

Cawley, W.E.; Warnick, R.F.

1982-03-30T23:59:59.000Z

40

Nuclear reactor control column  

DOE Patents [OSTI]

The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

Bachovchin, Dennis M. (Plum Borough, PA)

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Nuclear reactor control column  

SciTech Connect (OSTI)

The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest crosssectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

Bachovchin, D.M.

1982-08-10T23:59:59.000Z

42

Evaluation Report on "The Department's Unclassified Cyber Security Program"  

SciTech Connect (OSTI)

Industry experts report that security challenges and threats are continually evolving as malicious activity has become more web-based and attackers are able to rapidly adapt their attack methods. In addition, the number of data breaches continues to rise. In an effort to mitigate and address threats and protect valuable information, the Department of Energy anticipated spending about $275 million in Fiscal Year (FY) 2009 to implement cyber security measures necessary to protect its information technology resources. These systems and data are designed to support the Department's mission and business lines of energy security, nuclear security, scientific discovery and innovation, and environmental responsibility. The Federal Information Security Management Act of 2002 (FISMA) provides direction to agencies on the management and oversight of information security risks, including design and implementation of controls to protect Federal information and systems. As required by FISMA, the Office of Inspector General conducts an annual independent evaluation to determine whether the Department's unclassified cyber security program adequately protects its information systems and data. This memorandum and the attached report present the results of our evaluation for FY 2009. The Department continued to make incremental improvements in its unclassified cyber security program. Our evaluation disclosed that most sites had taken action to address weaknesses previously identified in our FY 2008 evaluation report. They improved certification and accreditation of systems; strengthened configuration management of networks and systems; performed independent assessments; and, developed and/or refined certain policies and procedures. In addition, the Department instituted a centralized incident response organization designed to eliminate duplicative efforts throughout the Department. As we have noted in previous reports, the Department continued to maintain strong network perimeter defenses against malicious intruders and other externals threats. These are positive accomplishments. However, in our judgment, additional action is required to further enhance the Department's unclassified cyber security program and help reduce risks to its systems and data. For example, our current review identified opportunities for improvements in areas such as security planning and testing, systems inventory, access controls, and configuration management. In particular, we issued a number of findings at sites managed by the National Nuclear Security Administration (NNSA). We also identified weaknesses across various Department program elements. Issues that warrant further attention include: (1) Weaknesses such as outdated security plans and not completing annual security control self-assessments were identified at several sites; (2) The Department had not yet resolved systems inventory issues and had yet to deploy a complex-wide automated asset management tool to help track information technology resources and identify interfaces between systems or networks; (3) Although certain improvements had been made to enhance access controls, we noted deficiencies such as a lack of periodic account reviews and inadequate password management at a number of sites; and (4) Previously identified weaknesses in configuration management had been corrected, however, we found problems related to weak administrator account settings and failure to install software patches, as well as incomplete implementation of the Federal Desktop Core Configuration. These internal control weaknesses existed, at least in part, because certain cyber security roles and responsibilities were not clearly delineated. Program officials also had not effectively performed monitoring and review activities essential for evaluating the adequacy of cyber security performance. In some cases, officials had not ensured that weaknesses discovered during audits and other evaluations were recorded and tracked to resolution in the organizations' Plans of Action and Milestones. Our testing disclosed that about 39 p

None

2009-10-01T23:59:59.000Z

43

Security and Use Control of Nuclear Explosives and Nuclear Weapons...  

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

4C, Security and Use Control of Nuclear Explosives and Nuclear Weapons by LtCol Karl Basham Functional areas: Nuclear Explosives, Nuclear Weapons, Security The Order establishes...

44

Nuclear reactor control assembly  

SciTech Connect (OSTI)

This patent describes an assembly for providing global power control in a nuclear reactor having the core split into two halves. It comprises a disk assembly formed from at least two disks each machined with an identical surface hole pattern such that rotation of one disk relative to the other causes the hole pattern to open or close, the disk assembly being positioned substantially at the longitudinal center of and coaxial with the core halves; and means for rotating at least one of the disks relative to the other.

Negron, S.B.

1991-06-11T23:59:59.000Z

45

UNCLASSIFIED  

National Nuclear Security Administration (NNSA)

were derived from the WNA's Reactor Database, which is linked to the International Atomic Energy Agency's Power Reactor Information System. The coefficients were then applied to...

46

UNCLASSIFIED  

Office of Scientific and Technical Information (OSTI)

on the weights of the pellets before and after each run. The pellets did not tend to fracture very much, but instead they wore down gradually and the lost material was not...

47

UNCLASSIFIED  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICE OF CIVIL toRockyDECEMBER 1 Department of

48

Nuclear reactor control rod  

SciTech Connect (OSTI)

This patent describes a vertically oriented bottom entry control rod from a nuclear reactor: a frame including an elongated central spine of cruciform cross section connected between an upper support member and a lower support member both of cruciform shape having four laterally extending arms. The arms are in alignment with the arms of the lower support member and each aligned upper and lower support members has a sheath extending between; absorber plates of neutron absorber material, different from the material of the frame, one of the absorber plates is positioned within a sheath beneath each of the arms; attachment means suspends the absorber plates from the arms of the upper support member within a sheath; elongated absorber members positioned within a sheath between each of the suspended absorber plates and an arm of the lower support member; and joint means between the upper ends of the absorber members and the lower ends of the suspended absorber plates for minimizing gaps; the sheath means encloses the suspended absorber plates and the absorber members extending between aligned arms of the upper and lower support members and secured.

Cearley, J.E.; Izzo, K.R.

1987-06-30T23:59:59.000Z

49

Unclassified Foreign Visits and Assignments Program  

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

The order defines a program for unclassified foreign national access to Department of Energy sites, information, and technologies. The page change streamlines the HQs Management Panel review process to include reviews by HSS, IN, and a representative of the cognizant under secretary for access requests involving foreign nationals. Cancels Secretarial Memorandum, Unclassified Foreign Visits and Assignments, dated 7-14-99; Memorandum from Francis S. Blake, Departmental Use of Foreign Access Central Tracking System, dated 11-05-01; Memorandum from Kyle E. McSlarrow, Interim Guidance for Implementation of the Department's Unclassified Foreign Visits and Assignments Program, dated 12-17-02; and Secretarial Memorandum, Policy Exclusion for Unclassified Foreign National's Access to Department of Energy Facilities in Urgent or Emergency Medical Situations, dated 4-10-01. Cancels: DOE P 142.1 and DOE N 142.1

2004-06-18T23:59:59.000Z

50

Nuclear Material Control and Accountability  

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

This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6. Admin Chg 1, 8-3-11.

2011-06-27T23:59:59.000Z

51

Nuclear Material Control and Accountability  

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

The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Cancels: DOE M 474.1-1B DOE M 474.1-2A

2005-08-26T23:59:59.000Z

52

Nuclear Material Control and Accountability  

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

The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Chg 1, dated 8-14-06. Canceled by DOE O 474.2.

2005-08-26T23:59:59.000Z

53

Nuclear Controls | National Nuclear Security Administration  

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

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54

UNCLASSIFIED Nuclear Materials Management & Safeguards System  

National Nuclear Security Administration (NNSA)

UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number: Project Title: Associated Materials: Programmatic RIS Previous...

55

UNCLASSIFIED Nuclear Materials Management & Safeguards System  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Reviewwill help prepareA Review Scientific Assessment

56

Nuclear Material Control and Accountability  

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

This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6, Admin Chg 1, 8-26-05. Admin Chg 2, dated 11-19-12, cancels DOE M 474.2 Admin Chg 1.

2011-06-27T23:59:59.000Z

57

Nuclear reactor control apparatus  

DOE Patents [OSTI]

Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.

Sridhar, Bettadapur N. (Cupertino, CA)

1983-10-25T23:59:59.000Z

58

Nuclear reactor control room construction  

DOE Patents [OSTI]

A control room 10 for a nuclear plant is disclosed. In the control room, objects 12, 20, 22, 26, 30 are no less than four inches from walls 10.2. A ceiling 32 contains cooling fins 35 that extend downwards toward the floor from metal plates 34. A concrete slab 33 is poured over the plates. Studs 36 are welded to the plates and are encased in the concrete.

Lamuro, Robert C. (Pittsburgh, PA); Orr, Richard (Pittsburgh, PA)

1993-01-01T23:59:59.000Z

59

Nuclear reactor control room construction  

DOE Patents [OSTI]

A control room for a nuclear plant is disclosed. In the control room, objects labelled 12, 20, 22, 26, 30 in the drawing are no less than four inches from walls labelled 10.2. A ceiling contains cooling fins that extend downwards toward the floor from metal plates. A concrete slab is poured over the plates. Studs are welded to the plates and are encased in the concrete. 6 figures.

Lamuro, R.C.; Orr, R.

1993-11-16T23:59:59.000Z

60

Control of Nuclear Weapon Data  

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

The directive establishes the policy, process and procedures for control of nuclear weapon data to ensure that dissemination of the information is restricted to individuals with appropriate clearances, approved authorization and valid need-to-know in keeping with the Atomic Energy Act (as amended) stipulation of ensuring common defense and security. Cancels DOE O 5610.2.

2011-07-21T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Advanced nuclear plant control complex  

DOE Patents [OSTI]

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

62

Climate Control Using Nuclear Energy  

E-Print Network [OSTI]

We examine implications of anthropogenic low pressure regions, - created by injecting heat from nuclear reactors, into atmosphere. We suggest the possibility that such artificially generated low pressure regions, near hurricanes could disrupt their growth, path, and intensity. This method can also create controlled tropical stroms, which lead to substantial rainfall in arid areas, such as - (1)Sahara desert, (2) Australian interior desert, and (3) Indian Thar desert. A simple vortex suction model is developed to study, effect on atmospheric dynamics, by such a nuclear heat injection system.

Moninder Singh Modgil

2008-01-01T23:59:59.000Z

63

Large Scale Weather Control Using Nuclear Reactors  

E-Print Network [OSTI]

It is pointed out that controlled release of thermal energy from fission type nuclear reactors can be used to alter weather patterns over significantly large geographical regions. (1) Nuclear heat creates a low pressure region, which can be used to draw moist air from oceans, onto deserts. (2) Creation of low pressure zones over oceans using Nuclear heat can lead to Controlled Cyclone Creation (CCC).(3) Nuclear heat can also be used to melt glaciers and control water flow in rivers.

Moninder Singh Modgil

2002-10-02T23:59:59.000Z

64

Large Scale Weather Control Using Nuclear Reactors  

E-Print Network [OSTI]

It is pointed out that controlled release of thermal energy from fission type nuclear reactors can be used to alter weather patterns over significantly large geographical regions. (1) Nuclear heat creates a low pressure region, which can be used to draw moist air from oceans, onto deserts. (2) Creation of low pressure zones over oceans using Nuclear heat can lead to Controlled Cyclone Creation (CCC).(3) Nuclear heat can also be used to melt glaciers and control water flow in rivers.

Singh-Modgil, M

2002-01-01T23:59:59.000Z

65

UNCLASSIFIED UNCLASSIFIED  

E-Print Network [OSTI]

Multiplier 3rd world countries Non-government factions Terrorists Widely Available Over 50 Countries

Chu, Peter C.

66

Control and Accountability of Nuclear Materials  

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

DOE O 474.1 prescribes Department of Energy (DOE) requirements for nuclear material control and accountability (MC&A) for DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission (NRC). Cancels DOE 5633.3B

1999-08-11T23:59:59.000Z

67

Control and Accountability of Nuclear Materials  

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

The order prescribes DOE minimum requirements and procedures for control and accountability of nuclear materials at DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission {NRC). Cancels DOE O 5633.3. Canceled by DOE O 5633.3B.

1993-02-12T23:59:59.000Z

68

Reactivity control assembly for nuclear reactor  

DOE Patents [OSTI]

Reactivity control assembly for nuclear reactor comprises supports stacked above reactor core for holding control rods. Couplers associated with the supports and a vertically movable drive shaft have lugs at their lower ends for engagement with the supports.

Bollinger, Lawrence R. (Schenectady, NY)

1984-01-01T23:59:59.000Z

69

Perspective unconventional means for nuclear reactor control  

SciTech Connect (OSTI)

The concept of reliable shutdown of nuclear reactors demands application of engineering control means on the basis of principles, safety, safe failure, redundancy, independence, variety, defence in depth, and intrinsical safety. This report describes application of control methods.

Ionaitis, R.R.

1993-12-31T23:59:59.000Z

70

The nuclear materials control technology briefing book  

SciTech Connect (OSTI)

As national and international interests in nuclear arms control and non-proliferation of nuclear weapons, intensify, it becomes ever more important that contributors be aware of the technologies available for the measurement and control of the nuclear materials important to nuclear weapons development. This briefing book presents concise, nontechnical summaries of various special nuclear material (SNM) and tritium production monitoring technologies applicable to the control of nuclear materials and their production. Since the International Atomic Energy Agency (IAEA) operates a multinational, on-site-inspector-based safeguards program in support of the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), many (but not all) of the technologies reported in this document are in routine use or under development for IAEA safeguards.

Hartwell, J.K.; Fernandez, S.J.

1992-03-01T23:59:59.000Z

71

Control and Accountability of Nuclear Materials  

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

To prescribe Department of Energy (DOE) requirements, including those for the National Nuclear Security Administration (NNSA), for nuclear material control and accountability (MC&A) for DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission (NRC). DOE N 251.60, dated 11-19-04, extends this directive until 11-19-05. Cancels DOE O 474.1.

2000-11-20T23:59:59.000Z

72

Security and Use Control of Nuclear Explosives and Nuclear Weapons  

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

This Order establishes requirements to implement the nuclear explosive security and use control elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety (NEWS) Program, to ensure authorized use, when directed by proper authority, and protect against deliberate unauthorized acts/deliberate unauthorized use. Cancels DOE O 452.4A.

2010-01-22T23:59:59.000Z

73

Security and Use Control of Nuclear Explosives and Nuclear Weapons  

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

The Order establishes requirements to implement the nuclear explosive security and use control (UC) elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety (NEWS) Program, to ensure authorized use, when directed by proper authority, and protect against deliberate unauthorized acts (DUAs), deliberate unauthorized use (DUU), and denial of authorized use (DAU).

2014-11-19T23:59:59.000Z

74

Control and Accountability of Nuclear Materials  

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

To prescribe the Department of Energy (DOE) minimum requirements and procedures for control and accountability of nuclear materials at DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE O 5633.2A and DOE O 5633.3A. Canceled by DOE O 474.1

1994-09-07T23:59:59.000Z

75

Neutron absorbing coating for nuclear criticality control  

DOE Patents [OSTI]

A neutron absorbing coating for use on a substrate, and which provides nuclear criticality control is described and which includes a nickel, chromium, molybdenum, and gadolinium alloy having less than about 5% boron, by weight.

Mizia, Ronald E. (Idaho Falls, ID); Wright, Richard N. (Idaho Falls, ID); Swank, William D. (Idaho Falls, ID); Lister, Tedd E. (Idaho Falls, ID); Pinhero, Patrick J. (Idaho Falls, ID)

2007-10-23T23:59:59.000Z

76

Enforcement Letter, Consolidated Nuclear Security, LLC | Department...  

Energy Savers [EERE]

security incidents involving the unclassified waste stream and discrepancies in the inventory of accountable nuclear material at DOE's Y-12 National Security Complex in Oak...

77

Fast-acting nuclear reactor control device  

DOE Patents [OSTI]

A fast-acting nuclear reactor control device for moving and positioning a fety control rod to desired positions within the core of the reactor between a run position in which the safety control rod is outside the reactor core, and a shutdown position in which the rod is fully inserted in the reactor core. The device employs a hydraulic pump/motor, an electric gear motor, and solenoid valve to drive the safety control rod into the reactor core through the entire stroke of the safety control rod. An overrunning clutch allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.

Kotlyar, Oleg M. (Idaho Falls, ID); West, Phillip B. (Idaho Falls, ID)

1993-01-01T23:59:59.000Z

78

Nuclear export and technology transfer controls  

SciTech Connect (OSTI)

A review of the U.S. implementation of nuclear export and technology transfer controls is undertaken to assess whether the U.S. controls is undertaken to assess whether the U.S. controls meet the full scope of the international commitment toward non-proliferation controls. The international non-proliferation controls have been incorporated into CoCom, the Coordinating Committee of the multinational organization established to protect the mutual interests of the participating countries in the area of strategic export controls. However, this CoCom list is classified and each participating country implements these controls pursuant to its own laws. A comparison to the non-proliferation controls promulgated by the U.K. is used to verify that the U.S. controls are at least as comprehensive as the British controls.

Hower, J.J.; Primeau, S.J. (Eagle Research Group, Inc., Arlington, VA (US))

1988-01-01T23:59:59.000Z

79

UNCLASSIFIED FOREIGN VISITS AND ASSIGNMENTS PROGRAM U.S. DEPARTMENT OF ENERGY  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof EnergyLeaseEnergyUNCLASSIFIED 2 1 2 : 0 - -, i

80

Nuclear reactor control apparatus. [FBR  

SciTech Connect (OSTI)

Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.

Sridhar, B.N.

1981-04-16T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Fast-acting nuclear reactor control device  

SciTech Connect (OSTI)

A fast-acting nuclear reactor control device is described for controlling a safety control rod within the core of a nuclear reactor, the reactor controlled by a reactor control system, the device comprising: a safety control rod drive shaft and an electromagnetic clutch co-axial with the drive shaft operatively connected to the safety control rod for driving and positioning the safety control rod within or without the reactor core during reactor operation, the safety rod being oriented in a substantially vertical position to allow the rod to fall into the reactor core under the influence of gravity during shutdown of the reactor; the safety control rod drive shaft further operatively connected to a hydraulic pump such that operation of the drive shaft simultaneously drives and positions the safety control rod and operates the hydraulic pump such that a hydraulic fluid is forced into an accumulator, filling the accumulator with oil for the storage and supply of primary potential energy for safety control rod insertion such that the release of potential energy in the accumulator causes hydraulic fluid to flow through the hydraulic pump, converting the hydraulic pump to a hydraulic motor having speed and power capable of full length insertion and high speed driving of the safety control rod into the reactor core; a solenoid valve interposed between the hydraulic pump and the accumulator, said solenoid valve being a normally open valve, actuated to close when the safety control rod is out of the reactor during reactor operation; and further wherein said solenoid opens in response to a signal from the reactor control system calling for shutdown of the reactor and rapid insertion of the safety control rod into the reactor core, such that the opening of the solenoid releases the potential energy in the accumulator to place the safety control rod in a safe shutdown position.

Kotlyar, O.M.; West, P.B.

1993-08-03T23:59:59.000Z

82

Reactivity control assembly for nuclear reactor. [LMFBR  

DOE Patents [OSTI]

This invention, which resulted from a contact with the United States Department of Energy, relates to a control mechanism for a nuclear reactor and, more particularly, to an assembly for selectively shifting different numbers of reactivity modifying rods into and out of the core of a nuclear reactor. It has been proposed heretofore to control the reactivity of a breeder reactor by varying the depth of insertion of control rods (e.g., rods containing a fertile material such as ThO/sub 2/) in the core of the reactor, thereby varying the amount of neutron-thermalizing coolant and the amount of neutron-capturing material in the core. This invention relates to a mechanism which can advantageously be used in this type of reactor control system.

Bollinger, L.R.

1982-03-17T23:59:59.000Z

83

Alarm system for a nuclear control complex  

DOE Patents [OSTI]

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1994-01-01T23:59:59.000Z

84

Advanced nuclear plant control room complex  

DOE Patents [OSTI]

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

85

Console for a nuclear control complex  

DOE Patents [OSTI]

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

86

Fast-acting nuclear reactor control device  

SciTech Connect (OSTI)

This invention consists of a fast-acting nuclear reactor control device for moving and positioning a safety control rod to desired elevations within the core of the reactor between a run position in which the safety control rod is outside the reactor core, and a shutdown position in which the rod is fully inserted in the reactor core. The device employs a hydraulic pump motor, an electric gear motor, and a solenoid valve to drive the safety control rod into the reactor core through the entire stroke of the safety control rod. An overrunning clutch, allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.

Kotlyar, O.M.; West, P.B.

1992-12-31T23:59:59.000Z

87

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

88

Reduction in Work Force Unclassified Staff Office of Human Resources  

E-Print Network [OSTI]

Reduction in Work Force Unclassified Staff 9.15 Office of Human Resources Applies to: Regular by the Health System. Health System employees should contact their human resource department for further information. The Ohio State University Office of Human Resources Page 1 of 1 Policy 9.15 Reduction in Work

Howat, Ian M.

89

MIT Department of Nuclear Engineering 1 Digital Instrumentation and Control  

E-Print Network [OSTI]

1 MIT Department of Nuclear Engineering 1 Digital Instrumentation and Control Issues in Nuclear Engineering 2 Nuclear Power Plant #12;2 MIT Department of Nuclear Engineering 3 Major Protection Functions Engineering 4 Background · Analog electro-mechanical systems in existing nuclear power plants are aging

Schweik, Charles M.

90

Manual for Control And Accountability of Nuclear Materials  

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

DOE M 474.1-1 prescribes Department of Energy (DOE) requirements and procedures for nuclear material control and accountability (MC&A). This Manual supplements DOE O 474.1, Control and Accountability of Nuclear Materials.

1999-08-11T23:59:59.000Z

91

Fuzzy controllers in nuclear material accounting  

SciTech Connect (OSTI)

Fuzzy controllers are applied to predicting and modeling a time series, with particular emphasis on anomaly detection in nuclear material inventory differences. As compared to neural networks, the fuzzy controllers can operate in real time; their learning process does not require many iterations to converge. For this reason fuzzy controllers are potentially useful in time series forecasting, where the authors want to detect and identify trends in real time. They describe an object-oriented implementation of the algorithm advanced by Wang and Mendel. Numerical results are presented both for inventory data and time series corresponding to chaotic situations, such as encountered in the context of strange attractors. In the latter case, the effects of noise on the predictive power of the fuzzy controller are explored.

Zardecki, A.

1994-10-01T23:59:59.000Z

92

Unclassified Foreign Visits and Assignments - DOE Directives,  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIAUltrafastaminoindazole,sediments. |63

93

MOX Services Unclassified Information System PIA, National Nuclear Services  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomen OwnedofDepartment ofJared Temanson -of EnergyEqualA new

94

Nuclear reactor shutdown control rod assembly  

DOE Patents [OSTI]

A temperature responsive, self-actuated nuclear reactor shutdown control rod assembly 10. The upper end 18 of a lower drive line 17 fits within the lower end of an upper drive line 12. The lower end (not shown) of the lower drive line 17 is connected to a neutron absorber. During normal temperature conditions the lower drive line 17 is supported by detent means 22,26. When an overtemperature condition occurs thermal actuation means 34 urges ring 26 upwardly sufficiently to allow balls 22 to move radially outwardly thereby allowing lower drive line 17 to move downwardly toward the core of the nuclear reactor resulting in automatic reduction of the reactor powder.

Bilibin, Konstantin (North Hollywood, CA)

1988-01-01T23:59:59.000Z

95

Security and Control of Nuclear Explosives and Nuclear Weapons  

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

This directive establishes requirements and responsibilities to prevent the deliberate unauthorized use of U.S. nuclear explosives and U.S. nuclear weapons. Cancels DOE O 452.4.

2001-12-17T23:59:59.000Z

96

Classified Matter Protection and Control  

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

Provides detailed requirements to supplement DOE O 471.2, which establishes policy for the protection and control of classified and unclassified information. Does not cancel other directives.

1995-09-26T23:59:59.000Z

97

Nuclear Power - Control, Reliability and Human Factors  

E-Print Network [OSTI]

Instrumentation and Control 49 H.M. Hashemian Chapter 4 Design Considerations for the Implementation of a Mobile IP Telephony System in a Nuclear Power Plant 67 J. Garc?a-Hern?ndez, J. C. Vel?zquez- Hern?ndez, C. F. Garc?a-Hern?ndez and M. A. Vallejo-Alarc?n... Reliability K s e n i i a Sapoz h n i k o v a and Roald Tayma n o v D.I.Mendeleyev Institute for Metrology, Russia 1. Introduction At present, a great number of embedded sens o r devi c es provi d e monito r i n g of operat i n g condi t io n...

98

Control and Accountability of Nuclear Materials: Responsibilities and Authorities  

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

The order prescribes the Department of Energy (DOE) policies, responsibilities, and authorities for control and accountability of nuclear materials. Cancels DOE O 5633.2.

1992-09-23T23:59:59.000Z

99

Louisiana Nuclear Energy and Radiation Control Law (Louisiana)  

Broader source: Energy.gov [DOE]

The Louisiana Department of Environmental Quality is responsible for the regulation of nuclear energy safety, permitting and radiation safety and control in Louisiana. The Department operates...

100

Excessing of Computers Used for Unclassified Controlled Information...  

Energy Savers [EERE]

Energy spends over 2 billioil each year on infonnation teclulology and has a current inventory of approxiinately 800 infomations ystems, including up to 11 5,000 personal...

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

10 CFR Part 1017 - Identification and Protection of Unclassified Controlled  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energyon ArmedWaste and Materials Disposition#EnergyFaceoff1 1 1 More Documents10 CFR

102

Excessing of Computers Used for Unclassified Controlled Information at the  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector General Office of Audit|Department of Energy56 EvaluationFriday, NovemberL-12-071]ExcessIdaho

103

Boron control system for a nuclear power plant  

SciTech Connect (OSTI)

Ion exchangers which reversibly store borate ions in a temperature dependent process are combined with evaporative boric acid recovery apparatus to provide a boron control system for controlling the reactivity of nuclear power plants. A plurality of ion exchangers are operated sequentially to provide varying amounts of boric acid to a nuclear reactor for load follow operations. Evaporative boric acid recovery apparatus is utilized for major changes in the boron concentration within the nuclear reactor.

Brown, W.W.; Van der Schoot, M.R.

1980-09-30T23:59:59.000Z

104

SECURITY AND CONTROL OF NUCLEAR EXPLOSIVES AND NUCLEAR WEAPONS  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards ,# , onLightThe

105

Manual for Control and Accountability of Nuclear Materials  

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

The manual prescribes requirements and assign responsibilities for nuclear material control and accountability. Cancels DOE M 474.1-1A. Canceled by DOE M 470.4-6.

2003-06-13T23:59:59.000Z

106

Manual for Control and Accountability of Nuclear Materials  

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

The manual prescribes requirements and procedures for nuclear material control and accountability (MC&A). Cancels DOE M 474.1-1. Canceled by DOE M 474.1-1B.

2000-11-22T23:59:59.000Z

107

Control and Accountability of Nuclear Materials Responsibilities and Authorities  

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

The order prescribe the Department of Energy (DOE) policies, responsibilities, and authorities for control and accountability of nuclear materials. Cancels DOE O 5630.1. Canceled by DOE O 5633.2A.

1988-01-29T23:59:59.000Z

108

A comparison of nuclear reactor control room display panels  

E-Print Network [OSTI]

complex and time consuming task. It is expected that the control room of future commercial nuclear reactor power plants will change considerably as a result of these studies. Currently there are literally hundreds of displays and controls... in the average commercial nuclear reactor power plant. This posed a significant problem when the NRC determined that a new set of displays was required in order to manage emergencies. It has been suggested that digital computers with graphics capabilities...

Bowers, Frances Renae

1988-01-01T23:59:59.000Z

109

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 57, NO. 2, APRIL 2010 807 Integrated Robust and Resilient Control of Nuclear  

E-Print Network [OSTI]

and Resilient Control of Nuclear Power Plants for Operational Safety and High Performance Xin Jin, Student & Secure (IRIS) simulator of nuclear power plants. Index Terms--Emergency operation, nuclear power plant Lyapunov equation. Reference Signals. Temperatures of the nuclear power plant. Sampling time. Controller

Ray, Asok

110

Fluorescence Imaging for Nuclear Arms Control Verification  

E-Print Network [OSTI]

grade Pu typically contains more than 90% 239Pu.10 Additionally, the fissile material must be in metallic form. There are many different nuclear warhead designs, but there are three general warhead types: gun-type, implosion and thermonuclear. In a... into a supercritical configuration. A thermonuclear device combines an implosion device, known as the primary, with a secondary fusion device composed of uranium and lithium deuteride. Most modern weapons contain a thermonuclear warhead. Gun...

Feener, Jessica S

2014-08-14T23:59:59.000Z

111

Nuclear reactivity control using laser induced polarization  

DOE Patents [OSTI]

A control element for reactivity control of a fission source provides an atomic density of .sup.3 He in a control volume which is effective to control criticality as the .sup.3 He is spin-polarized. Spin-polarization of the .sup.3 He affects the cross section of the control volume for fission neturons and hence, the reactivity. An irradiation source is directed within the .sup.3 He for spin-polarizing the .sup.3 He. An alkali-metal vapor may be included with the .sup.3 He where a laser spin-polarizes the alkali-metal atoms which in turn, spin-couple with .sup.3 He to spin-polarize the .sup.3 He atoms.

Bowman, Charles D. (Los Alamos, NM)

1990-01-01T23:59:59.000Z

112

Nuclear reactivity control using laser induced polarization  

DOE Patents [OSTI]

A control element for reactivity control of a fission source provides an atomic density of .sup.3 He in a control volume which is effective to control criticality as the .sup.3 He is spin-polarized. Spin-polarization of the .sup.3 He affects the cross section of the control volume for fission neutrons and hence, the reactivity. An irradiation source is directed within the .sup.3 He for spin-polarizing the .sup.3 He. An alkali-metal vapor may be included with the .sup.3 He where a laser spin-polarizes the alkali-metal atoms which in turn, spin-couple with .sup.3 He to spin-polarize the .sup.3 He atoms.

Bowman, Charles D. (Los Alamos, NM)

1991-01-01T23:59:59.000Z

113

Distributed expert systems for nuclear reactor control  

SciTech Connect (OSTI)

A network of distributed expert systems is the heart of a prototype supervisory control architecture developed at the Oak Ridge National Laboratory (ORNL) for an advanced multimodular reactor. Eight expert systems encode knowledge on signal acquisition, diagnostics, safeguards, and control strategies in a hybrid rule-based, multiprocessing and object-oriented distributed computing environment. An interactive simulation of a power block consisting of three reactors and one turbine provides a realistic, testbed for performance analysis of the integrated control system in real-time. Implementation details and representative reactor transients are discussed.

Otaduy, P.J.

1992-12-01T23:59:59.000Z

114

Distributed expert systems for nuclear reactor control  

SciTech Connect (OSTI)

A network of distributed expert systems is the heart of a prototype supervisory control architecture developed at the Oak Ridge National Laboratory (ORNL) for an advanced multimodular reactor. Eight expert systems encode knowledge on signal acquisition, diagnostics, safeguards, and control strategies in a hybrid rule-based, multiprocessing and object-oriented distributed computing environment. An interactive simulation of a power block consisting of three reactors and one turbine provides a realistic, testbed for performance analysis of the integrated control system in real-time. Implementation details and representative reactor transients are discussed.

Otaduy, P.J.

1992-01-01T23:59:59.000Z

115

Nuclear Arms Control R&D Consortium  

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

arms- control-technology experts LOS ALAMOS, N.M., April 7, 2014-A consortium led by the University of Michigan that includes Los Alamos National Laboratory as a partner has been...

116

Nuclear reactor flow control method and apparatus  

DOE Patents [OSTI]

Method and apparatus for improving coolant flow in a nuclear reactor during accident as well as nominal conditions. The reactor has a plurality of fuel elements in sleeves and a plenum above the fuel and through which the sleeves penetrate. Holes are provided in the sleeve so that coolant from the plenum can enter the sleeve and cool the fuel. The number and size of the holes are varied from sleeve to sleeve with the number and size of holes being greater for sleeves toward the center of the core and less for sleeves toward the periphery of the core. Preferably the holes are all the same diameter and arranged in rows and columns, the rows starting from the bottom of every sleeve and fewer rows in peripheral sleeves and more rows in the central sleeves.

Church, John P. (1204 Woodbine Rd., Aiken, SC 29803)

1993-01-01T23:59:59.000Z

117

Nuclear reactor flow control method and apparatus  

DOE Patents [OSTI]

Method and apparatus for improving coolant flow in a nuclear reactor during accident as well as nominal conditions. The reactor has a plurality of fuel elements in sleeves and a plenum above the fuel and through which the sleeves penetrate. Holes are provided in the sleeve so that coolant from the plenum can enter the sleeve and cool the fuel. The number and size of the holes are varied from sleeve to sleeve with the number and size of holes being greater for sleeves toward the center of the core and less for sleeves toward the periphery of the core. Preferably the holes are all the same diameter and arranged in rows and columns, the rows starting from the bottom of every sleeve and fewer rows in peripheral sleeves and more rows in the central sleeves.

Church, J.P.

1993-03-30T23:59:59.000Z

118

Dual annular rotating "windowed" nuclear reflector reactor control system  

DOE Patents [OSTI]

A nuclear reactor control system is provided in a nuclear reactor having a core operating in the fast neutron energy spectrum where criticality control is achieved by neutron leakage. The control system includes dual annular, rotatable reflector rings. There are two reflector rings: an inner reflector ring and an outer reflector ring. The reflectors are concentrically assembled, surround the reactor core, and each reflector ring includes a plurality of openings. The openings in each ring are capable of being aligned or non-aligned with each other. Independent driving means for each of the annular reflector rings is provided so that reactor criticality can be initiated and controlled by rotation of either reflector ring such that the extent of alignment of the openings in each ring controls the reflection of neutrons from the core.

Jacox, Michael G. (Idaho Falls, ID); Drexler, Robert L. (Idaho Falls, ID); Hunt, Robert N. M. (Idaho Falls, ID); Lake, James A. (Idaho Falls, ID)

1994-01-01T23:59:59.000Z

119

Temperature dependent scattering cross section effects on nuclear reactor control  

E-Print Network [OSTI]

Reactor e e o e o a a e e ~ a o e ~ a e o o 43 Ato. . . Dsnsitiec of 'Materials in the Conceived Fast Nuclear Reactor ~ ~ o e o e e a o a o e e o ~ ~ ~ ~ 6, IDPut SPecifications oi' the AIYi-6 Criticality arch e o o e a a ~ a e e o ~ ~ ~ e e e ~ o e... both reactors depended upon axially expanding fuel elements for inherent control, other methods should be considered, Due to ths magnitude and sign of the reactivity cosfi'ioients, inherent control is especially of. interest in large fast nuclear...

Biggs, Charles Leon

1968-01-01T23:59:59.000Z

120

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect (OSTI)

Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

Lynne M. Stevens

2010-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Nuclear reactor control rod cluster for enthalpy rise compensation  

SciTech Connect (OSTI)

This patent describes a control arrangement for use with a nuclear fuel assembly having guide thimbles to provide enthalpy rise compensation, comprising: (a) a spider assembly; and (b) control rodlets containing neutron absorber material, supported at their upper ends from the spider assembly in a pattern which matches that of the guide thimbles and extending generally parallel to one another downwardly for insertion into the guide thimbles of the fuel assembly; (c) the control rodlets arranged in a cluster having a higher axial neutron absorption capability at an upper portion than at a lower portion; each control rodlet varying in axial neutron absorption capability from every other rodlet.

Freeman, T.R.

1987-07-07T23:59:59.000Z

122

Coherent Control of a Single Silicon-29 Nuclear Spin Qubit  

E-Print Network [OSTI]

Magnetic fluctuations caused by the nuclear spins of a host crystal are often the leading source of decoherence for many types of solid-state spin qubit. In group-IV materials, the spin-bearing nuclei are sufficiently rare that it is possible to identify and control individual host nuclear spins. This work presents the first experimental detection and manipulation of a single $^{29}$Si nuclear spin. The quantum non-demolition (QND) single-shot readout of the spin is demonstrated, and a Hahn echo measurement reveals a coherence time of $T_2 = 6.3(7)$ ms - in excellent agreement with bulk experiments. Atomistic modeling combined with extracted experimental parameters provides possible lattice sites for the $^{29}$Si atom under investigation. These results demonstrate that single $^{29}$Si nuclear spins could serve as a valuable resource in a silicon spin-based quantum computer.

Jarryd J. Pla; Fahd A. Mohiyaddin; Kuan Y. Tan; Juan P. Dehollain; Rajib Rahman; Gerhard Klimeck; David N. Jamieson; Andrew S. Dzurak; Andrea Morello

2014-08-06T23:59:59.000Z

123

Nuclear Material Control and Accountability System Effectiveness Tool (MSET)  

SciTech Connect (OSTI)

A nuclear material control and accountability (MC&A) system effectiveness tool (MSET) has been developed in the United States for use in evaluating material protection, control, and accountability (MPC&A) systems in nuclear facilities. The project was commissioned by the National Nuclear Security Administration's Office of International Material Protection and Cooperation. MSET was developed by personnel with experience spanning more than six decades in both the U.S. and international nuclear programs and with experience in probabilistic risk assessment (PRA) in the nuclear power industry. MSET offers significant potential benefits for improving nuclear safeguards and security in any nation with a nuclear program. MSET provides a design basis for developing an MC&A system at a nuclear facility that functions to protect against insider theft or diversion of nuclear materials. MSET analyzes the system and identifies several risk importance factors that show where sustainability is essential for optimal performance and where performance degradation has the greatest impact on total system risk. MSET contains five major components: (1) A functional model that shows how to design, build, implement, and operate a robust nuclear MC&A system (2) A fault tree of the operating MC&A system that adapts PRA methodology to analyze system effectiveness and give a relative risk of failure assessment of the system (3) A questionnaire used to document the facility's current MPC&A system (provides data to evaluate the quality of the system and the level of performance of each basic task performed throughout the material balance area [MBA]) (4) A formal process of applying expert judgment to convert the facility questionnaire data into numeric values representing the performance level of each basic event for use in the fault tree risk assessment calculations (5) PRA software that performs the fault tree risk assessment calculations and produces risk importance factor reports on the facility's MC&A (software widely used in the aerospace, chemical, and nuclear power industries) MSET was peer reviewed in 2007 and validated in 2008 by benchmark testing at the Idaho National Laboratory in the United States. The MSET documents were translated into Russian and provided to Rosatom in July of 2008, and MSET is currently being evaluated for potential application in Russian Nuclear Facilities.

Powell, Danny H [ORNL] [ORNL; Elwood Jr, Robert H [ORNL] [ORNL; Roche, Charles T [ORNL] [ORNL; Campbell, Billy J [ORNL] [ORNL; Hammond, Glenn A [ORNL] [ORNL; Meppen, Bruce W [ORNL] [ORNL; Brown, Richard F [ORNL] [ORNL

2011-01-01T23:59:59.000Z

124

Method of controlling crystallite size in nuclear-reactor fuels  

DOE Patents [OSTI]

Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.

Lloyd, Milton H. (Oak Ridge, TN); Collins, Jack L. (Knoxville, TN); Shell, Sam E. (Oak Ridge, TN)

1985-01-01T23:59:59.000Z

125

Automatic coolant flow control device for a nuclear reactor assembly  

DOE Patents [OSTI]

A device which controls coolant flow through a nuclear reactor assembly comprises a baffle means at the exit end of said assembly having a plurality of orifices, and a bimetallic member in operative relation to the baffle means such that at increased temperatures said bimetallic member deforms to unblock some of said orifices and allow increased coolant flow therethrough.

Hutter, Ernest (Wilmette, IL)

1986-01-01T23:59:59.000Z

126

CIA sheds new light on nuclear control in CIS  

SciTech Connect (OSTI)

In a wide-ranging presentation to the Senate Governmental Affairs Committee February 24, 1993, newly installed CIA director James Woolsey and one of his senior aides provided a great deal of new information on nuclear weapons issues and how they are controlled in the former USSR. The main topics covered in the briefing are briefly discussed.

Lockwood, D.

1993-03-01T23:59:59.000Z

127

Automatic coolant flow control device for a nuclear reactor assembly  

DOE Patents [OSTI]

A device which controls coolant flow through a nuclear reactor assembly comprises a baffle means at the exit end of said assembly having a plurality of orifices, and a bimetallic member in operative relation to the baffle means such that at increased temperatures said bimetallic member deforms to unblock some of said orifices and allow increased coolant flow therethrough.

Hutter, E.

1984-01-27T23:59:59.000Z

128

Indicator system for advanced nuclear plant control complex  

DOE Patents [OSTI]

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

129

Kinetic advantage of controlled intermediate nuclear fusion  

SciTech Connect (OSTI)

The dominated process of controlled fusion is to let nuclei gain enough kinetic energy to overcome Coulomb barrier. As a result, a fusion scheme can consider two factors in its design: to increase kinetic energy of nuclei and to alter the Coulomb barrier. Cold Fusion and Hot fusion are all one-factor schemes while Intermediate Fusion is a twofactors scheme. This made CINF kinetically superior. Cold Fusion reduces deuteron-deuteron distance, addressing Coulomb barrier, and Hot Fusion heat up plasma into extreme high temperature, addressing kinetic energy. Without enough kinetic energy made Cold Fusion skeptical. Extreme high temperature made Hot Fusion very difficult to engineer. Because CIFN addresses both factors, CIFN is a more promising technique to be industrialized.

Guo Xiaoming [Physics and Computer Science Department, Wilfrid Laurier University, Waterloo, Ontario, N2L 3C5 (Canada)

2012-09-26T23:59:59.000Z

130

A nuclear data acquisition system flow control model  

SciTech Connect (OSTI)

A general Petri Net representation of a nuclear data acquisition system model is presented. This model provides for the unique requirements of a nuclear data acquisition system including the capabilities of concurrently acquiring asynchronous and synchronous data, of providing multiple priority levels of flow control arbitration, and of permitting multiple input sources to reside at the same priority without the problem of channel lockout caused by a high rate data source. Finally, a previously implemented gamma camera/physiological signal data acquisition system is described using the models presented.

Hack, S.N.

1988-02-01T23:59:59.000Z

131

Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA | UNCLASSIFIED | 1  

E-Print Network [OSTI]

Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA.S. Department of Energy's NNSA | UNCLASSIFIED | 2 Outline Isotope Production Facility Cutting of Window.S. Department of Energy's NNSA | UNCLASSIFIED | 3 Isotope Production Facility - LANSCE H+ is produced

McDonald, Kirk

132

A holistic investigation of complexity sources in nuclear power plant control rooms  

E-Print Network [OSTI]

The nuclear power community in the United States is moving to modernize aging power plant control rooms as well as develop control rooms for new reactors. New generation control rooms, along with modernized control rooms, ...

Sasangohar, Farzan

2011-01-01T23:59:59.000Z

133

An Approach to Autonomous Control for Space Nuclear Power Systems  

SciTech Connect (OSTI)

Under Project Prometheus, the National Aeronautics and Space Administration (NASA) investigated deep space missions that would utilize space nuclear power systems (SNPSs) to provide energy for propulsion and spacecraft power. The initial study involved the Jupiter Icy Moons Orbiter (JIMO), which was proposed to conduct in-depth studies of three Jovian moons. Current radioisotope thermoelectric generator (RTG) and solar power systems cannot meet expected mission power demands, which include propulsion, scientific instrument packages, and communications. Historically, RTGs have provided long-lived, highly reliable, low-power-level systems. Solar power systems can provide much greater levels of power, but power density levels decrease dramatically at {approx} 1.5 astronomical units (AU) and beyond. Alternatively, an SNPS can supply high-sustained power for space applications that is both reliable and mass efficient. Terrestrial nuclear reactors employ varying degrees of human control and decision-making for operations and benefit from periodic human interaction for maintenance. In contrast, the control system of an SNPS must be able to provide continuous operatio for the mission duration with limited immediate human interaction and no opportunity for hardware maintenance or sensor calibration. In effect, the SNPS control system must be able to independently operate the power plant while maintaining power production even when subject to off-normal events and component failure. This capability is critical because it will not be possible to rely upon continuous, immediate human interaction for control due to communications delays and periods of planetary occlusion. In addition, uncertainties, rare events, and component degradation combine with the aforementioned inaccessibility and unattended operation to pose unique challenges that an SNPS control system must accommodate. Autonomous control is needed to address these challenges and optimize the reactor control design.

Wood, Richard Thomas [ORNL; Upadhyaya, Belle R. [University of Tennessee, Knoxville (UTK)

2011-01-01T23:59:59.000Z

134

Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities  

SciTech Connect (OSTI)

The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for 85Kr and 129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ) and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs), have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures.

N. R. Soelberg; J. D. Law; T. G. Garn; M. Greenhalgh; R. T. Jubin; P. Thallapally; D. M. Strachan

2013-08-01T23:59:59.000Z

135

Nuclear Arms Control R&D Consortium  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includes Los Alamos April 7, 2014

136

Unclassified Foreign Visits and Assignments Program - DOE Directives,  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIAUltrafastaminoindazole,sediments. |63Delegations,

137

An attempt to control a manmade nuclear fusion  

E-Print Network [OSTI]

A detailed simple model is applied to study a high temperature hydrogen plasma ball. It is assumed that the ions and delocalized electrons are distributed randomly throughout the charged plasma ball (extra/missing charge is assumed to be found in a thin layer on the surface of a ball). The energy of the microscopic electrostatic field around the ions is taken into account and calculated. It is shown in the framework of the model that charged hydrogen plasma ball can be stable as a metastable state, when subjected to external (atmospheric) pressure. Equilibrium radius of a ball, the barrier and the enthalpy of the equilibrium ball are calculated. It looks like the charged plasma ball in a metastable equilibrium should be used to conduct controllable nuclear fusion. Changes in the electric charge can be used to control the volume of a plasma ball.

Yuri Kornyushin

2007-10-22T23:59:59.000Z

138

PIA - WEB Unclassified Business Operations General Support System |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - September 2006 The 2002OpticsPeriodical:Rocky Mountain OTCSunflower

139

Exchange Control of Nuclear Spin Diffusion in a Double Quantum Dot  

E-Print Network [OSTI]

The influence of gate-controlled two-electron exchange on the relaxation of nuclear polarization in small ensembles (N?10[superscript 6]) of nuclear spins is examined in a GaAs double quantum dot system. Waiting in the ...

Reilly, D. J.

140

Nuclear reactor control rod with uniformly changeable axial worth  

SciTech Connect (OSTI)

A control rod is described for use in a nuclear reactor core to provide xenon compensation, comprising: (a) an elongated inner cylindrical member having a lower end; and (b) an elongated outer cylindrical member surrounding the inner member and having a lower end with concentrically-arranged inner and outer edge portions defined thereon; (c) each of the members being composed of alternating poison and nonpoison regions; (d) the inner member being axially movable relative to the outer member to adjust the degree to which the poison regions of the members overlap with the nonpoison regions thereof and thereby change the overall worth of the rod; and (e) the lower end of the inner member having defined thereon a radially outwardly projecting ledge for supporting in a rest relationship thereon the lower end of the outer member at only its inner edge portion for retaining the outer member about the inner member.

Freeman, T.R.

1989-04-11T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Flammability Control In A Nuclear Waste Vitrification System  

SciTech Connect (OSTI)

The Defense Waste Processing Facility at the Savannah River Site processes high-level radioactive waste from the processing of nuclear materials that contains dissolved and precipitated metals and radionuclides. Vitrification of this waste into borosilicate glass for ultimate disposal at a geologic repository involves chemically modifying the waste to make it compatible with the glass melter system. Pretreatment steps include removal of excess aluminum by dissolution and washing, and processing with formic and nitric acids to: 1) adjust the reduction-oxidation (redox) potential in the glass melter to reduce radionuclide volatility and improve melt rate; 2) adjust feed rheology; and 3) reduce by steam stripping the amount of mercury that must be processed in the melter. Elimination of formic acid in pretreatment has been studied to eliminate the production of hydrogen in the pretreatment systems, which requires nuclear grade monitoring equipment. An alternative reductant, glycolic acid, has been studied as a substitute for formic acid. However, in the melter, the potential for greater formation of flammable gases exists with glycolic acid. Melter flammability is difficult to control because flammable mixtures can be formed during surges in offgases that both increase the amount of flammable species and decrease the temperature in the vapor space of the melter. A flammable surge can exceed the 60% of the LFL with no way to mitigate it. Therefore, careful control of the melter feed composition based on scaled melter surge testing is required. The results of engineering scale melter tests with the formic-nitric flowsheet and the use of these data in the melter flammability model are presented.

Zamecnik, John R.; Choi, Alexander S.; Johnson, Fabienne C.; Miller, Donald H.; Lambert, Daniel P.; Stone, Michael E.; Daniel, William E. Jr.

2013-07-25T23:59:59.000Z

142

Improved Design of Nuclear Reactor Control System | U.S. DOE...  

Office of Science (SC) Website

instrumentation: Improved Design of Nuclear Reactor Control System Developed at: Oak Ridge National Laboratory, Holifield Radioactive Ion Beam Facility (HRIBF) Developed...

143

Neural net controlled tag gas sampling system for nuclear reactors  

DOE Patents [OSTI]

A method and system for providing a tag gas identifier to a nuclear fuel rod and analyze escaped tag gas to identify a particular failed nuclear fuel rod. The method and system include disposing a unique tag gas composition into a plenum of a nuclear fuel rod, monitoring gamma ray activity, analyzing gamma ray signals to assess whether a nuclear fuel rod has failed and is emitting tag gas, activating a tag gas sampling and analysis system upon sensing tag gas emission from a failed nuclear rod and evaluating the escaped tag gas to identify the particular failed nuclear fuel rod.

Gross, Kenneth C. (Bolingbrook, IL); Laug, Matthew T. (Idaho Fall, ID); Lambert, John D. B. (Wheaton, IL); Herzog, James P. (Downers Grove, IL)

1997-01-01T23:59:59.000Z

144

Neural net controlled tag gas sampling system for nuclear reactors  

DOE Patents [OSTI]

A method and system are disclosed for providing a tag gas identifier to a nuclear fuel rod and analyze escaped tag gas to identify a particular failed nuclear fuel rod. The method and system include disposing a unique tag gas composition into a plenum of a nuclear fuel rod, monitoring gamma ray activity, analyzing gamma ray signals to assess whether a nuclear fuel rod has failed and is emitting tag gas, activating a tag gas sampling and analysis system upon sensing tag gas emission from a failed nuclear rod and evaluating the escaped tag gas to identify the particular failed nuclear fuel rod. 12 figs.

Gross, K.C.; Laug, M.T.; Lambert, J.B.; Herzog, J.P.

1997-02-11T23:59:59.000Z

145

Status of radioiodine control for nuclear fuel reprocessing plants  

SciTech Connect (OSTI)

This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used.

Burger, L.L.; Scheele, R.D.

1983-07-01T23:59:59.000Z

146

Tags and seals for controling nuclear materials, Arms control and nonproliferation technologies. Second quarter 1993  

SciTech Connect (OSTI)

This issue of Arms Control and Nonproliferation Technologies summarizes demonstrations and addresses related topics. The first article, ``Basic Nuclear Material Control and Accountability Concepts as Might be Applied to the Uranium from the US-Russian HEU Purchase,`` describes safeguards sybsystems necessary for effective nuclear material safeguards. It also presents a general discussion on HEU-to-low-enrichment uranium (LEU) commingling processes and suggests applicable key measurement points. The second article, ``A Framework for Evaluating Tamper-Indicating-Device Technologies (TIDs),`` describes their uses, proper selection, and evaluation. The final three articles discuss the tags and seals applications and general characteristics of several nuclear material containers: the Type 30B uranium hexafluoride container, the AT-400R container, and the DOT Specification 6M container for SNM. Finally, the Appendix displays short descriptions and illustrations of seven tags and seals, including: the E-cup and wire seal, the python seal, the secure loop inspectable tag/seal (SLITS), bolt-and-loop type electronic identification devices, and the shrink-wrap seal.

Staehle, G; Talaber, C; Stull, S; Moulthrop, P [eds.

1993-12-31T23:59:59.000Z

147

Insiders and outsiders : nuclear arms control experts in Cold War America  

E-Print Network [OSTI]

This dissertation presents a history of the community of nuclear arms control experts in the United States during the middle and later years of the Cold War, the age of thermonuclear ballistic missiles. Arms control experts ...

Wilson, Benjamin Tyler

2014-01-01T23:59:59.000Z

148

Nuclear reactor control rod having a reduced worth tip  

SciTech Connect (OSTI)

This patent describes a nuclear reactor having a fuel assembly and a control rod moveable in and out for controlling the reactivity of the reactor, the control rod comprising: (a) an elongated tubular cladding; (b) means for closing the opposite ends of the cladding; (c) first pellets of a first type disposed within the cladding in an end-to-end relationship; and (d) second pellets of a second type disposed within the cladding in an end-to-end relationship; (e) one of the first and second types of pellets being formed of a material having a generally high neutron absorbing capacity; (f) the other of the first and second types of pellets being formed of an inert material having a generally low neutron absorbing capacity; (g) the pellets of the first and second types thereof being cylindrical with their respective diameters being generally equal; (h) the inert pellets being interspaced between the high neutron absorbing pellets at a lower end portion of the cladding with the remaining portion of the cladding above the lower end portion containing only the high neutron absorbing pellets; and (i) the axial heights of one of the first and second pluralities of pellets of the first and second types located at the lower end portion of the cladding progressively varying from pellet to pellet, the axial heights of the other of the first and second pellets of the first and second types located at the lower end portion of the cladding are generally equal from pellet to pellet, so as to produce an improved reduced worth tip at the lower end portion of the cladding.

Doshi, P.K.; Wilson, J.F.

1986-11-25T23:59:59.000Z

149

Optical control of nuclear resonant absorption: theory and experiment  

E-Print Network [OSTI]

Modification of nuclear resonant absorption by means of laser radiation is analyzed both theoretically and experimentally. Theoretical analysis is done on the basis of four-level model of atom. This model includes both electronic and nuclear...

Kolesov, Roman L.

2004-09-30T23:59:59.000Z

150

Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities  

SciTech Connect (OSTI)

Nuclear fission results in the production of fission products and activation products, some of which tend to be volatile during used fuel reprocessing. These can evolve in volatile species in the reprocessing facility off-gas streams, depending on the separations and reprocessing technologies that are used. Radionuclides that have been identified as volatile radionuclides are noble gases (most notably isotopes of Kr and Xe); 3H; 14C; and 129I. Radionuclides that tend to form volatile species that evolve into reprocessing facility off-gas systems are more challenging to efficiently control compared to radionuclides that tend to stay in solid or liquid phases. Future used fuel reprocessing facilities in the United States can require efficient capture of some volatile radionuclides in their off-gas streams to meet regulatory emission requirements. In aqueous reprocessing, these radionuclides are most commonly expected to evolve into off-gas streams in tritiated water [3H2O (T2O) and 3HHO (THO)], radioactive CO2, noble gases, and gaseous HI, I2, or volatile organic iodides. The fate and speciation of these radionuclides from a non-aqueous fuel reprocessing facility is less well known at this time, but active investigations are in progress. An Off-Gas Sigma Team was formed in late FY 2009 to integrate and coordinate the Fuel Cycle Research and Development (FCR&D) activities directed towards the capture and sequestration of the these volatile radionuclides (Jubin 2012a). The Sigma Team concept was envisioned to bring together multidisciplinary teams from across the DOE complex that would work collaboratively to solve the technical challenges and to develop the scientific basis for the capture and immobilization technologies such that the sum of the efforts was greater than the individual parts. The Laboratories currently participating in this effort are Argonne National Laboratory (ANL), Idaho National Laboratory (INL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL). This article focuses on control of volatile radionuclides that evolve during aqueous reprocessing of UNF. In particular, most of the work by the Off-gas Sigma Team has focused on the capture and sequestration of 129I and 85Kr, mainly because, as discussed below, control of 129I can require high efficiencies to meet regulatory requirements, and control of 85Kr using cryogenic processing, which has been the technology demonstrated and used commercially to date, can add considerable cost to a reprocessing facility.

Soelberg, Nicolas R. [Idaho National Laboratory, Idaho Falls, ID (United States); Garn, Troy [Idaho National Laboratory, Idaho Falls, ID (United States); Greenhalgh, Mitchell [Idaho National Laboratory, Idaho Falls, ID (United States); Law, Jack [Idaho National Laboratory, Idaho Falls, ID (United States); Jubin, Robert T. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Strachan, Denis M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Thallapally, Praveen K. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

2013-07-22T23:59:59.000Z

151

Unclassified Source Term and Radionuclide Data for Corrective Action Unit 98: Frenchman Flat Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect (OSTI)

Frenchman Flat is one of several areas of the Nevada Test Site (NTS) used for underground nuclear testing (Figure 1-1). These nuclear tests resulted in groundwater contamination in the vicinity of the underground test areas. As a result, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is currently conducting a corrective action investigation (CAI) of the Frenchman Flat underground test areas. Since 1996, the Nevada Division of Environmental Protection (NDEP) has regulated NNSA/NSO corrective actions through the ''Federal Facility Agreement and Consent Order'' ([FFACO], 1996). Appendix VI of the FFACO agreement, ''Corrective Action Strategy'', was revised on December 7, 2000, and describes the processes that will be used to complete corrective actions, including those in the Underground Test Area (UGTA) Project. The individual locations covered by the agreement are known as corrective action sites (CASs), which are grouped into corrective action units (CAUs). The UGTA CASs are grouped geographically into five CAUs: Frenchman Flat, Central Pahute Mesa, Western Pahute Mesa, Yucca Flat/Climax Mine, and Rainier Mesa/Shoshone Mountain (Figure 1-1). These CAUs have distinctly different contaminant source, geologic, and hydrogeologic characteristics related to their location (FFACO, 1996). The Frenchman Flat CAU consists of 10 CASs located in the northern part of Area 5 and the southern part of Area 11 (Figure 1-1). This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for Frenchman Flat, CAU 98. The methodology used to estimate hydrologic source terms (HSTs) for the Frenchman Flat CAU is also documented. The HST of an underground nuclear test is the portion of the total inventory of radionuclides that is released over time into the groundwater following the test. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. This evaluation was conducted in support of the development of a CAU contaminant transport model for the Frenchman Flat CAU.

Farnham, Irene

2005-09-01T23:59:59.000Z

152

JET Papers Presented at International Atomic Energy Agency 10th International Conference on Plasma Physics and Controlled Nuclear Research  

E-Print Network [OSTI]

JET Papers Presented at International Atomic Energy Agency 10th International Conference on Plasma Physics and Controlled Nuclear Research

153

Electromagnetic Signature Technique as a Promising Tool to Verify Nuclear Weapons Storage and Dismantlement under a Nuclear Arms Control Regime  

SciTech Connect (OSTI)

The 2010 ratification of the New START Treaty has been widely regarded as a noteworthy national security achievement for both the Obama administration and the Medvedev-Putin regime, but deeper cuts are envisioned under future arms control regimes. Future verification needs will include monitoring the storage of warhead components and fissile materials and verifying dismantlement of warheads, pits, secondaries, and other materials. From both the diplomatic and technical perspectives, verification under future arms control regimes will pose new challenges. Since acceptable verification technology must protect sensitive design information and attributes, non-nuclear non-sensitive signatures may provide a significant verification tool without the use of additional information barriers. The use of electromagnetic signatures to monitor nuclear material storage containers is a promising technology with the potential to fulfill these challenging requirements. Research performed at Pacific Northwest National Laboratory (PNNL) has demonstrated that low frequency electromagnetic signatures of sealed metallic containers can be used to confirm the presence of specific components on a yes/no basis without revealing classified information. Arms control inspectors might use this technique to verify the presence or absence of monitored items, including both nuclear and non-nuclear materials. Although additional research is needed to study signature aspects such as uniqueness and investigate container-specific scenarios, the technique potentially offers a rapid and cost-effective tool to verify reduction and dismantlement of U.S. and Russian nuclear weapons.

Bunch, Kyle J.; Williams, Laura S.; Jones, Anthony M.; Ramuhalli, Pradeep

2012-08-01T23:59:59.000Z

154

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

SciTech Connect (OSTI)

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

Williams, Laura S.

2011-05-25T23:59:59.000Z

155

Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA UNCLASSIFIED  

E-Print Network [OSTI]

, LLC for the U.S. Department of Energy's NNSA Ocean routes for commerce #12;Operated by Los AlamosOperated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA UNCLASSIFIED #12;Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA

156

ACCELERATED TESTING OF NEUTRON-ABSORBING ALLOYS FOR NUCLEAR CRITICALITY CONTROL  

SciTech Connect (OSTI)

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

157

Method of nuclear reactor control using a variable temperature load dependent set point  

SciTech Connect (OSTI)

A method and apparatus for controlling a nuclear reactor in response to a variable average reactor coolant temperature set point is disclosed. The set point is dependent upon percent of full power load demand. A manually-actuated ''droop mode'' of control is provided whereby the reactor coolant temperature is allowed to drop below the set point temperature a predetermined amount wherein the control is switched from reactor control rods exclusively to feedwater flow.

Kelly, J.J.; Rambo, G.E.

1982-04-27T23:59:59.000Z

158

Startup control of the TOPAZ-II space nuclear reactor. Master`s thesis  

SciTech Connect (OSTI)

The Russian designed and manufactured TOPAZ-II Thermionic Nuclear Space Reactor has been supplied to the Ballistic Missile Defense Organization for study as part of the TOPAZ International Program. A Preliminary Nuclear Safety Assessment investigated the readiness to use the TOPAZ-II in support of a Nuclear Electric Propulsion Space Test Mission (NEPSTP). Among the anticipated system modifications required for launching the TOPAZ-II system within safety goals is for a U.S. designed Automatic Control System. The requirements and desired features of such a control system are developed based upon U.S. safety standards. System theory and design are presented in order to establish the basis for development of a hybrid control model from available simulations. The model is verified and then used in exploration of various control schemes and casualty analysis providing groundwork for future Automatic Control System design.

Astrin, C.D.

1996-09-01T23:59:59.000Z

159

OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS  

SciTech Connect (OSTI)

This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

Ronald L. Boring

2012-10-01T23:59:59.000Z

160

Mapping Complexity Sources in Nuclear Power Plant Domains Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their  

E-Print Network [OSTI]

Mapping Complexity Sources in Nuclear Power Plant Domains Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their effects on human reliability is critical of complexity leveraging network theory. INTRODUCTION The nuclear power industry in United States has declined

Cummings, Mary "Missy"

Note: This page contains sample records for the topic "unclassified controlled nuclear" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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161

A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty  

E-Print Network [OSTI]

A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty@csam.ucl.ac.be, Gevers@csam.ucl.ac.be 2 Electricite de France, Direction des Etudes et Recherches, 6 Quai Watier, F-78041 of a controller for the secondary circuit of a nu- clear Pressurized Water Reactor, leading to the conclu- sions

Gevers, Michel

162

FRAMEWORK AND APPLICATION FOR MODELING CONTROL ROOM CREW PERFORMANCE AT NUCLEAR POWER PLANTS  

SciTech Connect (OSTI)

This paper summarizes an emerging project regarding the utilization of high-fidelity MIDAS simulations for visualizing and modeling control room crew performance at nuclear power plants. The key envisioned uses for MIDAS-based control room simulations are: (i) the estimation of human error associated with advanced control room equipment and configurations, (ii) the investigative determination of contributory cognitive factors for risk significant scenarios involving control room operating crews, and (iii) the certification of reduced staffing levels in advanced control rooms. It is proposed that MIDAS serves as a key component for the effective modeling of cognition, elements of situation awareness, and risk associated with human performance in next generation control rooms.

Ronald L Boring; David I Gertman; Tuan Q Tran; Brian F Gore

2008-09-01T23:59:59.000Z

163

Controlled Unclassified Information and E.O. 13556 | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power Systems EngineeringDepartmentSmart GridThird Quarter OverallDepartment of

164

Optimal control theory for xenon spatial oscillations in load follow of a nuclear reactor  

SciTech Connect (OSTI)

A simple core control model has been developed for the control of xenon spatial oscillations in load-following operations of a current design commercial nuclear pressurized water reactor. The model has been formulated as a linear - quadratic - tracking problem in the context of moderm optimal control theory and the resulting two-point boundary value problem (TPBVP) has been solved directly by the techniques of initial value methods.

Cho, N.Z.

1980-01-01T23:59:59.000Z

165

Device for actuating a nuclear reactor control rod  

SciTech Connect (OSTI)

A first assembly for low-speed translational displacement and dropping of a control rod comprises a leak-tight casing tube which communicates with the reactor vessel, a screw and nut system coupled to the control rod by means of the nut and a screw -retaining device which is capable of releasing the screw. In the event of accidental failure of the casing tube, upward displacement of the control rod and of the broken portion of the casing tube is limited by a second assembly comprising means for rotational locking of the screw drive rotor and calibrated elastic means for producing action on the rotor in opposition to the vertical thrust produced by failure of the casing tube.

Etienne, C.; Fardouet, C.; L'abbe, G.M.

1982-02-09T23:59:59.000Z

166

WTEC panel report on European nuclear instrumentation and controls. Final report  

SciTech Connect (OSTI)

A study of instrumentation and controls (I and C) technology used in nuclear power plants in Europe was conducted by a panel of US specialists. This study plants in Europe was conducted by a panel of US specialists. This study included a review of the literature on the subject, followed by a visit to some of the leading organizations in Europe in the field nuclear I and C. Areas covered are: (1) role of the operator and control room design; (2) transition from analog to digital technology; (3) computerized operator support systems for fault management; (4) control strategies and techniques; (5) Nuclear power plant I and C architecture; (6) instrumentation and (7) computer standards and tools. The finding relate to poor reactions.

White, J.D.; Lanning, D.D.; Johnson, P.M.H. [eds.] [World Technology Evaluation Center, Baltimore, MD (United States); Shelton, R.D. [World Technology Evaluation Center, Baltimore, MD (United States)

1991-12-01T23:59:59.000Z

167

Dual annular rotating [open quotes]windowed[close quotes] nuclear reflector reactor control system  

DOE Patents [OSTI]

A nuclear reactor control system is provided in a nuclear reactor having a core operating in the fast neutron energy spectrum where criticality control is achieved by neutron leakage. The control system includes dual annular, rotatable reflector rings. There are two reflector rings: an inner reflector ring and an outer reflector ring. The reflectors are concentrically assembled, surround the reactor core, and each reflector ring includes a plurality of openings. The openings in each ring are capable of being aligned or non-aligned with each other. Independent driving means for each of the annular reflector rings is provided so that reactor criticality can be initiated and controlled by rotation of either reflector ring such that the extent of alignment of the openings in each ring controls the reflection of neutrons from the core. 4 figures.

Jacox, M.G.; Drexler, R.L.; Hunt, R.N.M.; Lake, J.A.

1994-03-29T23:59:59.000Z

168

Unclassified Source Term and Radionuclide Data for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada Test Site, Nevada, Revision 1  

SciTech Connect (OSTI)

This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for CAU 97: Yucca Flat/Climax Mine. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. The hydrologic source term (HST) of an underground nuclear test is the portion of the total RST that is released into the groundwater over time following the test. In this report, the HST represents radionuclide release some time after the explosion and does not include the rapidly evolving mechanical, thermal, and chemical processes during the explosion. The CAU 97: Yucca Flat/Climax Mine has many more detonations and a wider variety of settings to consider compared to other CAUs. For instance, the source term analysis and evaluation performed for CAUs 101 and 102: Central and Western Pahute Mesa and CAU 98: Frenchman Flat did not consider vadose zone attenuation because many detonations were located near or below the water table. However, the large number of Yucca Flat/Climax Mine tests and the location of many tests above the water table warrant a more robust analysis of the unsaturated zone.

Peter Martian

2009-05-01T23:59:59.000Z

169

Nuclear export controls and the CTBT: Where we`ve been and challenges ahead -- Views of an engineer  

SciTech Connect (OSTI)

The paper discusses the following topics: the importance of export controls; the uniqueness of nuclear weapons and their export control requirements; ``dual-use`` controls; and recent developments in nonproliferation beyond export control. Also discussed are some non-obvious challenges which include computer modeling and visualization, and fissile material availability and instant nukes. The author concludes by asking the Nuclear Suppliers Group to consider whether there are ways to make its controls more effective.

Lundy, A.S.

1998-09-01T23:59:59.000Z

170

Application of an exact model matching technique to coupled-core nuclear reactor control  

SciTech Connect (OSTI)

In this Note the control problem of linearized coupled-core multivariable nuclear reactors is treated by using a recent exact model matching technique in the frequency domain. The case of state feedback control is first considered and then the results are used where only the output variables of the reactor are available for feedback. A numerical example of a three coupled-core nuclear reactor model with one delayed neutron group for each core and short neutron travel time between cores is included.

Tzafestas, S.G.; Chrysochoides, N.G.; Rokkos, K.

1984-08-01T23:59:59.000Z

171

Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems  

SciTech Connect (OSTI)

This report presents the technical basis for establishing acceptable mitigating strategies that resolve diversity and defense-in-depth (D3) assessment findings and conform to U.S. Nuclear Regulatory Commission (NRC) requirements. The research approach employed to establish appropriate diversity strategies involves investigation of available documentation on D3 methods and experience from nuclear power and nonnuclear industries, capture of expert knowledge and lessons learned, determination of best practices, and assessment of the nature of common-cause failures (CCFs) and compensating diversity attributes. The research described in this report does not provide guidance on how to determine the need for diversity in a safety system to mitigate the consequences of potential CCFs. Rather, the scope of this report provides guidance to the staff and nuclear industry after a licensee or applicant has performed a D3 assessment per NUREG/CR-6303 and determined that diversity in a safety system is needed for mitigating the consequences of potential CCFs identified in the evaluation of the safety system design features. Succinctly, the purpose of the research described in this report was to answer the question, 'If diversity is required in a safety system to mitigate the consequences of potential CCFs, how much diversity is enough?' The principal results of this research effort have identified and developed diversity strategies, which consist of combinations of diversity attributes and their associated criteria. Technology, which corresponds to design diversity, is chosen as the principal system characteristic by which diversity criteria are grouped to form strategies. The rationale for this classification framework involves consideration of the profound impact that technology-focused design diversity provides. Consequently, the diversity usage classification scheme involves three families of strategies: (1) different technologies, (2) different approaches within the same technology, and (3) different architectures within the same technology. Using this convention, the first diversity usage family, designated Strategy A, is characterized by fundamentally diverse technologies. Strategy A at the system or platform level is illustrated by the example of analog and digital implementations. The second diversity usage family, designated Strategy B, is achieved through the use of distinctly different technologies. Strategy B can be described in terms of different digital technologies, such as the distinct approaches represented by general-purpose microprocessors and field-programmable gate arrays. The third diversity usage family, designated Strategy C, involves the use of variations within a technology. An example of Strategy C involves different digital architectures within the same technology, such as that provided by different microprocessors (e.g., Pentium and Power PC). The grouping of diversity criteria combinations according to Strategies A, B, and C establishes baseline diversity usage and facilitates a systematic organization of strategic approaches for coping with CCF vulnerabilities. Effectively, these baseline sets of diversity criteria constitute appropriate CCF mitigating strategies for digital safety systems. The strategies represent guidance on acceptable diversity usage and can be applied directly to ensure that CCF vulnerabilities identified through a D3 assessment have been adequately resolved. Additionally, a framework has been generated for capturing practices regarding diversity usage and a tool has been developed for the systematic assessment of the comparative effect of proposed diversity strategies (see Appendix A).

Wood, Richard Thomas [ORNL; Belles, Randy [ORNL; Cetiner, Mustafa Sacit [ORNL; Holcomb, David Eugene [ORNL; Korsah, Kofi [ORNL; Loebl, Andy [ORNL; Mays, Gary T [ORNL; Muhlheim, Michael David [ORNL; Mullens, James Allen [ORNL; Poore III, Willis P [ORNL; Qualls, A L [ORNL; Wilson, Thomas L [ORNL; Waterman, Michael E. [U.S. Nuclear Regulatory Commission

2010-02-01T23:59:59.000Z

172

Self-actuating and locking control for nuclear reactor  

DOE Patents [OSTI]

A self-actuating, self-locking flow cutoff valve particularly suited for use in a nuclear reactor of the type which utilizes a plurality of fluid support neutron absorber elements to provide for the safe shutdown of the reactor. The valve comprises a substantially vertical elongated housing and an aperture plate located in the housing for the flow of fluid therethrough, a substantially vertical elongated nozzle member located in the housing and affixed to the housing with an opening in the bottom for receiving fluid and apertures adjacent a top end for discharging fluid. The nozzle further includes two sealing means, one located above and the other below the apertures. Also located in the housing and having walls surrounding the nozzle is a flow cutoff sleeve having a fluid opening adjacent an upper end of the sleeve, the sleeve being moveable between an upper open position wherein the nozzle apertures are substantially unobstructed and a closed position wherein the sleeve and nozzle sealing surfaces are mated such that the flow of fluid through the apertures is obstructed. It is a particular feature of the present invention that the valve further includes a means for utilizing any increase in fluid pressure to maintain the cutoff sleeve in a closed position. It is another feature of the invention that there is provided a means for automatically closing the valve whenever the flow of fluid drops below a predetermined level.

Chung, Dong K. (Chatsworth, CA)

1982-01-01T23:59:59.000Z

173

Ultrafast control of nuclear spins using only microwave pulses: towards switchable solid-state quantum gates  

E-Print Network [OSTI]

We demonstrate the control of the alpha-proton nuclear spin, I=1/2, coupled to the stable radical CH(COOH)2, S=1/2, in a gamma-irradiated malonic acid single crystal using only microwave pulses. We show that, depending on the state of the electron spin mS=+/-1/2, the nuclear spin can be locked in a desired state or oscillate between mI=+1/2 and mI=-1/2 on the nanosecond time scale. This approach provides a fast and efficient way of controlling nuclear spin qubits and also enables the design of switchable spin-based quantum gates by addressing only the electron spin.

George Mitrikas; Yiannis Sanakis; Georgios Papavassiliou

2009-10-13T23:59:59.000Z

174

Method of installing a control room console in a nuclear power plant  

DOE Patents [OSTI]

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1994-01-01T23:59:59.000Z

175

Nuclear reactor control rod with uniformly changeable axial worth  

SciTech Connect (OSTI)

In combination with a fuel assembly having at least one hollow guide thimble, means to compensate for a reduction in reactivity occurring generally uniformly in a transverse direction and symmetric in the axial direction is described, comprising: (a) a control rod inserted in the guide thimble including (i) an elongated inner cylindrical member having a lower end, (ii) an elongated outer cylindrical member surrounding the inner member and having a lower end with concentrically-arranged lower inner and outer edge portions defined thereon, (iii) each of the members being composed of alternating poison and nonpoison regions, (iv) the inner member being axially movable relative to the outer member, (v) an outwardly projecting ledge adapted to support in a rest relationship the lower end of the outer member; and (b) means for retaining the outer member in a stationary position in the guide thimble while the inner member is movable axially relative thereto to adjust the degree to which the poison regions of the members overlap with the nonpoison regions and thereby change the overall worth of the rod. (c) The retaining means are in a lower portion of the guide thimble and sized to support the lower end of the outer member at its lower outer edge portion. The retaining means have a central hole sized to allow passage of the lower end and ledge of the inner member therethrough.

Freeman, T.R.

1987-11-17T23:59:59.000Z

176

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: neutron flux, cur- rent noise, vibration diagnostics: Swedish Nuclear Powe

Pzsit, Imre

177

Nuclear Instruments and Methods in Physics Research A 467468 (2001) 202205 Control and data acquisition systems for high field  

E-Print Network [OSTI]

Nuclear Instruments and Methods in Physics Research A 467­468 (2001) 202­205 Control and data, Budker Institute of Nuclear Physics of SBRAS, Lavrentyeva 11, 630090 Novosibirsk, Russia Abstract for installation at Bessy-II (Germany). The second one controls a 10 T wiggler which is under testing now

Kozak, Victor R.

178

Advanced international training course on state systems of accounting for and control of nuclear materials  

SciTech Connect (OSTI)

This report incorporates all lectures and presentations at the Advanced International Training Course on State Systems of Accounting for and Control of Nuclear Material held April 27 through May 12, 1981 at Santa Fe and Los Alamos, New Mexico, and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards. Major emphasis for the 1981 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory, the Battelle Pacific Northwest Laboratory, and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at both the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, Richland, Washington.

Not Available

1981-10-01T23:59:59.000Z

179

Applying Human Factors Evaluation and Design Guidance to a Nuclear Power Plant Digital Control System  

SciTech Connect (OSTI)

The United States (U.S.) nuclear industry, like similar process control industries, has moved toward upgrading its control rooms. The upgraded control rooms typically feature digital control system (DCS) displays embedded in the panels. These displays gather information from the system and represent that information on a single display surface. In this manner, the DCS combines many previously separate analog indicators and controls into a single digital display, whereby the operators can toggle between multiple windows to monitor and control different aspects of the plant. The design of the DCS depends on the function of the system it monitors, but revolves around presenting the information most germane to an operator at any point in time. DCSs require a carefully designed human system interface. This report centers on redesigning existing DCS displays for an example chemical volume control system (CVCS) at a U.S. nuclear power plant. The crucial nature of the CVCS, which controls coolant levels and boration in the primary system, requires a thorough human factors evaluation of its supporting DCS. The initial digital controls being developed for the DCSs tend to directly mimic the former analog controls. There are, however, unique operator interactions with a digital vs. analog interface, and the differences have not always been carefully factored in the translation of an analog interface to a replacement DCS. To ensure safety, efficiency, and usability of the emerging DCSs, a human factors usability evaluation was conducted on a CVCS DCS currently being used and refined at an existing U.S. nuclear power plant. Subject matter experts from process control engineering, software development, and human factors evaluated the DCS displays to document potential usability issues and propose design recommendations. The evaluation yielded 167 potential usability issues with the DCS. These issues should not be considered operator performance problems but rather opportunities identified by experts to improve upon the design of the DCS. A set of nine design recommendations was developed to address these potential issues. The design principles addressed the following areas: (1) color, (2) pop-up window structure, (3) navigation, (4) alarms, (5) process control diagram, (6) gestalt grouping, (7) typography, (8) terminology, and (9) data entry. Visuals illustrating the improved DCS displays accompany the design recommendations. These nine design principles serve as the starting point to a planned general DCS style guide that can be used across the U.S. nuclear industry to aid in the future design of effective DCS interfaces.

Thomas Ulrich; Ronald Boring; William Phoenix; Emily Dehority; Tim Whiting; Jonathan Morrell; Rhett Backstrom

2012-08-01T23:59:59.000Z

180

Supporting the President's Arms Control and Nonproliferation Agenda: Transparency and Verification for Nuclear Arms Reductions  

SciTech Connect (OSTI)

The President's arms control and nonproliferation agenda is still evolving and the details of initiatives supporting it remain undefined. This means that DOE, NNSA, NA-20, NA-24 and the national laboratories can help define the agenda, and the policies and the initiatives to support it. This will require effective internal and interagency coordination. The arms control and nonproliferation agenda is broad and includes the path-breaking goal of creating conditions for the elimination of nuclear weapons. Responsibility for various elements of the agenda will be widely scattered across the interagency. Therefore an interagency mapping exercise should be performed to identify the key points of engagement within NNSA and other agencies for creating effective policy coordination mechanisms. These can include informal networks, working groups, coordinating committees, interagency task forces, etc. It will be important for NA-20 and NA-24 to get a seat at the table and a functional role in many of these coordinating bodies. The arms control and nonproliferation agenda comprises both mature and developing policy initiatives. The more mature elements such as CTBT ratification and a follow-on strategic nuclear arms treaty with Russia have defined milestones. However, recent press reports indicate that even the START follow-on strategic arms pact that is planned to be complete by the end of 2009 may take significantly longer and be more expansive in scope. The Russians called for proposals to count non-deployed as well as deployed warheads. Other elements of the agenda such as FMCT, future bilateral nuclear arms reductions following a START follow-on treaty, nuclear posture changes, preparations for an international nuclear security summit, strengthened international safeguards and multilateral verification are in much earlier stages of development. For this reason any survey of arms control capabilities within the USG should be structured to address potential needs across the near-term (1-4) years and longer-term (5-10) years planning horizons. Some final observations include acknowledging the enduring nature of several key objectives on the Obama Administration's arms control and nonproliferation agenda. The CTBT, FMCT, bilateral nuclear arms reductions and strengthening the NPT have been sought by successive U.S. Administrations for nearly thirty years. Efforts towards negotiated arms control, although de-emphasized by the G.W. Bush Administration, have remained a pillar of U.S. national security strategy for decades and are likely to be of enduring if not increasing importance for decades to come. Therefore revitalization and expansion of USG capabilities in this area can be a positive legacy no matter what near-term arms control goals are achieved over the next four years. This is why it is important to reconstruct integrated bureaucratic, legislative, budgetary and diplomatic strategies to sustain the arms control and nonproliferation agenda. In this endeavor some past lessons must be taken to heart to avoid bureaucratic overkill and keep interagency policy-making and implementation structures lean and effective. On the Technical side a serious, sustained multilateral program to develop, down select and performance test nuclear weapons dismantlement verification technologies and procedures should be immediately initiated. In order to make this happen the United States and Russia should join with the UK and other interested states in creating a sustained, full-scale research and development program for verification at their respective nuc1ear weapons and defense establishments. The goals include development of effective technologies and procedures for: (1) Attribute measurement systems to certify nuclear warheads and military fissile materials; (2) Chain-of-custody methods to track items after they are authenticated and enter accountability; (3) Transportation monitoring; (4) Storage monitoring; (5) Fissile materials conversion verification. The remainder of this paper focuses on transparency and verification for nuclear arms a

Doyle, James E [Los Alamos National Laboratory; Meek, Elizabeth [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Magnetic Quantum-Phase Control between Two Entangled Macroscopic Nuclear Ensembles  

E-Print Network [OSTI]

Heralded generation and manipulation of quantum entanglement between two macroscopic and spatially separated crystals at room temperature is theoretically studied. We show that by combining an x-ray parametric down-conversion source and x-ray interferometry with nuclear resonant scattering techniques, two macroscopic crystals hosting M\\"ossbauer nuclei located each on an interferometer arm can be entangled for few tens of nanoseconds. The coherence time of the entanglement state can be prolonged up to values comparable to the lifetime of a single nuclear excited state, on the order of hundred nanoseconds. A non-mechanical magnetic control of the quantum phase between the two spatially separated entangled nuclear crystals is put forward.

Wen-Te Liao; Christoph H. Keitel; Adriana Plffy

2014-07-11T23:59:59.000Z

182

The NV center as a quantum actuator: time-optimal control of nuclear spins  

E-Print Network [OSTI]

Indirect control of qubits by a quantum actuator has been proposed as an appealing strategy to manipulate qubits that couple only weakly to external fields. While universal quantum control can be easily achieved when the actuator-qubit coupling is anisotropic, the efficiency of this approach is less clear. Here we analyze the time-efficiency of the quantum actuator control. We describe a strategy to find time-optimal control sequence by the quantum actuator and compare their gate times with direct driving, identifying regimes where the actuator control performs faster. As an example, we focus on a specific implementation based on the Nitrogen-Vacancy center electronic spin in diamond (the actuator) and nearby carbon-13 nuclear spins (the qubits).

Clarice D. Aiello; Paola Cappellaro

2014-10-21T23:59:59.000Z

183

The trend of digital control system design for nuclear power plants in Korea  

SciTech Connect (OSTI)

Currently there are 20 nuclear power plants (NPPs) in operation, and 6 more units are under construction in Korea. The control systems of those NPPs have also been developed together with the technology advancement. Control systems started with On-Off control using the relay logic, had been evolved into Solid-State logic using TTL ICs, and applied with the micro-processors since the Yonggwang NPP Units 3 and 4 which started its construction in 1989. Multiplexers are also installed at the local plant areas to collect field input and to send output signals while communicating with the controllers located in the system cabinets near the main control room in order to reduce the field wiring cables. The design of the digital control system technology for the NPPs in Korea has been optimized to maximize the operability as well as the safety through the design, construction, start-up and operation experiences. Both Shin-Kori Units 1 and 2 and Shin-Wolsong Units 1 and 2 NPP projects under construction are being progressed at the same time. Digital Plant Control Systems of these projects have adopted multi-loop controllers, redundant loop configuration, and soft control system for the radwaste system. Programmable Logic Controller (PLC) and Distributed Control System (DCS) are applied with soft control system in Shin-Kori Units 3 and 4. This paper describes the evolvement of control system at the NPPs in Korea and the experience and design improvement through the observation of the latest failure of the digital control system. In addition, design concept and its trend of the digital control system being applied to the NPP in Korea are introduced. (authors)

Park, S. H.; Jung, H. Y.; Yang, C. Y.; Choe, I. N. [Korea Power Engineering Company, 360-9 Mabuk-Dong, Yongin-Si, Gyeonggi-Do, 446-713 (Korea, Republic of)

2006-07-01T23:59:59.000Z

184

Field control of single x-ray photons in nuclear forward scattering  

E-Print Network [OSTI]

Means to coherently control single x-ray photons in resonant scattering of light off nuclei by electric or magnetic fields are investigated theoretically. In order to derive the time response in nuclear forward scattering, we adapt the Maxwell-Bloch equations known from quantum optics to describe the resonant light pulse propagation through a nuclear medium. Two types of time-dependent perturbations of nuclear forward scattering are considered for coherent control of the resonantly scattered x-ray quanta. First, the simultaneous coherent propagation of two pulses through the nuclear sample is addressed. We find that the signal of a weak pulse can be enhanced or suppressed by a stronger pulse simultaneously propagating through the sample in counter-propagating geometry. Second, the effect of a time-dependent hyperfine splitting is investigated and we put forward a scheme that allows parts of the spectrum to be shifted forward in time. This is the inverse effect of coherent photon storage and may become a valuable technique if single x-ray photon wavepackets are to become the information carriers in future photonic circuits.

Xiangjin Kong; Wen-Te Liao; Adriana Plffy

2014-04-09T23:59:59.000Z

185

Production of an English/Russian glossary of terminology for nuclear materials control and accounting  

SciTech Connect (OSTI)

The program plans for Former Soviet Union National Nuclear Materials Control and Accounting (MC and A) Systems Enhancements call for the development of an English/Russian Glossary of MC and A terminology. This glossary was envisioned as an outgrowth of the many interactions, training sessions, and other talking and writing exercises that would transpire in the course of carrying out these programs. This report summarizes the status of the production of this glossary, the most recent copy of which is attached to this report. The glossary contains over 950 terms and acronyms associated with nuclear material control and accounting for safeguards and nonproliferation. This document is organized as follows: English/Russian glossary of terms and acronyms; Russian/English glossary of terms and acronyms; English/Russian glossary of acronyms; and Russian/English glossary of acronyms.

Schachowskoj, S.; Smith, H.A. Jr.

1995-05-01T23:59:59.000Z

186

Review of Methods Related to Assessing Human Performance in Nuclear Power Plant Control Room Simulations  

SciTech Connect (OSTI)

With the increased use of digital systems in Nuclear Power Plant (NPP) control rooms comes a need to thoroughly understand the human performance issues associated with digital systems. A common way to evaluate human performance is to test operators and crews in NPP control room simulators. However, it is often challenging to characterize human performance in meaningful ways when measuring performance in NPP control room simulations. A review of the literature in NPP simulator studies reveals a variety of ways to measure human performance in NPP control room simulations including direct observation, automated computer logging, recordings from physiological equipment, self-report techniques, protocol analysis and structured debriefs, and application of model-based evaluation. These methods and the particular measures used are summarized and evaluated.

Katya L Le Blanc; Ronald L Boring; David I Gertman

2001-11-01T23:59:59.000Z

187

Application of fuzzy logic in nuclear reactor control Part I: An assessment of state-of-the-art  

SciTech Connect (OSTI)

This article discusses the application of fuzzy logic to nuclear reactor control. The method has been suggested by many investigators in many control applications. Reviews of the application of fuzzy logic in process control are given by Tong and Sugeno. Because fuzzy logic control (FLC) provides a pathway for transforming human abstractions into the numerical domain, it has the potential to assist nuclear reactor operators in the control room. With this transformation, linguistically expressed control principles can be coded into the fuzzy controller rule base. Having acquired the skill of the operators, the FLC can assist an operator in controlling the complex system. The thrust of FLC is to derive a conceptual model of the control operation, without expressing the process as mathematical equations, to assist the human operator in interpreting incoming plant variables and arriving at a proper control action. To introduce the concept of FLC in nuclear reactor operation, an overview of the mythology and a review of its application in both nuclear and nonnuclear control application domains are presented along with subsequent discussion of fuzzy logic controllers, their structures, and their method of information processing. The article concludes with the application of a tunable FLC to a typical reactor control problem.

Herger, A.S.; Jamshidl, M. [Univ. of New Mexico, Albuquerque, NM (United States); Alang-Rashid, N.K. [Malaysian Institute for Nuclear Technology Research, Bangi (Malaysia)

1995-10-01T23:59:59.000Z

188

Application of fuzzy logic in nuclear reactor control: Part 1: An assessment of state-of-the-art  

SciTech Connect (OSTI)

This article discusses the application of fuzzy logic of nuclear reactor control. The method has been suggested by many investigators in many control applications. Reviews of the application of fuzzy logic in process control are given by Tong and Sugeno. Because fuzzy logic control (FLC) provides a pathway for transforming human abstractions into the numerical domain, it has the potential to assist nuclear reactor operators in the control room. With this transformation, linguistically expressed control principles can be coded into the fuzzy controller rule base. Having acquired the skill of he operators, the FLC can assist an operator in controlling the complex system. The thrust of FLC is to derive a conceptual model of the control operation, without expressing the process as mathematical equations, to assist the human operator in interpreting incoming plant variables and arriving at a proper control action. To introduce the concept of FLC in nuclear reactor operation, an overview of the mythology and a review of its application in both nuclear and nonnuclear control application domains are presented along with subsequent discussion of fuzzy logic controllers, their structures, and their method of information processing. The article concludes with the application of a tunable FLC to a typical reactor control problem. 49 refs., 9 figs., 3 tabs.

Heger, A.S.; Alang-Rashid, N.K.; Jamshidi, M. [Univ. of New Mexico, Albuquerque, NM (United States)

1995-01-01T23:59:59.000Z

189

INDUSTRIAL CONTROL SYSTEM CYBER SECURITY: QUESTIONS AND ANSWERS RELEVANT TO NUCLEAR FACILITIES, SAFEGUARDS AND SECURITY  

SciTech Connect (OSTI)

Typical questions surrounding industrial control system (ICS) cyber security always lead back to: What could a cyber attack do to my system(s) and; how much should I worry about it? These two leading questions represent only a fraction of questions asked when discussing cyber security as it applies to any program, company, business, or organization. The intent of this paper is to open a dialog of important pertinent questions and answers that managers of nuclear facilities engaged in nuclear facility security and safeguards should examine, i.e., what questions should be asked; and how do the answers affect an organization's ability to effectively safeguard and secure nuclear material. When a cyber intrusion is reported, what does that mean? Can an intrusion be detected or go un-noticed? Are nuclear security or safeguards systems potentially vulnerable? What about the digital systems employed in process monitoring, and international safeguards? Organizations expend considerable efforts to ensure that their facilities can maintain continuity of operations against physical threats. However, cyber threats particularly on ICSs may not be well known or understood, and often do not receive adequate attention. With the disclosure of the Stuxnet virus that has recently attacked nuclear infrastructure, many organizations have recognized the need for an urgent interest in cyber attacks and defenses against them. Several questions arise including discussions about the insider threat, adequate cyber protections, program readiness, encryption, and many more. These questions, among others, are discussed so as to raise the awareness and shed light on ways to protect nuclear facilities and materials against such attacks.

Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

2011-07-01T23:59:59.000Z

190

2014 HEADQUARTERS FACILITIES MASTER SECURITY PLAN - CHAPTER 13...  

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

Official Use Only (OUO) and its subcategories of Personally Identifiable Information (PII) and Export Controlled Information (ECI), Unclassified Controlled Nuclear Information...

191

Abstract. The problem of controlled nuclear fusion (CNF) is a colossal scientific and technological challenge on a global  

E-Print Network [OSTI]

Abstract. The problem of controlled nuclear fusion (CNF) is a colossal scientific and technological the feasibility of building a magnetic thermonuclear reactor''. The three papers below briefly outline the history044n08ABEH001068 The initial period in the history of nuclear fusion research at the Kurchatov

192

International Nuclear Fuel Cycle Fact Book  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECN/NEA activities reports; not reflect any one single source but frequently represent a consolidation/combination of information.

Leigh, I.W.; Patridge, M.D.

1991-05-01T23:59:59.000Z

193

Spent Nuclear Fuel Project document control and Records Management Program Description  

SciTech Connect (OSTI)

The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document.

MARTIN, B.M.

2000-05-18T23:59:59.000Z

194

Chemistry-nuclear chemistry division. Progress report, October 1979-September 1980  

SciTech Connect (OSTI)

This report presents the research and development programs pursued by the Chemistry-Nuclear Chemistry Division of the Los Alamos National Laboratory. Topics covered include advanced analytical methods, atmospheric chemistry and transport, biochemistry, biomedical research, element migration and fixation, inorganic chemistry, isotope separation and analysis, atomic and molecular collisions, molecular spectroscopy, muonic x rays, nuclear cosmochemistry, nuclear structure and reactions, radiochemical separations, theoretical chemistry, and unclassified weapons research.

Ryan, R.R. (comp.)

1981-05-01T23:59:59.000Z

195

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

SciTech Connect (OSTI)

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

196

Control rod worth and related nuclear characteristics of an axially heterogeneous liquidmetal fast breeder reactor core  

SciTech Connect (OSTI)

An axially heterogeneous core (AHC) concept is applied to a 1000-MW(electric)-class tank-type liquidmetal fast breeder reactor (LMFBR). This AHC is characterized by a disk-shaped internal blanket with a radial thickness adjustment at the core midplane. The nuclear characteristics connected with control rod worth of the AHC are analyzed and compared with those of a homogeneous core (HOC) of the same power rating. The neutronics analysis shows that the reactivity insertion due to the vertical displacement of control rods relative to the core, which is an important safety characteristic of a tank-type LMFBR core, is significantly decreased in the AHC because of the reduced control worth requirement and smaller peakto-average differential worth in the primary control system. This allows the AHC to have a vertical displacement 50% greater than that of the HOC and may offer less rigid design conditions for roof slab stiffness and core support systems in a tank-type LMFBR. A reduction in the number of primary control rods is also possible because of a smaller control worth requirement and a better power peaking factor. The work was sponsored by a federation of Japanese electric power companies and performed under the guidance of the fast breeder reactor project office.

Kawashima, K.; Inayaki, T.; Inoue, K.; Kaneto, K.

1985-08-01T23:59:59.000Z

197

The applicability of sample collection and analysis in support of nuclear arms control agreements  

SciTech Connect (OSTI)

Agreements are being negotiated to halt the spread of nuclear arms both within the declared nuclear weapons states and to states not heretofore declaring their possession. With the verification regime of the recently negotiated Chemical Weapons Convention (CWC) as a model, negotiators are considering variations of on-site inspection as formulas to enhance the assurance of compliance with future agreements. These on-site inspections may be part of a treaty dictated verification regime or one of a set of voluntary {open_quotes}confidence building{close_quotes} measures. In either case, the collection of material samples for analysis could be an integral component of the inspection as it is in the CWC. The following is an assessment of the applicability of sampling and analysis for compliance monitoring nuclear arms control agreements currently envisioned. There are two essentially orthogonal ways of approaching this question of applicability: the consideration of the analytical questions and the consideration of the specifics of the individual agreements. This study is meant to utilize both approaches in examining the possible impact of sampling and analysis on compliance assessment. First attention must be given to technical questions relating to the efficacy of sampling and analysis.

McGuire, R.R.

1995-08-01T23:59:59.000Z

198

Method and means for remote removal of guide balls from nuclear reactor control rods  

SciTech Connect (OSTI)

This patent describes a method of remotely removing guide balls from nuclear reactor control rods using a punch mechanism, comprising: (a) providing attachment means in the punch mechanism for attaching the punch mechanism to means for reversibly lowering the punch mechanism over the top of one of the control rods; (b) providing a die within the punch mechanism; (c) providing cylinder means within the punch mechanism operatively connected to the die for axially moving the die in a back-and-forth direction; (d) providing a die block within the punch mechanism cooperating with the die; (e) providing guide means within the punch mechanism for self-aligning the punch mechanism so that the die and the die block are automatically aligned with a first one of the guide balls therebetween when the punch mechanism is lowered over the top of the control rod; (f) lowering the punch mechanism over the control rod so that the die, the die block, and the first guide ball are in alignment; and (g) then operating the cylinder means so that the die advances into the die block, thereby removing the first guide ball from the control rod.

Krieg, A.H.

1988-11-29T23:59:59.000Z

199

Gain margin and phase margin analysis of a nuclear reactor control system with multiple transport lags  

SciTech Connect (OSTI)

In this paper a method for finding the boundaries of constant gain margin and phase margin of control systems with transport lags and adjustable parameters is presented. The considered systems are first modified by adding a gain-phase margin tester, then the characteristic equations are formulated, and finally the stability equations are used to find the boundaries of constant gain margin and phase margin. The main advantage of the proposed method is to obtain complete information about the effects of adjustable parameters on gain margin and phase margin and their corresponding crossover frequencies. In order to show the usefulness of the proposed method a nuclear reactor control system with multiple transport lags is chosen as one of the examples.

Chang, C.H. (Institute of Electronics, National Chiao-Tung Univ. (TW)); Han, K.W. (Chung-Shan Institute and National Chiao-Tung Univ., Hsinchu (TW))

1989-08-01T23:59:59.000Z

200

Digital control systems in nuclear power plants: Failure information, modeling concepts, and applications. Revision 1  

SciTech Connect (OSTI)

This report briefly describes some current applications of advanced computerized digital display and control systems at US commercial nuclear power plants and presents the results of a literature search that was made to gather information on the reliability of these systems. Both hardware and software reliability were addressed in this review. Only limited failure rate information was found, with the chemical process industry being the primary source of information on hardware failure rates and expert opinion the primary source for software failure rates. Safety-grade digital control systems are typically installed on a functional like-for-like basis, replacing older analog systems without substantially changing interactions with other plant systems. Future work includes performing a limited probabilistic risk assessment of a representative DCS to assess its risk significance.

Galyean, W.J.

1993-06-23T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Digital control systems in nuclear power plants: Failure information, modeling concepts, and applications  

SciTech Connect (OSTI)

This report briefly describes some current applications of advanced computerized digital display and control systems at US commercial nuclear power plants and presents the results of a literature search that was made to gather information on the reliability of these systems. Both hardware and software reliability were addressed in this review. Only limited failure rate information was found, with the chemical process industry being the primary source of information on hardware failure rates and expert opinion the primary source for software failure rates. Safety-grade digital control systems are typically installed on a functional like-for-like basis, replacing older analog systems without substantially changing interactions with other plant systems. Future work includes performing a limited probabilistic risk assessment of a representative DCS to assess its risk significance.

Galyean, W.J.

1993-06-23T23:59:59.000Z

202

Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities  

SciTech Connect (OSTI)

The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work tasks, may have a failure rate of 1.0E-3 or higher (Gertman, 1996). With between 10,000 and 45,000 subtasks being performed during an outage (Gomes, 1996), the opportunity for human error of some consequence is a realistic concern. Although a number of factors exist that can make these errors recoverable, reducing and effectively coordinating the sheer number of tasks to be performed, particularly those that are error prone, has the potential to enhance outage efficiency and safety. Additionally, outage management requires precise coordination of work groups that do not always share similar objectives. Outage managers are concerned with schedule and cost, union workers are concerned with performing work that is commensurate with their trade, and support functions (safety, quality assurance, and radiological controls, etc.) are concerned with performing the work within the plants controls and procedures. Approaches to outage management should be designed to increase the active participation of work groups and managers in making decisions that closed the gap between competing objectives and the potential for error and process inefficiency.

Gregory Weatherby

2012-05-01T23:59:59.000Z

203

Four pin mounting system for nuclear reactor control rod guide tubes  

SciTech Connect (OSTI)

This paper describes a nuclear reactor having a control rod guide tube and an upper core plate, a pin-type mounting system for removably mounting the lower flange of a control rod guide tube over an opening in the upper core plate. It comprises: a pair of resilient pin members formed of stainless steel, mounted in passages formed through first opposing sides of the guide tube lower flange and resiliently and slidably receivable in a first pair of opposing bores formed on first opposing sides of the opening in the upper core plate to permit deflection thereof when the guide tube is subject to the usual shear loads associated with the operation of the nuclear reactor, the resilient pin members bearing substantially all of the usual shear load to which the guide tube is subjected. A paid of reinforcing pin members formed to stainless steel mounted on second opposing sides of the guide tube lower flange and slidably receivable in a second pair of bores formed on second opposing sides of the opening in the upper core plate.

Balog, L.J.; Boyle, D.E.

1990-06-26T23:59:59.000Z

204

Simulation-based expert system for nuclear reactor control and diagnostics. Progress report  

SciTech Connect (OSTI)

This research concerns the development of artificial intelligence (AI) techniques suitable for application to the diagnostics and control of nuclear power plant systems. The overall objective of the current effort is to build a prototype simulation-based expert system for diagnosing accidents in nuclear reactors. The system is being designed to analyze plant data heuristically using fuzzy logic to form a set of hypotheses about a particular transient. Hypothesis testing, fault magnitude estimation and transient analysis is performed using simulation programs to model plant behavior. An adaptive learning technique has been developed for achieving accurate simulations of plant dynamics using low-order physical models of plant components. The results of the diagnostics and simulation analysis of the plant transient are to be analyzed by an expert system for final diagnoses and control guidance. To date, significant progress has been made toward achieving the primary goals of this project. Based on a critical safety functions approach, an overall design for the nuclear plant expert system has been developed. The methodology for performing diagnostic reasoning on plant signals has been developed and the algorithms implemented and tested. A methodology for utilizing the information contained in the physical models of plant components has also been developed. This work included the derivation of a unique Kalman filtering algorithm for using power plant data to systematically improve on-line simulations through the judicious adjustment of key model parameters. A few simulation models of key plant components have been developed and implemented to demonstrate the method on a realistic accident scenario. The chosen transient is a loss of feed flow exasperated by a stuck open relief valve, similar to the initiating event of the Three Mile Island Unit 2 accident in 1979.

Lee, J.C.; Martin, W.R.

1986-07-31T23:59:59.000Z

205

Nuclear reactors built, being built, or planned 1992  

SciTech Connect (OSTI)

Nuclear Reactors Built, Being Built, or Planned contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1992. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US and foreign embassies; and from foreign governmental nuclear departments. Information is presented on five parts: Civilian, Production, Military, Export and Critical Assembly.

Not Available

1993-07-01T23:59:59.000Z

206

Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability  

SciTech Connect (OSTI)

The U.S. Department of Energys Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

2013-03-01T23:59:59.000Z

207

Unclassified Sources Term and Radionuclide Data for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada Test Site, Nevada, Revision 2  

SciTech Connect (OSTI)

This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for CAU 97: Yucca Flat/Climax Mine. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. The hydrologic source term (HST) of an underground nuclear test is the portion of the total RST that is released into the groundwater over time following the test. In this report, the HST represents radionuclide release some time after the explosion and does not include the rapidly evolving mechanical, thermal, and chemical processes during the explosion. The CAU 97: Yucca Flat/Climax Mine has many more detonations and a wider variety of settings to consider compared to other CAUs. For instance, the source term analysis and evaluation performed for CAUs 101 and 102: Central and Western Pahute Mesa and CAU 98: Frenchman Flat did not consider vadose zone attenuation because many detonations were located near or below the water table. However, the large number of Yucca Flat/Climax Mine tests and the location of many tests above the water table warrant a more robust analysis of the unsaturated zone. The purpose of this report is to develop and document conceptual models of the Yucca Flat/Climax Mine HST for use in implementing source terms for the Yucca Flat/Climax Mine models. This document presents future plans to incorporate the radionuclide attenuation mechanisms due to unsaturated/multiphase flow and transport within the Yucca Flat CAU scale modeling. The important processes that influence radionuclide migration for the unsaturated and saturated tests in alluvial, volcanic, and carbonate settings are identified. Many different flow and transport models developed by Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL), including original modeling of multiphase flow and transport by the Stoller-Navarro Joint Venture (SNJV), are integrated to form a general understanding of how the RST relates to the HST. This report is unlike the Frenchman Flat source term analysis because it does not calculate the HST for each test. Instead, this work only identifies the important processes that must be considered when the CAU-transport modeling is performed.

Peter Martian

2009-08-01T23:59:59.000Z

208

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall  

SciTech Connect (OSTI)

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.

Michael R. Kruzic

2007-09-16T23:59:59.000Z

209

Reactor control system upgrade for the McClellan Nuclear Radiation Center Sacramento, CA.  

SciTech Connect (OSTI)

Argonne National Laboratory is currently developing a new reactor control system for the McClellan Nuclear Radiation Facility. This new control system not only provides the same functionality as the existing control system in terms of graphic displays of reactor process variables, data archival capability, and manual, automatic, pulse and square-wave modes of operation, but adds to the functionality of the previous control system by incorporating signal processing algorithms for the validation of sensors and automatic calibration and verification of control rod worth curves. With the inclusion of these automated features, the intent of this control system is not to replace the operator but to make the process of controlling the reactor easier and safer for the operator. For instance, an automatic control rod calibration method reduces the amount of time to calibrate control rods from days to minutes, increasing overall reactor utilization. The control rod calibration curve, determined using the automatic calibration system, can be validated anytime after the calibration, as long as the reactor power is between 50W and 500W. This is done by banking all of the rods simultaneously and comparing the tabulated rod worth curves with a reactivity computer estimate. As long as the deviation between the tabulated values and the reactivity estimate is within a prescribed error band, then the system is in calibration. In order to minimize the amount of information displayed, only the essential flux-related data are displayed in graphical format on the control screen. Information from the sensor validation methods is communicated to the operators via messages, which appear in a message window. The messages inform the operators that the actual process variables do not correlate within the allowed uncertainty in the reactor system. These warnings, however, cannot cause the reactor to shutdown automatically. The reactor operator has the ultimate responsibility of using this information to either keep the reactor operating or to shut the reactor down. In addition to new developments in the signal processing realm, the new control system will be migrating from a PC-based computer platform to a Sun Solaris-based computer platform. The proven history of stability and performance of the Sun Sohuis operating system are the main advantages to this change. The I/O system will also be migrating from a PC-based data collection system, which communicates plant data to the control computer using RS-232 connections, to an Ethernet-based I/O system. The Ethernet Data Acquisition System (EDAS) modules from Intelligent Instrumentation, Inc. provide an excellent solution for embedded control of a system using the more universally-accepted data transmission standard of TCP/IP. The modules contain a PROM, which operates all of the functionality of the I/O module, including the TCP/IP network access. Thus the module does not have an internal, sophisticated operating system to provide functionality but rather a small set hard-coded of instructions, which almost eliminates the possibility of the module failing due to software problems. An internal EEPROM can be modified over the Internet to change module configurations. Once configured, the module is contacted just like any other Internet host using TCP/IP socket calls. The main advantage to this architecture is its flexibility, expandability, and high throughput.

Power, M. A.

1999-03-10T23:59:59.000Z

210

A virtual control room with an embedded, interactive nuclear reactor simulator  

SciTech Connect (OSTI)

The use of virtual nuclear control room can be an effective and powerful tool for training personnel working in the nuclear power plants. Operators could experience and simulate the functioning of the plant, even in critical situations, without being in a real power plant or running any risk. 3D models can be exported to Virtual Reality formats and then displayed in the Virtual Reality environment providing an immersive 3D experience. However, two major limitations of this approach are that 3D models exhibit static textures, and they are not fully interactive and therefore cannot be used effectively in training personnel. In this paper we first describe a possible solution for embedding the output of a computer application in a 3D virtual scene, coupling real-world applications and VR systems. The VR system reported here grabs the output of an application running on an X server; creates a texture with the output and then displays it on a screen or a wall in the virtual reality environment. We then propose a simple model for providing interaction between the user in the VR system and the running simulator. This approach is based on the use of internet-based application that can be commanded by a laptop or tablet-pc added to the virtual environment. (authors)

Markidis, S.; Rizwan, U. [Dept. of Nuclear, Plasma, and Radiological Engineering, Univ. of Illinois, Urbana, IL 61801 (United States)

2006-07-01T23:59:59.000Z

211

REVIEW Of COMPUTERIZED PROCEDURE GUIDELINES FOR NUCLEAR POWER PLANT CONTROL ROOMS  

SciTech Connect (OSTI)

Computerized procedures (CPs) are recognized as an emerging alternative to paper-based procedures for supporting control room operators in nuclear power plants undergoing life extension and in the concept of operations for advanced reactor designs. CPs potentially reduce operator workload, yield increases in efficiency, and provide for greater resilience. Yet, CPs may also adversely impact human and plant performance if not designed and implemented properly. Therefore, it is important to ensure that existing guidance is sufficient to provide for proper implementation and monitoring of CPs. In this paper, human performance issues were identified based on a review of the behavioral science literature, research on computerized procedures in nuclear and other industries, and a review of industry experience with CPs. The review of human performance issues led to the identification of a number of technical gaps in available guidance sources. To address some of the gaps, we developed 13 supplemental guidelines to support design and safety. This paper presents these guidelines and the case for further research.

David I Gertman; Katya Le Blanc; Ronald L Boring

2011-09-01T23:59:59.000Z

212

Using micro saint to predict performance in a nuclear power plant control room  

SciTech Connect (OSTI)

The United States Nuclear Regulatory Commission (NRC) requires a technical basis for regulatory actions. In the area of human factors, one possible technical basis is human performance modeling technology including task network modeling. This study assessed the feasibility and validity of task network modeling to predict the performance of control room crews. Task network models were built that matched the experimental conditions of a study on computerized procedures that was conducted at North Carolina State University. The data from the {open_quotes}paper procedures{close_quotes} conditions were used to calibrate the task network models. Then, the models were manipulated to reflect expected changes when computerized procedures were used. These models` predictions were then compared to the experimental data from the {open_quotes}computerized conditions{close_quotes} of the North Carolina State University study. Analyses indicated that the models predicted some subsets of the data well, but not all. Implications for the use of task network modeling are discussed.

Lawless, M.T.; Laughery, K.R. [Micro Analysis and Design, Inc., Boulder, CO (United States); Persenky, J.J. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-09-01T23:59:59.000Z

213

Annual report on strategic special nuclear material inventory differences, April 1, 1990--March 31, 1991  

SciTech Connect (OSTI)

This report of unclassified Inventory Difference (ID's) covers the twelve months from April 1, 1990 through March 31, 1991 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses as the included data.

Not Available

1992-01-01T23:59:59.000Z

214

Unclassified Source Term and Radionuclide Data for the Groundwater Flow and Contaminant Transport Model of Corrective Action Units 101 and 102: Central and Western Pahute Mesa, Nye County, Nevada, Revision 0  

SciTech Connect (OSTI)

This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for Central and Western Pahute Mesa: Corrective Action Units (CAUs) 101 and 102.

McCord, John

2004-08-01T23:59:59.000Z

215

International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings  

SciTech Connect (OSTI)

This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

Not Available

1984-06-01T23:59:59.000Z

216

International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings  

SciTech Connect (OSTI)

This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held June 3 through June 21, 1985, at Santa Fe and Los Alamos, New Mexico, and San Clemente, California. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the Course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1985 course was placed on safeguards methods used at item-control facilities, particularly nuclear power generating stations and test reactors. An introduction to safeguards methods used at bulk handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants, was also included. The course was conducted by the University of California's Los Alamos National Laboratory and the Southern California Edison Company. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the San Onofre Nuclear Generating Station, San Clemente, California.

Not Available

1986-06-01T23:59:59.000Z

217

U.S. Seafood Safe and Unaffected by Radiation Contamination from Japanese Nuclear Power Plant Incident; U.S. Monitoring Control Strategy Explained  

E-Print Network [OSTI]

U.S. Seafood Safe and Unaffected by Radiation Contamination from Japanese Nuclear Power Plant about radiation contamination from the Japanese nuclear power plant incident and on the control potential routes by which seafood contaminated with radionuclides from the Japanese nuclear power plant

218

Redundant Sensor Calibration and Estimation for Monitoring and Control of Nuclear Power Plants Xin Jin, Asok Ray and Robert M. Edwards  

E-Print Network [OSTI]

Redundant Sensor Calibration and Estimation for Monitoring and Control of Nuclear Power Plants Xin@engr.psu.edu INTRODUCTION Performance, reliability and safety of nuclear power plants depend upon validity and accuracy are installed with redundancy in nuclear power plants. Redundancy can be classified into two groups: direct

Ray, Asok

219

An Integrated Scheme for Anomaly Identification and Automatic Control of Nuclear Power Plants Xin Jin, Robert M. Edwards and Asok Ray  

E-Print Network [OSTI]

An Integrated Scheme for Anomaly Identification and Automatic Control of Nuclear Power Plants Xin.edu INTRODUCTION Nuclear Power Plants (NPPs) are complex systems with many variables that require adjustment Jin, Robert M. Edwards and Asok Ray Department of Mechanical and Nuclear Engineering, The Pennsylvania

Ray, Asok

220

Standard guide for application of radiation monitors to the control and physical security of special nuclear material  

E-Print Network [OSTI]

1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

American Society for Testing and Materials. Philadelphia

1999-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Chemistry-Nuclear Chemistry Division. Progress report, October 1980-September 1981  

SciTech Connect (OSTI)

This report describes major progress in the research and development programs pursued by the Chemistry-Nuclear Chemistry Division of the Los Alamos National Laboratory during FY 1981. Topics covered include advanced analytical methods, atmospheric chemistry and transport, biochemistry, biomedical research, medical radioisotopes research, element migration and fixation, nuclear waste isolation research, inorganic and structural chemistry, isotope separation, analysis and applications, the newly established Nuclear Magnetic Resonance Center, atomic and molecular collisions, molecular spectroscopy, nuclear cosmochemistry, nuclear structure and reactions, pion charge exchange, radiochemical separations, theoretical chemistry, and unclassified weapons research.

Ryan, R.R. (comp.)

1982-05-01T23:59:59.000Z

222

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall  

SciTech Connect (OSTI)

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100 centimeters squared (cm2) beta/gamma. Removable beta/gamma contamination levels seldom exceeded 1,000 dpm/100 cm2, but, in railroad trenches on the reactor pad containing soil on the concrete pad in front of the shield wall, the beta dose rates ranged up to 120 milli-roentgens per hour from radioactivity entrained in the soil. General area dose rates were less than 100 micro-roentgens per hour. Prior to demolition of the reactor shield wall, removable and fixed contaminated surfaces were decontaminated to the best extent possible, using traditional decontamination methods. Fifth, large sections of the remaining structures were demolished by mechanical and open-air controlled explosive demolition (CED). Mechanical demolition methods included the use of conventional demolition equipment for removal of three main buildings, an exhaust stack, and a mobile shed. The 5-foot (ft), 5-inch (in.) thick, neutron-activated reinforced concrete shield was demolished by CED, which had never been performed at the NTS.

Michael R. Kruzic

2008-06-01T23:59:59.000Z

223

DOE/DHS INDUSTRIAL CONTROL SYSTEM CYBER SECURITY PROGRAMS: A MODEL FOR USE IN NUCLEAR FACILITY SAFEGUARDS AND SECURITY  

SciTech Connect (OSTI)

Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is to provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.

Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

2011-07-01T23:59:59.000Z

224

RADIOACTIVE WASTE MANAGEMENT IN THE USSR: A REVIEW OF UNCLASSIFIED SOURCES, 1963-1990  

SciTech Connect (OSTI)

The Soviet Union operates a vast and growing radioactive waste management system. Detailed information on this system is rare and a general overall picture only emerges after a review of a great deal of literature. Poor waste management practices and slow implementation of environmental restoration activities have caused a great deal of national concern. The release of information on the cause and extent of an accident involving high-level waste at the Kyshtym production reactor site in 1957, as well as other contamination at the site, serve to highlight past Soviet waste management practices. As a result, the area of waste management is now receiving greater emphasis, and more public disclosures. Little is known about Soviet waste management practices related to uranium mining, conversion, and fuel fabrication processes. However, releases of radioactive material to the environment from uranium mining and milling operations, such as from mill tailings piles, are causing public concern. Official Soviet policy calls for a closed fuel cycle, with reprocessing of power reactor fuel that has been cooled for five years. For power reactors, only VVER-440 reactor fuel has been reprocessed in any significant amount, and a decision on the disposition of RBMK reactor fuel has been postponed indefinitely. Soviet reprocessing efforts are falling behind schedule; thus longer storage times for spent fuel will be required, primarily at multiple reactor stations. Information on reprocessing in the Soviet Union has been severely limited until 1989, when two reprocessing sites were acknowledged by the Soviets. A 400-metric ton (MT) per year reprocessing facility, located at Kyshtym, has been operational since 1949 for reprocessing production reactor fuel. This facility is reported to have been reprocessing VVER-440 and naval reactor fuel since 1978, with about 2000 MT of VVER-440 fuel being reprocessed by July 1989. A second facility, located near Krasnoyarsk and having a 1500 MT per year capacity as the first of several modules, was about 30% completed by July 1989. The completion of this plant was subsequently "indefinitely postponed." The initial reprocessing scheme at the Kyshtym site used sodium uranyl acetate precipitation from fuel dissolved in nitric acid solutions. The basic method~ ology now appears to be based on the conventional PUREX process. Dry reprocessing on a pilot or laboratory scale has been under way in Dimitrovgrad since 1984, and a larger unit is now being built, according to the French CEA. Perhaps significantly, much research is being done on partitioning high-level waste into element fractions. The Soviets appear to have the technology to remove radioactive noble gases released during reprocessing operations; however, there are no indications of its implementation. Millions of curies of liquid low- and intermediate-level wastes have been disposed of by well injection into underground areas where they were supposedly contained by watertight rock strata. Some gaseous wastes were also disposed of by well injection. This practice is not referred to in recent literature and thus may not be widely used today. Rather, it appears that these waste streams are now first treated to reduce volume, and then solidified using bitumen or concrete. These solidified liquid wastes from Soviet nuclear power reactor operations, along with solid wastes, are disposed of in shallow-land burial sites located at most large power reactor stations. In addition, 35 shallow-land burial sites have been alluded to by the Soviets for disposal of industrial, medical, and research low-level wastes as well as ionization sources. Research on tritium-bearing and other gaseous wastes is mentioned, as well as a waste minimization program aimed at reducing the volume of waste streams by 30%. The Soviets have announced that their high-level waste management plan is to 1) store liquid wastes for 3-5 years; 2) incorporate the waste into glass (at a final glass volume of 100-150 liters/MT of fuel reprocessed); 3) set it aside in air-cooled storage

Bradley, D. J.; Schneider, K. J.

1990-03-01T23:59:59.000Z

225

Evaluation of exposure limits to toxic gases for nuclear reactor control room operators  

SciTech Connect (OSTI)

We have evaluated ammonia, chlorine, Halon (actually a generic name for several halogenated hydro-carbons), and sulfur dioxide for their possible effects during an acute two-minute exposure in order to derive recommendations for maximum exposure levels. To perform this evaluation, we conducted a search to find the most pertinent literature regarding toxicity in humans and in experimental animals. Much of the literature is at least a decade old, not an unexpected finding since acute exposures are less often performed now than they were a few years ago. In most cases, the studies did not specifically examine the effects of two-minute exposures; thus, extrapolations had to be made from studies of longer-exposure periods. Whenever possible, we gave the greatest weight to human data, with experimental animal data serving to strengthen the conclusion arrived at from consideration of the human data. Although certain individuals show hypersensitivity to materials like sulfur dioxide, we have not attempted to factor this information into the recommendations. After our evaluation of the data in the literature, we held a small workshop. Major participants in this workshop were three consultants, all of whom were Diplomates of the American Board of Toxicology, and staff from the Nuclear Regulatory Commission. Our preliminary recommendations for two-minute exposure limits and the rationale for them were discussed and consensus reached on final recommendations. These recommendations are: (1) ammonia-300 to 400-ppm; (2) chlorine-30 ppm; (3) Halon 1301-5%; Halon 1211-2%; and (4) sulfur dioxide-100 ppm. Control room operators should be able to tolerate two-minute exposures to these levels, don fresh-air masks, and continue to operate the reactor if the toxic material is eliminated, or safely shut down the reactor if the toxic gas remains. 96 refs., 9 tabs.

Mahlum, D.D.; Sasser, L.B. (Pacific Northwest Lab., Richland, WA (United States))

1991-07-01T23:59:59.000Z

226

Qualification issues associated with the use of advanced instrumentation and control systems hardware in nuclear power plants  

SciTech Connect (OSTI)

The instrumentation and control (I&C) systems in advanced reactors will make extensive use of digital controls, microprocessors, multiplexing, and Tiber-optic transmission. Elements of these advances in I&C have been implemented on some current operating plants. However, the widespread use of the above technologies, as well as the use of artificial intelligence with minimum reliance on human operator control of reactors, highlights the need to develop standards for qualifying I&C used in the next generation of nuclear power plants. As a first step in this direction, the protection system I&C for present-day plants was compared to that proposed for advanced light water reactors (ALWRs). An evaluation template was developed by assembling a configuration of a safety channel instrument string for a generic ALWR, then comparing the impact of environmental stressors on that string to their effect on an equivalent instrument string from an existing light water reactor. The template was then used to address reliability issues for microprocessor-based protection systems. Standards (or lack thereof) for the qualification of microprocessor-based safety I&C systems were also identified. This approach addresses in part issues raised in Nuclear Regulatory Commission policy document SECY-91-292. which recognizes that advanced I&C systems for the nuclear industry are ``being developed without consensus standards, as the technology available for design is ahead of the technology that is well understood through experience and supported by application standards.``

Korsah, K. [Oak Ridge National Lab., TN (United States); Antonescu, C. [Nuclear Regulatory Commission, Rockville, MD (United States). Office of Nuclear Regulatory Research

1993-10-01T23:59:59.000Z

227

Isotope and Nuclear Chemistry Division annual report, FY 1983  

SciTech Connect (OSTI)

This report describes progress in the major research and development programs carried out in FY 1983 by the Isotope and Nuclear Chemistry Division. It covers radiochemical diagnostics of weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production, separation, and applications (including biomedical applications); element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced analytical techniques; development and applications; atmospheric chemistry and transport; and earth and planetary processes.

Heiken, J.H.; Lindberg, H.A. (eds.)

1984-05-01T23:59:59.000Z

228

Underground nuclear power station using self-regulating heat-pipe controlled reactors  

DOE Patents [OSTI]

A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

Hampel, Viktor E. (Pleasanton, CA)

1989-01-01T23:59:59.000Z

229

An underground nuclear power station using self-regulating heat-pipe controlled reactors  

DOE Patents [OSTI]

A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast- acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor. 5 figs.

Hampel, V.E.

1988-05-17T23:59:59.000Z

230

Validating real-time implementations of diagonal recurrent neural network and fuzzy logic controllers for nuclear reactor control  

SciTech Connect (OSTI)

A diagonal recurrent neural network (DRNN) and a fuzzy logic controller (FLC) were designed for optimal temperature control. The DRNN and FLC utilize the response of a fifth-order, one delayed neutron group linear model to an optimal controller that was previously designed. In this paper, the results of testing a real-time implementation of the DRNN and FLC are presented. The method of testing that was utilized is called hardware in loop simulation (HILS). Here, a distributed simulation of a highly non-linear model of the reactor on a network of workstations is used in the final step of testing prior to experimentation on the reactor. Also, in this setup actual control hardware is used to validate the controller realizations.

Ramaswamy, P.; Edwards, R.M.; Lee, K.Y.

1994-12-31T23:59:59.000Z

231

The Novel ''Controlled Intermediate Nuclear Fusion'' and its Possible Industrial Realization as Predicted by Hadronic Mechanics and Chemistry  

E-Print Network [OSTI]

In this note, we propose, apparently for the first time, a new type of controlled nuclear fusion called "intermediate" because occurring at energies intermediate between those of the ''cold'' and ''hot'' fusions, and propose a specific industrial realization. For this purpose: 1) We show that known limitations of quantum mechanics, quantum chemistry and special relativity cause excessive departures from the conditions occurring for all controlled fusions; 2) We outline the covering hadronic mechanics, hadronic chemistry and isorelativity specifically conceived, constructed and verified during the past two decades for new cleans energies and fuels; 3) We identify seven physical laws predicted by the latter disciplines that have to be verified by all controlled nuclear fusions to occur; 4) We review the industrial research conducted to date in the selection of the most promising engineering realization as well as optimization of said seven laws; and 5) We propose with construction details a specific {\\it hadronic reactor} (patented and international patents pending), consisting of actual equipment specifically intended for the possible industrial production of the clean energy released by representative cases of controlled intermediate fusions for independent scrutiny by interested colleagues.

Ruggero Maria Santilli

2006-02-17T23:59:59.000Z

232

UNCLASSIFIED Executive summary  

E-Print Network [OSTI]

used in the Time Domain Integral Equation method Problem area Improving stealth technology radar absorbing materials. In particular ferromagnetic materials can be utilised as a coating materials. Since nonlinear responses are expected, the method is fully formulated in the time domain

Vuik, Kees

233

Nuclear Instruments and Methods in Physics Research A 428 (1999) 593}607 Radio-controlled xenon #ashers for atmospheric monitoring  

E-Print Network [OSTI]

Nuclear Instruments and Methods in Physics Research A 428 (1999) 593}607 Radio-controlled xenon 84119, USA. Now at: University of Kansas, Department of Physics, Law- rence, KS 66045, USA. Now at: Wave

234

Controlling the atom. The beginnings of nuclear regulation 1946--1962  

SciTech Connect (OSTI)

This book traces the early history of nuclear power regulation in the US. It focuses on the Atomic Energy Commission (AEC), the federal agency that until 1975 was primarily responsible for planning and carrying out programs to protect public health and safety from the hazards of the civilian use of nuclear energy. It also describes the role of other groups that figured significantly in the development of regulatory policies, including the congressional Joint Committee on Atomic Energy, federal agencies other than the AEC, state governments, the nuclear industry, and scientific organizations. And it considers changes in public perceptions of and attitudes toward atomic energy and the dangers of radiation exposure. The context in which regulatory programs evolved is a rich and complex mixture of political, legislative, legal, technological, scientific, and administrative history. The basic purpose of this book is to provide the Nuclear Regulatory Commission (NRC), which inherited responsibility for nuclear safety after Congress disbanded the AEC, and the general public with information on the historical antecedents and background of regulatory issues.

Mazuzan, G.T.; Walker, J.S.

1997-08-01T23:59:59.000Z

235

Initial quantification of human error associated with specific instrumentation and control system components in licensed nuclear power plants  

SciTech Connect (OSTI)

This report provides a methodology for the initial quantification of specific categories of human errors made in conjunction with several instrumentation and control (I and C) system components operated, maintained, and tested in licensed nuclear power plants. The resultant human error rates (HER) provide the first real systems bases of comparison for the existing derived and/or best judgement equivalent set of such rates or probabilities. These calculated error rates also provide the first real indication of human performance as it relates directly to specific tasks in nuclear plants. This work of developing specific HERs is both an extension of and an outgrowth of the generic HERs developed for safety system pumpc and valves as reported in NUREG/CR-1880.

Luckas, W.J. Jr.; Lettieri, V.; Hall, R.E.

1982-02-01T23:59:59.000Z

236

Initial quantification of human error associated with specific instrumentation and control system components in licensed nuclear power plants  

SciTech Connect (OSTI)

This report provides a methodology for the initial quantification of specific categories of human errors made in conjunction with several instrumentation and control (I and C) system components operated, maintained, and tested in licensed nuclear power plants. The resultant human error rates (HER) provide the first real systems bases of comparison for the existing derived and/or best judgement equivalent set of such rates or probabilities. These calculated error rates also provide the first real indication of human performance as it relates directly to specific tasks in nuclear plants. This work of developing specific HERs is both an extension of and an outgrowth of the generic HERs developed for safety system pumps and valves as reported in NUREG/CR-1880.

Luckas, W.J. Jr.; Lettieri, V.; Hall, R.E.

1982-02-01T23:59:59.000Z

237

VALIDATION OF NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY (MC&A) SYSTEM EFFECTIVENESS TOOL (MSET) AT IDAHO NATIONAL LABORATORY (INL)  

SciTech Connect (OSTI)

A Nuclear Material Control and Accountability (MC&A) Functional Model has been developed to describe MC&A systems at facilities possessing Category I or II Special Nuclear Material (SNM). Emphasis is on achieving the objectives of 144 Fundamental Elements in key areas ranging from categorization of nuclear material to establishment of Material Balance Areas (MBAs), controlling access, performing quality measurements of inventories and transfers, timely reporting all activities, and detecting and investigating anomalies. An MC&A System Effectiveness Tool (MSET), including probabilistic risk assessment (PRA) technology for evaluating MC&A effectiveness and relative risk, has been developed to accompany the Functional Model. The functional model and MSET were introduced at the 48th annual International Nuclear Material Management (INMM) annual meeting in July, 20071,2. A survey/questionnaire is used to accumulate comprehensive data regarding the MC&A elements at a facility. Data is converted from the questionnaire to numerical values using the DELPHI method and exercises are conducted to evaluate the overall effectiveness of an MC&A system. In 2007 a peer review was conducted and a questionnaire was completed for a hypothetical facility and exercises were conducted. In the first quarter of 2008, a questionnaire was completed at Idaho National Laboratory (INL) and MSET exercises were conducted. The experience gained from conducting the MSET exercises at INL helped evaluate the completeness and consistency of the MC&A Functional Model, descriptions of fundamental elements of the MC&A Functional Model, relationship between the MC&A Functional Model and the MC&A PRA tool and usefulness of the MSET questionnaire data collection process.

Meppen, Bruce; Haga, Roger; Moedl, Kelley; Bean, Tom; Sanders, Jeff; Thom, Mary Alice

2008-07-01T23:59:59.000Z

238

International Nuclear Fuel Cycle Fact Book  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

Leigh, I.W.

1992-05-01T23:59:59.000Z

239

International Nuclear Fuel Cycle Fact Book  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information.

Leigh, I W; Mitchell, S J

1990-01-01T23:59:59.000Z

240

Application of Neutron-Absorbing Structural-Amorphous Metal (SAM) Coatings for Spent Nuclear Fuel (SNF) Container to Enhance Criticality Safety Control  

SciTech Connect (OSTI)

This report describes the analysis and modeling approaches used in the evaluation for criticality-control applications of the neutron-absorbing structural-amorphous metal (SAM) coatings. The applications of boron-containing high-performance corrosion-resistant material (HPCRM)--amorphous metal as the neutron-absorbing coatings to the metallic support structure can enhance criticality safety controls for spent nuclear fuel in baskets inside storage containers, transportation casks, and disposal containers. The use of these advanced iron-based, corrosion-resistant materials to prevent nuclear criticality in transportation, aging, and disposal containers would be extremely beneficial to the nuclear waste management programs.

Choi, J

2007-01-12T23:59:59.000Z

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


241

Isotope and Nuclear Chemistry Division annual report FY 1986, October 1985-September 1986  

SciTech Connect (OSTI)

This report describes progress in the major research and development programs carried out in FY 1986 by the Isotope and Nuclear Chemistry Division. The report includes articles on radiochemical diagnostics and weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production and separation; chemical biology and nuclear medicine; element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced concepts and technology; and atmospheric chemistry.

Heiken, J.H. (ed.)

1987-06-01T23:59:59.000Z

242

Radiation exposure and central nervous system cancers: A case-control study among workers at two nuclear facilities  

SciTech Connect (OSTI)

A nested case-control study was conducted among workers employed between 1943 and 1977 at two nuclear facilities to investigate the possible association of primary malignant neoplasms of the central nervous system (CNS) with occupational exposure to ionizing radiation from external and internal sources. Eighty-nine white male and female workers, who according to the information on death certificates dies of primary CNS cancers, were identified as cases. Four matched controls were selected for each case. External radiation exposure data were available from film badge readings for individual workers, whereas radiation dose to lung from internally deposited radionuclides, mainly uranium, was estimated from area and personnel monitoring data and was used in analyses in lieu of the dose to the brain. Matched sets were included in the analyses only if information was available for the case and at least one of the corresponding controls. Thus, the analyses of external radiation included 27 cases and 90 matched controls, and 47 cases and 120 matched controls were analyzed for the effects of radiation from internally deposited uranium. No association was observed between deaths fron CNS cancers and occupational exposure to ionizing radiation from external or internal sources. However, due to the small number of monitored subjects and low doses, a weak association could not be ruled out. 43 refs., 1 fig., 15 tabs.

Carpenter, A.V.; Flanders, W.D.; Frome, E.L.; Crawford-Brown, D.J.; Fry, S.A.

1987-03-01T23:59:59.000Z

243

Chemical exposures and central nervous system cancers: a case-control study among workers at two nuclear facilities  

SciTech Connect (OSTI)

In a nested case-control study of workers employed between 1943 and 1977 at two nuclear facilities, we evaluated the possible association of primary CNS cancers with occupational exposure to chemicals. Seventy-two white male and 17 white female workers who, according to the information on death certificates, died of primary CNS cancers were identified as cases. For each case, four controls were matched on race, sex, facility at which initially employed (cohort), year of birth, and year of hire. Each job title/department combination was subjectively evaluated for potential exposure to each of 26 chemicals or chemical groups. Statistically significant associations were not found between CNS cancer deaths and any of the 26 chemicals. An increased risk of CNS cancer occurrence was observed among subjects employed for more than 20 yr (OR = 7.0, 95% CI = 1.2,41.1, cases = 9).

Carpenter, A.V.; Flanders, W.D.; Frome, E.L.; Tankersley, W.G.; Fry, S.A.

1988-01-01T23:59:59.000Z

244

he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering (NSE) generate, control, and apply nuclear  

E-Print Network [OSTI]

T he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering and technology. Professor Richard K. Lester Head, Department of Nuclear Science & Engineering rklester contact Professor Richard K. Lester, Head Department of Nuclear Science & Engineering rklester

Polz, Martin

245

GKTC ACTIVITIES TO PROVIDE NUCLEAR MATERIAL PHYSICAL PROTECTION, CONTROL AND ACCOUNTING TRAINING FOR 2011-2012  

SciTech Connect (OSTI)

The GKTC was created at the Kyiv Institute of Nuclear Research as a result of collaborative efforts between the United States and Ukraine. The GKTC has been designated by the Ukrainian Government to provide the MPC&A training and methodological assistance to nuclear facilities and nuclear specialists. In 2010 the GKTC has conducted the planned assessment of training needs of Ukrainian MPC&A specialists. The objective of this work is to acquire the detailed information about the number of MPC&A specialists and guard personnel, who in the coming years should receive the further advanced training. As a result of the performed training needs evaluation the GKTC has determined that in the coming years a number of new training courses need to be developed. Some training courses are already in the process of development. Also taking into account the specific of activity on the guarding of nuclear facilities, GKTC has begun to develop the specialized training courses for the guarding unit personnel. The evaluation of needs of training of Ukrainian specialists on the physical protection shows that without the technical base of learning is not possible to satisfy the needs of Ukrainian facilities, in particular, the need for further training of specialists who maintains physical protection technical means, provides vulnerability assessment and testing of technical means. To increase the training effectiveness and create the basis for specialized training courses holding the GKTC is now working on the construction of an Interior (non-classified) Physical Protection Training Site. The objective of this site is to simulate the actual conditions of the nuclear facility PP system including the complex of engineering and technical means that will help the GKTC training course participants to consolidate the knowledge and gain the practical skills in the work with PP system engineering and technical means for more effective performance of their official duties. This paper briefly describes the practical efforts applied to the provision of physical protection specialists advanced training in Ukraine and real results on the way to implement such efforts in 2011-2012.

Romanova, Olena; Gavrilyuk, Victor I.; Kirischuk, Volodymyr; Gavrilyuk-Burakova, Anna; Diakov, Oleksii; Drapey, Sergiy; Proskurin, Dmitry; Dickman, Deborah A.; Ferguson, Ken

2011-10-01T23:59:59.000Z

246

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

SciTech Connect (OSTI)

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

247

ADMINISTRATIVE CHANGE TO DOE O 474.2, NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICEACME | National Nuclear SecurityO 474.2 Chg

248

Improved Design of Nuclear Reactor Control System | U.S. DOE Office of  

Office of Science (SC) Website

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 IndustrialIsadoreConnecticut Regions National11-12, 2005Idaho RegionsIllinoisScience

249

Princeton and PPPL share in $25 million nuclear arms-control project |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FOR Primary Authorstem ThePrinceton

250

Princeton and PPPL share in $25 million nuclear arms-control project |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FOR Primary Authorstem ThePrincetonPrinceton Plasma

251

Quantum Control of Light: From Slow Light and Fast Cars to Nuclear Gamma  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, and 323 K. | EMSLnanoparticlesQuantumQuantumRay

252

Gain-scheduled controller design for load-following in static space nuclear power systems  

E-Print Network [OSTI]

of variations in the fuel temperature reactivity feedback coeficient on the load-following capabilities of the SNPS. Robustness analysis results of the gain-scheduled compensator demonstrate that the proposed control concept exhibits a significant degree...

Onbasioglu, Fetiye Ozlem

1993-01-01T23:59:59.000Z

253

Nuclear reactor engineering  

SciTech Connect (OSTI)

Chapters are presented concerning energy from nuclear fission; nuclear reactions and radiations; diffusion and slowing-down of neutrons; principles of reactor analysis; nuclear reactor kinetics and control; energy removal; non-fuel reactor materials; the reactor fuel system; radiation protection and environmental effects; nuclear reactor shielding; nuclear reactor safety; and power reactor systems.

Glasstone, S.; Sesonske, A.

1981-01-01T23:59:59.000Z

254

Nuclear Counterterrorism  

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

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

255

Control of the direction and rate of nuclear spin flips in InAs quantum dots using detuned optical pulse trains  

E-Print Network [OSTI]

We find that detuning an optical pulse train from electronic transitions in quantum dots controls the direction of nuclear spin flips. The optical pulse train generates electron spins that precess about an applied magnetic field, with a spin component parallel to the field only for detuned pulses. This component leads to asymmetry in the nuclear spin flips, providing a way to produce a stable and precise value of the nuclear spin polarization. This effect is observed using two-color, time-resolved Faraday rotation and ellipticity.

S. G. Carter; A. Shabaev; Sophia E. Economou; T. A. Kennedy; A. S. Bracker; T. L. Reinecke

2009-01-16T23:59:59.000Z

256

The Application of High-Resolution Gamma-Ray Spectrometry (HRGS) to Nuclear Safeguards, Nonproliferation, and Arms Control Activities  

SciTech Connect (OSTI)

While well-developed methodologies exist for the employment of high- resolution gamma ray spectrometry (HRGS) in determining the isotopic composition of plutonium samples, the potential capabilities of such measurements in determining the properties of nuclear materials otherwise remain largely unexploited. These measurements contain information sufficiently detailed such that not only can the isotopic composition of uranium and plutonium materials be determined, but the details of the spectrum obtained will depend reproducibly upon other factors including the total mass, density, chemical composition, and geometrical configuration of the material, and for certain materials, the elapsed time since chemical processing. The potential thus exists to obtain a `gamma-ray fingerprint` for typical containers or assemblies of nuclear material which will then serve to identify that class of item in a later confirmatory measurement. These measurements have the additional advantage that, by comparison with active interrogation techniques which usually require the introduction of some extraneous form of radiation or other intrusive activity, they are totally passive, and thus impose only minimal additional safety or regulatory burdens on the operators. In the application of these measurements to the verification of treaty-limited items, where the information acquired may be sensitive in nature, the use of the CIVET (Controlled Intrusiveness Verification Technique) approach, where a computer-based interface is employed to limit access to the information obtained, may be followed.

Kane, Walter R.; Lemley, James R.; Forman, Leon

1997-12-31T23:59:59.000Z

257

Estimation, Analysis and Smoothing of Self-Similar Network Induced Delays in Feedback Control of Nuclear Reactors  

E-Print Network [OSTI]

This paper analyzes a nuclear reactor power signal that suffers from network induced random delays in the shared data network while being fed-back to the Reactor Regulating System (RRS). A detailed study is carried out to investigate the self similarity of random delay dynamics due to the network traffic in shared medium. The fractionality or selfsimilarity in the network induced delay that corrupts the measured power signal coming from Self Powered Neutron Detectors (SPND) is estimated and analyzed. As any fractional order randomness is intrinsically different from conventional Gaussian kind of randomness, these delay dynamics need to be handled efficiently, before reaching the controller within the RRS. An attempt has been made to minimize the effect of the randomness in the reactor power transient data with few classes of smoothing filters. The performance measure of the smoothers with fractional order noise consideration is also investigated into.

Majumder, Basudev; Pan, Indranil; Saha, Sayan; Das, Shantanu; Gupta, Amitava; 10.1109/PACC.2011.5978960

2012-01-01T23:59:59.000Z

258

Joint System Prognostics For Increased Efficiency And Risk Mitigation In Advanced Nuclear Reactor Instrumentation and Control  

SciTech Connect (OSTI)

The science of prognostics is analogous to a doctor who, based on a set of symptoms and patient tests, assesses a probable cause, the risk to the patient, and a course of action for recovery. While traditional prognostics research has focused on the aspect of hydraulic and mechanical systems and associated failures, this project will take a joint view in focusing not only on the digital I&C aspect of reliability and risk, but also on the risks associated with the human element. Model development will not only include an approximation of the control system physical degradation but also on human performance degradation. Thus the goal of the prognostic system is to evaluate control room operation; to identify and potentially take action when performance degradation reduces plant efficiency, reliability or safety.

Donald D. Dudenhoeffer; Tuan Q. Tran; Ronald L. Boring; Bruce P. Hallbert

2006-08-01T23:59:59.000Z

259

Annual report on strategic special nuclear material inventory differences, April 1, 1990--March 31, 1991  

SciTech Connect (OSTI)

This report of unclassified Inventory Difference (ID`s) covers the twelve months from April 1, 1990 through March 31, 1991 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses as the included data.

Not Available

1992-01-01T23:59:59.000Z

260

Protective coatings for radiation control in boiling water nuclear power reactors  

SciTech Connect (OSTI)

Stainless-steel surfaces (316 nuclear grade) develop /sup 60/Co-embedded oxide scales when exposed to a boiling water reactor (BWR) environment. Thin films such as Pd, Ni, Au, and Cr were found to drastically reduce the radioactive buildup. The films were prepared by vacuum evaporation and electroless deposition. The electroless coating consisted of a thin cathodically treated layer, followed by a nickel strike (--1 ..mu..m) and an electroless layer (--600 A). The present paper describes the results obtained from a transmission electron microscope replica study of the radioactive growths that formed on uncoated and thin-film-coated stainless-steel rods. The coated rods, when exposed to a simulated BWR environment, exhibited corrosion film growths ranging from large faceted grains (uncoated) and isolated islands of similar crystallites (Au coated) to extremely small nucleated growths (Pd, Ni coated). Also, it was found that chromium oxide films, which generally form a protective oxide on stainless steel, do not completely stop either the corrosion film growth or the associated radioactive buildup. The morphologies of the corrosion film growth were correlated with the relative /sup 60/Co activity, and the substrate topography. The best coating to date was found to be a Pd thin film, 1000 A thick, which reduced the radioactive buildup by a factor of --13.

Rao, T.V.; Vook, R.W.; Meyer, W.; Wittwer, C.

1987-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association  

SciTech Connect (OSTI)

The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC&A) systems in both countries. Mayak Production Association (MPA) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC&A systems at MPA. Current cooperative efforts are focused on enhancements to the existing MPC&A systems at four plants that are operated by MPA and that produce, process, handle and/or store proliferation-sensitive nuclear materials.

Starodubtsev, G.S.; Prishchepov, A.I.; Zatorsky, Y.M.; James, L.T. [and others

1997-11-01T23:59:59.000Z

262

A methodology to quantify the release of spent nuclear fuel from dry casks during security-related scenarios.  

SciTech Connect (OSTI)

Assessing the risk to the public and the environment from a release of radioactive material produced by accidental or purposeful forces/environments is an important aspect of the regulatory process in many facets of the nuclear industry. In particular, the transport and storage of radioactive materials is of particular concern to the public, especially with regard to potential sabotage acts that might be undertaken by terror groups to cause injuries, panic, and/or economic consequences to a nation. For many such postulated attacks, no breach in the robust cask or storage module containment is expected to occur. However, there exists evidence that some hypothetical attack modes can penetrate and cause a release of radioactive material. This report is intended as an unclassified overview of the methodology for release estimation as well as a guide to useful resource data from unclassified sources and relevant analysis methods for the estimation process.

Durbin, Samuel G.; Luna, Robert Earl

2013-11-01T23:59:59.000Z

263

International Nuclear Fuel Cycle Fact Book. Revision 12  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

Leigh, I.W.

1992-05-01T23:59:59.000Z

264

Nuclear reactors built, being built, or planned 1996  

SciTech Connect (OSTI)

This publication contains unclassified information about facilities, built, being built, or planned in the United States for domestic use or export as of December 31, 1996. The Office of Scientific and Technical Information, U.S. Department of Energy, gathers this information annually from Washington headquarters, and field offices of DOE; from the U.S. Nuclear Regulatory Commission (NRC); from the U. S. reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from U.S. and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: (1) a commercial reactor locator map and tables of the characteristic and statistical data that follow; a table of abbreviations; (2) tables of data for reactors operating, being built, or planned; and (3) tables of data for reactors that have been shut down permanently or dismantled.

NONE

1997-08-01T23:59:59.000Z

265

A review of the environmental survivability of telerobotic control sensor systems for use in nuclear waste tanks  

SciTech Connect (OSTI)

This report was prepared by the Oak Ridge National Laboratory (ORNL) and funded by the Department of Energy (DOE) Office of Technology Development (OTD) Robotics Technology Development Program (RTDP). During the next few years field deployment of remotely operated systems in nuclear waste cleanup operations will increase dramatically as DOE strives to efficiently and safely remediate the many waste storage sites. Typically, the most fragile components in remote systems are the sensors that provide feedback to the operators or to computer control algorithms. The purpose of this review is to determine the availability of environmentally hardened sensors to support control of a manipulator or vehicle system in a waste tank environment. The emphasis of the report is on the environmental ruggedness of currently available sensors. For the purpose of this review a set of nominal requirements for survivability were adopted conditions in the single-shell tanks at Hanford. This report is designed to be a practical guide to the state of the art in commercially available environmentally tolerant sensors for use with robotic systems. It is neither intended to be an exhaustive review of the technical literature on potential measurement techniques nor a complete physical review of the functioning of particular sensor systems. This report is intended to be a living document. As additional, corrected, or updated information is received from sensor manufacturers, it will be incorporated into the report database. The physical report will then be periodically revised and released in updated format. The authors wish to apologize to any sources of environmentally hardened sensors that were omitted during this review and encourage submission of new or updated data.

Holcomb, D.E.; Burks, B.L.

1994-05-01T23:59:59.000Z

266

Nuclear Counterterrorism  

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

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. The Manual is Official Use Only, and is not available on the Directives Portal. The point of contact for the Manual is Randall Weidman, NA-121.2, 202-586-4582.) Canceled by DOE O 457.1A

2006-02-07T23:59:59.000Z

267

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

surrounding a nuclear plant, and they are stronglylocation for a nuclear plant, but it is the measures thatand consequences of nuclear plant accidents and would match

Nero, jA.V.

2010-01-01T23:59:59.000Z

268

Regulatory Guide 5.29, Revision 2, "Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants".  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298,NIST3 AÇORIANONewsRegulatory Analysis

269

Nuclear reactors built, being built, or planned, 1991  

SciTech Connect (OSTI)

This document contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1991. The book is divided into three major sections: Section 1 consists of a reactor locator map and reactor tables; Section 2 includes nuclear reactors that are operating, being built, or planned; and Section 3 includes reactors that have been shut down permanently or dismantled. Sections 2 and 3 contain the following classification of reactors: Civilian, Production, Military, Export, and Critical Assembly. Export reactor refers to a reactor for which the principal nuclear contractor is an American company -- working either independently or in cooperation with a foreign company (Part 4, in each section). Critical assembly refers to an assembly of fuel and assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).

Simpson, B.

1992-07-01T23:59:59.000Z

270

A nuclear criticality safety assessment of the loss of moderation control in 2 1/2 and 10-ton cylinders containing enriched UF{sub 6}  

SciTech Connect (OSTI)

Moderation control for maintaining nuclear criticality safety in 2 {1/2}-ton, 10-ton, and 14-ton cylinders containing enriched uranium hexafluoride (UF{sub 6}) has been used safely within the nuclear industry for over thirty years, and is dependent on cylinder integrity and containment. This assessment evaluates the loss of moderation control by the breaching of containment and entry of water into the cylinders. The first objective of this study was to estimate the required amounts of water entering these large UF{sub 6} cylinders to react with, and to moderate the uranium compounds sufficiently to cause criticality. Hypothetical accident situations were modeled as a uranyl fluoride (UO{sub 2}F{sub 2}) slab above a UF{sub 6} hemicylinder, and a UO{sub 2}F{sub 2} sphere centered within a UF{sub 6} hemicylinder. These situations were investigated by computational analyses utilizing the KENO V.a Monte Carlo Computer Code. The results were used to estimate both the masses of water required for criticality, and the limiting masses of water that could be considered safe. The second objective of the assessment was to calculate the time available for emergency control actions before a criticality would occur, i.e., a {open_quotes}safetime{close_quotes}, for various sources of water and different size openings in a breached cylinder. In the situations considered, except the case for a fire hose, the safetime appears adequate for emergency control actions. The assessment shows that current practices for handling moderation controlled cylinders of low enriched UF{sub 6}, along with the continuation of established personnel training programs, ensure nuclear criticality safety for routine and emergency operations.

Newvahner, R.L. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Pryor, W.A. [PAI Corp., Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

271

Identifying and Protecting Official Use Only Information  

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

To establish a program within the Department of Energy (DOE), including the National Nuclear Security Administration (NNSA), to identify certain unclassified controlled information as Official Use Only (OUO) and to identify, mark, and protect documents containing such information.

2003-04-09T23:59:59.000Z

272

Calendar | OSTI, US Dept of Energy, Office of Scientific and...  

Office of Scientific and Technical Information (OSTI)

itting241.1Metadata.ppt 2015-01-02 11:38 Restricted Announcement of U.S. Department of Energy (DOE) Classified and Unclassified Controlled Nuclear Information (UCNI) 2015-01-02...

273

Application of Neutron-Absorbing Structural-Amorphous metal (SAM) Coatings for Spent Nuclear Fuel (SNF) Container to Enhance Criticality Safety Controls  

E-Print Network [OSTI]

241 Pu, etc. ). To prevent nuclear criticality in spent fuelto enhance criticality safety for spent nuclear fuel inSpent Nuclear Fuel (SNF) Container to Enhance Criticality

2006-01-01T23:59:59.000Z

274

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed absorption cross-section behavior. Consequently, if NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;Demazire

Demazire, Christophe

275

NUCLEAR PLANT OPERATIONS AND  

E-Print Network [OSTI]

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper- ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed. Consequently, if*E-mail: demaz@nephy.chalmers.se NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;high-burnup fuel

Pzsit, Imre

276

Technical cooperation between IAE/NNC and U.S. DOE National Laboratories on nuclear export controls in Kazakhstan -- a status report  

SciTech Connect (OSTI)

The US Department of Energy (DOE) sponsors technical cooperative agreements, also known as Lab to Lab agreements, between its National Laboratories and similar institutions in the Newly Independent States (NIS) for the purpose of sharing some of the experience and expertise on nuclear export controls and nonproliferation of the former with their NIS counterparts so that, in turn, they can provide technical support to their respective governments in nonproliferation matters. In Kazakhstan, two separate technical cooperative agreements involving the Institute of Atomic Energy of the National Nuclear Center, Argonne National Laboratory, and Los Alamos National Laboratory were established in 1996. The tasks carried out during the first year of these technical cooperative agreements are described and the objectives and end products of the tasks are discussed.

Picologlou, B. [Argonne National Lab., IL (United States); Cernicek, A. [Los Alamos National Lab., NM (United States); Pakhnitz, V.; Koltysheva, G. [Inst. of Atomic Energy/NNC (Kazakhstan)

1997-09-01T23:59:59.000Z

277

Nuclear Physics  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |Navy Nuclear NavyNuclear Physics

278

Nuclear Structure  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |NavyNuclear Speed-Dating Nuclear

279

Nuclear disarmament verification  

SciTech Connect (OSTI)

Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

DeVolpi, A.

1993-12-31T23:59:59.000Z

280

Implications of an Improvised Nuclear Device Detonation on Command and Control for Surrounding Regions at the Local, State and Federal Levels  

SciTech Connect (OSTI)

This paper discusses command and control issues relating to the operation of Incident Command Posts (ICPs) and Emergency Operations Centers (EOCs) in the surrounding area jurisdictions following the detonation of an Improvised Nuclear Device (IND). Although many aspects of command and control will be similar to what is considered to be normal operations using the Incident Command System (ICS) and the National Incident Management System (NIMS), the IND response will require many new procedures and associations in order to design and implement a successful response. The scope of this white paper is to address the following questions: Would the current command and control framework change in the face of an IND incident? What would the management of operations look like as the event unfolded? How do neighboring and/or affected jurisdictions coordinate with the state? If the target areas command and control infrastructure is destroyed or disabled, how could neighboring jurisdictions assist with command and control of the targeted jurisdiction? How would public health and medical services fit into the command and control structure? How can pre-planning and common policies improve coordination and response effectiveness? Where can public health officials get federal guidance on radiation, contamination and other health and safety issues for IND response planning and operations?

Pasquale, David A.; Hansen, Richard G.

2013-01-23T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

UNCLASSIFIED Defense Technical Information Center  

E-Print Network [OSTI]

IR (FLIR) imagers. The acquisition. We describe the development of a new dual- ne sensr stemw i nd of such an FPAfor a sensor in a boost- generation FLIR. One of the principal enhancements phase interceptor. In addition, we describe the envisioned for the next generation FLIR is multispectral development of acousto

Zhu, Zhigang

282

SPECIAL REREVIEW FINAL DETERMINATION UNCLASSIFIED  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*.MSE&.17-August 20030 .March3SPECIAL

283

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, jA.V.

2010-01-01T23:59:59.000Z

284

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

Nero, jA.V.

2010-01-01T23:59:59.000Z

285

American Nuclear Society 7th Topical Meeting on Robotics and Remote Systems AN INPUT SHAPING CONTROLLER ENABLING  

E-Print Network [OSTI]

. of Mechanical Engineering Massachusetts Institute of Technology Cambridge, MA Eric Kriikku Savannah River Technology Center Westinghouse Savannah River Company Aiken, SC ABSTRACT A gantry crane at the Savannah River Technology Center was retrofitted with an Input Shaping controller. The controller intercepts the operator

Singhose, William

286

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, jA.V.

2010-01-01T23:59:59.000Z

287

Dynamic Modeling and Control of Nuclear Reactors Coupled to Closed-Loop Brayton Cycle Systems using SIMULINK{sup TM}  

SciTech Connect (OSTI)

The operation of space reactors for both in-space and planetary operations will require unprecedented levels of autonomy and control. Development of these autonomous control systems will require dynamic system models, effective control methodologies, and autonomous control logic. This paper briefly describes the results of reactor, power-conversion, and control models that are implemented in SIMULINK{sup TM} (Simulink, 2004). SIMULINK{sup TM} is a development environment packaged with MatLab{sup TM} (MatLab, 2004) that allows the creation of dynamic state flow models. Simulation modules for liquid metal, gas cooled reactors, and electrically heated systems have been developed, as have modules for dynamic power-conversion components such as, ducting, heat exchangers, turbines, compressors, permanent magnet alternators, and load resistors. Various control modules for the reactor and the power-conversion shaft speed have also been developed and simulated. The modules are compiled into libraries and can be easily connected in different ways to explore the operational space of a number of potential reactor, power-conversion system configurations, and control approaches. The modularity and variability of these SIMULINK{sup TM} models provides a way to simulate a variety of complete power generation systems. To date, both Liquid Metal Reactors (LMR), Gas Cooled Reactors (GCR), and electric heaters that are coupled to gas-dynamics systems and thermoelectric systems have been simulated and are used to understand the behavior of these systems. Current efforts are focused on improving the fidelity of the existing SIMULINK{sup TM} modules, extending them to include isotopic heaters, heat pipes, Stirling engines, and on developing state flow logic to provide intelligent autonomy. The simulation code is called RPC-SIM (Reactor Power and Control-Simulator)

Wright, Steven A.; Sanchez, Travis [Sandia National Laboratories, Org 6872 MS-1146, PO Box 5800 Albuquerque, New Mexico 87185 (United States)

2005-02-06T23:59:59.000Z

288

Application of a Virtual Reactivity Feedback Control Loop in Non-Nuclear Testing of a Fast Spectrum Reactor  

SciTech Connect (OSTI)

For a compact, fast-spectrum reactor, reactivity feedback is dominated by core deformation at elevated temperature. Given the use of accurate deformation measurement techniques, it is possible to simulate nuclear feedback in non-nuclear electrically heated reactor tests. Implementation of simulated reactivity feedback in response to measured deflection is being tested at the Nasa Marshall Space Flight Center Early Flight Fission Test Facility (EFF-TF). During tests of the SAFE-100 reactor prototype, core deflection was monitored using a high resolution camera. 'Virtual' reactivity feedback was accomplished by applying the results of Monte Carlo calculations (MCNPX) to core deflection measurements; the computational analysis was used to establish the reactivity worth of various core deformations. The power delivered to the SAFE-100 prototype was then adjusted accordingly via kinetics calculations. The work presented in this paper will demonstrate virtual reactivity feedback as core power was increased from 1 kWt to 10 kWt, held approximately constant at 10 kWt, and then allowed to decrease based on the negative thermal reactivity coefficient. (authors)

Bragg-Sitton, Shannon M. [NASA Marshall Space Flight Center, Huntsville, Al, 35812 (United States); Forsbacka, Matthew [NASA Headquarters, 300 E St. S, Washington, DC 20465 (United States)

2004-07-01T23:59:59.000Z

289

Critical Analysis of Dry Storage Temperature Limits for Zircaloy-Clad Spent Nuclear Fuel Based on Diffusion Controlled Cavity Growth  

SciTech Connect (OSTI)

Interim dry storage of spent nuclear fuel (SNF) rods is of critical concern because a shortage of existing SNF wet storage capacity combined with delays in the availability of a permanent disposal repository has led to an increasing number of SNF rods being placed into interim dry storage. Safe interim dry storage must be maintained for a minimum of twenty years according to the Standard Review Plan for Dry Cask Storage Systems [1] and the Code of Federal Regulations, 10 CFR Part 72 [2]. Interim dry storage licensees must meet certain safety conditions when storing SNF rods to ensure that there is a ''very low probability (e.g. 0.5%) of cladding breach during long-term storage'' [1]. Commercial SNF typically consists of uranium oxide pellets surrounded by a thin cladding. The cladding is usually an {alpha}-zirconium based alloy know as ''Zircaloy''. In dry storage, the SNF rods are confined in one of several types of cask systems approved by the Nuclear Regulatory Commission (NRC). ''The cask system must be designed to prevent degradation of fuel cladding that results in a type of cladding breach, such as axial-splits or ductile fracture, where irradiated UO{sub 2} particles may be released. In addition, the fuel cladding should not degrade to the point where more than one percent of the fuel rods suffer pinhole or hairline crack type failure under normal storage conditions [1].'' The NRC has approved two models [3,4] for use by proposed dry storage licensees to determine the maximum initial temperature limit for nuclear fuel rods in dry storage that supposedly meet the above criteria and yield consistent temperature limits. Though these two models are based on the same fundamental failure theory, different assumptions have been made including the choice of values for material constants in the failure equation. This report will examine and compare the similarities and inconsistencies of these two models. It will illustrate some of the shortcomings of the current models and suggest modifications as well as some experiments that should be started in the near future. This report will also discuss changes in the current NRC standards with regard to the adoption of a strain-based model to be used to determine maximum allowable temperatures of the SNF.

Hayes, T.A.; Rosen, R.S.; Kassner, M.E.

1999-12-01T23:59:59.000Z

290

Nuclear Chemistry Division annual report FY83  

SciTech Connect (OSTI)

The purpose of the annual reports of the Nuclear Chemistry Division is to provide a timely summary of research activities pursued by members of the Division during the preceding year. Throughout, details are kept to a minimum; readers desiring additional information are encouraged to read the referenced documents or contact the authors. The Introduction presents an overview of the Division's scientific and technical programs. Next is a section of short articles describing recent upgrades of the Division's major facilities, followed by sections highlighting scientific and technical advances. These are grouped under the following sections: nuclear explosives diagnostics; geochemistry and environmental sciences; safeguards technology and radiation effect; and supporting fundamental science. A brief overview introduces each section. Reports on research supported by a particular program are generally grouped together in the same section. The last section lists the scientific, administrative, and technical staff in the Division, along with visitors, consultants, and postdoctoral fellows. It also contains a list of recent publications and presentations. Some contributions to the annual report are classified and only their abstracts are included in this unclassified portion of the report (UCAR-10062-83/1); the full article appears in the classified portion (UCAR-10062-83/2).

Struble, G. (ed.)

1983-01-01T23:59:59.000Z

291

Deployment of a Full-Scope Commercial Nuclear Power Plant Control Room Simulator at the Idaho National Laboratory  

SciTech Connect (OSTI)

The INL operates the HSSL to conduct research in the design and evaluation of advanced reactor control rooms, integration of intelligent support systems to assist operators, development and assessment of advanced human performance models, and visualizations to assess advanced operational concepts across various infrastructures. This advanced facility consists of a reconfigurable simulator and a virtual reality capability (known as the Computer-Aided Virtual Environment (CAVE)) (Figure 2). It supports human factors research, including human-in-the-loop performance, HSI, and analog and digital hybrid control displays. It can be applied to the development and evaluation of control systems and displays for complex systems such as existing and advanced NPP control rooms, command and control systems, and advance emergency operations centers. The HSSL incorporates a reconfigurable control room simulator, which is currently housed in the Center for Advanced Energy Studies (CAES), a joint venture of the DOE and the Idaho University System. The simulator is a platform- and plant-neutral environment intended for full-scope and part-task testing of operator performance in various control room configurations. The simulator is not limited to a particular plant or even simulator architecture. It can support engineering simulator platforms from multiple vendors using digital interfaces. Due to its ability to be reconfigured, it is possible to switch the HSI - not just to digital panels but also to different control modalities such as those using greater plant automation or intelligent alarm filtering. The simulator currently includes three operator workstations, each capable of driving up to eight 30-inch monitors. The size and number of monitors varies depending on the particular front-end simulator deployed for a simulator study. These operator workstations would typically be used for the shift supervisor or senior reactor operator, reactor operator, and assistant reactor operator in current US NPPs. In addition to the three workstations, information can be shared between the workstations and further displayed on a large-screen overview display or a panel mimic. An 82-inch high-definition display is commonly used for the overview display.

Ronald Boring; Julius Persensky; Kenneth Thomas

2011-09-01T23:59:59.000Z

292

Standard practice for qualification and acceptance of boron based metallic neutron absorbers for nuclear criticality control for dry cask storage systems and transportation packaging  

E-Print Network [OSTI]

1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both. 1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and cermets, clad or unclad, containing the neutron absorber boron-10 (10B). 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2007-01-01T23:59:59.000Z

293

AQUATIC PLANT CONTROL RESEARCH PROGRAM  

E-Print Network [OSTI]

IS OBSOLETEDO FORM 1473IJ_'13 Unclassified SECURITY CLASSIFICATION OF THIS PA:>E (WIt"" Oil/II En/ered) #12 of the use of such ommf;1rClal produr:ts. #12;Unclassified SECURITY CLASSIFICATION OF THIS PAGE (WIlen D of Engineers, U. S. Army 13. NUMBER OF PAGES Washington, D. C. 20314 83 15. SECURITY CLASS. (ot this report

US Army Corps of Engineers

294

nuclear controls | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

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295

Features of temperature control of fuel element cladding for pressurized water nuclear reactor WWER-1000 while simulating reactor accidents  

SciTech Connect (OSTI)

During the experiments simulating NPR (nuclear power reactor) accidents with a coolant loss fuel elements behavior in a steam-hydrogen medium was studied at the temperature changed with the rate from 1 to 100K/s within the range of 3001500 C. Indications of the thermocouples fixed on the cladding notably differ from real values of the cladding temperatures in the area of measuring junction due to thermal resistance influence of the transition zones cladding-junction and junction-coolant. The estimating method of a measurement error was considered which can provide adequate accounting of the influence factors. The method is based on thermal probing of a thermocouple by electric current flashing through thermoelements under the coolant presence or absence, a response time registration and processing, calculation of thermal inertia value for a thermocouple junction. A formula was derived for calculation of methodical error under stationary mode and within the stage of linear increase in temperature, which will determine the conditions for the cladding depressurization. Some variants of the formula application were considered, and the values of methodical errors were established which reached ?5% of maximum value by the final moment of the stage of linear increase in the temperature.

Zaytsev, P. A.; Priymak, S. V.; Usachev, V. B.; Oleynikov, P. P.; Soldatkin, D. M. [Scientific Research Institute, Scientific Industrial Association LUCH, Podolsk (Russian Federation)] [Scientific Research Institute, Scientific Industrial Association LUCH, Podolsk (Russian Federation)

2013-09-11T23:59:59.000Z

296

Some thoughts on the nonproliferation of nuclear weapons  

SciTech Connect (OSTI)

This paper discusses factors controlling the dissemination of nuclear technologies and especially fissile materials.

Krikorian N.H.; Hawkins, H.T.

1996-05-01T23:59:59.000Z

297

Pioneering the nuclear age  

SciTech Connect (OSTI)

This paper reviews the historical aspects of nuclear physics. The scientific aspects of the early transuranium elements are discussed and arms control measures are reviewed. 11 refs., 14 figs. (LSP)

Seaborg, G.T.

1988-09-01T23:59:59.000Z

298

Nuclear Nonproliferation,  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |Navy Nuclear Navy Posted:Sensor

299

Nuclear reactors built, being built, or planned: 1995  

SciTech Connect (OSTI)

This report contains unclassified information about facilities built, being built, or planned in the US for domestic use or export as of December 31, 1995. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: (1) a commercial reactor locator map and tables of the characteristic and statistical data that follow; a table of abbreviations; (2) tables of data for reactors operating, being built, or planned; and (3) tables of data for reactors that have been shut down permanently or dismantled. The reactors are subdivided into the following parts: Civilian, Production, Military, Export, and Critical Assembly. Export reactor refers to a reactor for which the principal nuclear contractor is a US company--working either independently or in cooperation with a foreign company (Part 4). Critical assembly refers to an assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).

NONE

1996-08-01T23:59:59.000Z

300

Nuclear reactors built, being built, or planned, 1994  

SciTech Connect (OSTI)

This document contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1994. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: a commercial reactor locator map and tables of the characteristic and statistical data that follow; a table of abbreviations; tables of data for reactors operating, being built, or planned; and tables of data for reactors that have been shut down permanently or dismantled. The reactors are subdivided into the following parts: Civilian, Production, Military, Export, and Critical Assembly. Export reactor refers to a reactor for which the principal nuclear contractor is a US company -- working either independently or in cooperation with a foreign company (Part 4). Critical assembly refers to an assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).

NONE

1995-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Nuclear Systems Technology | Nuclear Science | ORNL  

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

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302

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

303

E-Print Network 3.0 - aluminum-clad spent nuclear Sample Search...  

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

of Texas... Stephen Bolt Ben Lail Adam Davis 12;Nuclear History 1942 - First self sustaining nuclear... 1946 - Atomic Energy Act of 1946 was passed to control nuclear energy...

304

E-Print Network 3.0 - aluminum-based spent nuclear Sample Search...  

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

of Texas... Stephen Bolt Ben Lail Adam Davis 12;Nuclear History 1942 - First self sustaining nuclear... 1946 - Atomic Energy Act of 1946 was passed to control nuclear energy...

305

Nuclear Nonproliferation  

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

306

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

307

Transactions of the fourth symposium on space nuclear power systems  

SciTech Connect (OSTI)

This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these papers include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, refractory alloys and high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

El-Genk, M.S.; Hoover, M.D. (eds.)

1987-01-01T23:59:59.000Z

308

Transactions of the fifth symposium on space nuclear power systems  

SciTech Connect (OSTI)

This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these paper include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

El-Genk, M.S.; Hoover, M.D. (eds.)

1988-01-01T23:59:59.000Z

309

Nuclear Physics  

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

310

Nuclear Energy  

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

311

applied nuclear research: Topics by E-print Network  

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

2011-01-01 2 he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering (NSE) generate, control, and apply nuclear Environmental Sciences...

312

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

313

Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies NPIC&HMIT 2009, Knoxville, Tennessee, April 5-9, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL  

E-Print Network [OSTI]

Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) FUELASSEMBLY SELF SHIELDING Polytechnic Institute Department of Mechanical, Aerospace and Nuclear Engineering Romanc2@rpi.edu; Danony

Danon, Yaron

314

Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies NPIC&HMIT 2009, Knoxville, Tennessee, April 5-9, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL  

E-Print Network [OSTI]

Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, automation 1 INTRODUCTION In nuclear power plants (NPPs), novel digitalized I&C systems enable complicated, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) VERIFICATION OF SAFETY LOGIC DESIGNS

Heljanko, Keijo

315

Nuclear Explosive and Weapon Surety Program  

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

All nuclear explosives and nuclear explosive operations require special safety, security, and use control consideration because of the potentially unacceptable consequences of an accident or unauthorized act; therefore, a Nuclear Explosive and Weapon Surety (NEWS) Program is established to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives.

2015-01-26T23:59:59.000Z

316

Nuclear material operations manual  

SciTech Connect (OSTI)

This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion.

Tyler, R.P.

1981-02-01T23:59:59.000Z

317

Nuclear Waffles  

E-Print Network [OSTI]

The dense neutron-rich matter found in supernovae and neutron stars is expected to form complex nonuniform phases referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts. We use two recently developed hybrid CPU/GPU codes to perform large scale molecular dynamics (MD) simulations with $51200$ and $409600$ nucleons of nuclear pasta. From the output of the MD simulations we characterize the topology and compute two observables, the radial distribution function $g(r)$ and the structure factor $S(q)$, for systems with proton fractions $Y_p=0.10, 0.20, 0.30$ and $0.40$ at about one third of nuclear saturation density and temperatures near $1.0$ MeV. We observe that the two lowest proton fraction systems simulated, $Y_p=0.10$ and $0.20$, equilibrate quickly and form liquid-like structures. Meanwhile, the two higher proton fraction systems, $Y_p=0.30$ and $0.40$, take a longer time to equilibrate and organize themselves in solid-like periodic structures. Furthermore, the $Y_p=0.40$ system is made up of slabs, lasagna phase, interconnected by defects while the $Y_p=0.30$ systems consist of a stack of perforated plates, the nuclear waffle phase. The periodic configurations observed in our MD simulations for proton fractions $Y_p\\ge0.30$ have important consequences for the structure factors $S(q)$ of protons and neutrons, which relate to many transport properties of supernovae and neutron star crust. A detailed study of the waffle phase and how its structure depends on temperature, size of the simulation and the screening length showed that finite-size effects appear to be under control and, also, that the plates in the waffle phase merge at temperatures slightly above $1.0$ MeV and the holes in the plates form an hexagonal lattice at temperatures slightly lower than $1.0$ MeV.

A. S. Schneider; D. K. Berry; C. M. Briggs; M. E. Caplan; C. J. Horowitz

2014-09-08T23:59:59.000Z

318

Nuclear Material Control and Accountability  

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

These changes are intended to correct typographical and pagination errors, delete a canceled reference and clarify the intent of four metrics in Attachment 3.

2012-11-19T23:59:59.000Z

319

Nuclear Material Control and Accountability  

Office of Environmental Management (EM)

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320

Nuclear Materials Control and Accountability  

Office of Environmental Management (EM)

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Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Nuclear Physics: Experiment Research  

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

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322

Nuclear Science & Technology  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguards and Nuclear

323

Nuclear Weapons Journal  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguardsResearchNuclear Weapons

324

The design and synthesis of nuclear localization signal (NLS) mimics  

E-Print Network [OSTI]

Nuclear import of proteins is a carefully controlled process that is critical for cellular function and regulation. A protein is marked for nuclear entry by a nuclear localization signal (NLS), a peptide motif, which typically consists of one or two...

Ho, Thai Huu

2013-02-22T23:59:59.000Z

325

Method of controlling fusion reaction rates  

DOE Patents [OSTI]

This invention relates to a method of controlling the reaction rates in a nuclear fusion reactor; and more particularly, to the use of polarized nuclear fuel.

Kulsrud, R.M.; Furth, H.P.; Valeo, E.J.; Goldhaber, M.

1983-05-09T23:59:59.000Z

326

Nuclear Security 101 | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |Navy NuclearNuclear Science

327

Nuclear Security Enterprise | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |Navy NuclearNuclear

328

R326 Dispatch Nuclear migration: Cortical anchors for cytoplasmic dynein  

E-Print Network [OSTI]

dynein, and provide a critical link in understanding the basis of nuclear migration in yeast. The nuclearR326 Dispatch Nuclear migration: Cortical anchors for cytoplasmic dynein Kerry Bloom Nuclear body that rolls around at random inside the sack of a eukaryotic cell. Controlled nuclear movements

329

National Center for Nuclear Security: The Nuclear Forensics Project (F2012)  

SciTech Connect (OSTI)

These presentation visuals introduce the National Center for Nuclear Security. Its chartered mission is to enhance the Nations verification and detection capabilities in support of nuclear arms control and nonproliferation through R&D activities at the NNSS. It has three focus areas: Treaty Verification Technologies, Nonproliferation Technologies, and Technical Nuclear Forensics. The objectives of nuclear forensics are to reduce uncertainty in the nuclear forensics process & improve the scientific defensibility of nuclear forensics conclusions when applied to nearsurface nuclear detonations. Research is in four key areas: Nuclear Physics, Debris collection and analysis, Prompt diagnostics, and Radiochemistry.

Klingensmith, A. L.

2012-03-21T23:59:59.000Z

330

Nuclear Engineer (Nuclear Safety Specialist)  

Broader source: Energy.gov [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...

331

International Nuclear Security  

SciTech Connect (OSTI)

This presentation discusses: (1) Definitions of international nuclear security; (2) What degree of security do we have now; (3) Limitations of a nuclear security strategy focused on national lock-downs of fissile materials and weapons; (4) What do current trends say about the future; and (5) How can nuclear security be strengthened? Nuclear security can be strengthened by: (1) More accurate baseline inventories; (2) Better physical protection, control and accounting; (3) Effective personnel reliability programs; (4) Minimize weapons-usable materials and consolidate to fewer locations; (5) Consider local threat environment when siting facilities; (6) Implement pledges made in the NSS process; and (7) More robust interdiction, emergency response and special operations capabilities. International cooperation is desirable, but not always possible.

Doyle, James E. [Los Alamos National Laboratory

2012-08-14T23:59:59.000Z

332

ORISE Resources: Radiological and Nuclear Terrorism: Medical...  

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

Training Clinicians for Response to a Radiological or Nuclear Terrorism Attack The Centers for Disease Control and Prevention and its Radiation Studies Branch in the National...

333

Nuclear Operations | National Nuclear Security Administration  

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

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334

Nuclear Verification | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |NavyNuclear

335

Nuclear Pairs | Jefferson Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclear Pairs High-Resolution

336

Nuclear Physics Program  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclear Pairs

337

Nuclear Science Series: Radiochemistry  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguards and

338

Unclassified March 2000 EP-2000-8019  

E-Print Network [OSTI]

it is important to know the fluid pressure in the rock formations. A mathematical model for the prediction of the fluid pressure history is given by a time-dependent diffusion equation. Application of the finite AMS Subject Classification: 65F10, 65F15, 76S05 1 Introduction Knowledge of the fluid pressure history

Vuik, Kees

339

UNCLASSIFIED Institute for Materials Science Lecture Series  

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

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340

EVALUATION REPORT The Department of Energy's Unclassified  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.Program - LibbyofThisStatement Tuesday, September 25-- ConsumerDepartment of

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Evaluation Report The Department of Energy's Unclassified  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.Program -DepartmentNovember 1, 2010December 1,Goals Chapter 42.15 -

342

Unclassified Foreign National Visits & Assignments Questionnaire |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists' Research Petroleum ReserveDepartment of EnergyDepartmentSankar

343

Unclassified Foreign National Visits & Assignments Questionnaire  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy Usage »of EnergyTheTwo New EnergyofDEVELOPMENTEnergy LowUmatilla Tribes

344

PROBING DENSE NUCLEAR MATTER VIA NUCLEAR COLLISIONS  

E-Print Network [OSTI]

University of California. LBL-12095 Probing Dense NuclearMatter Nuclear Collisions* v~a H. Stocker, M.Gyulassy and J. Boguta Nuclear Science Division Lawrence

Stocker, H.

2012-01-01T23:59:59.000Z

345

Nuclear Astrophysics  

E-Print Network [OSTI]

Nuclear physics has a long and productive history of application to astrophysics which continues today. Advances in the accuracy and breadth of astrophysical data and theory drive the need for better experimental and theoretical understanding of the underlying nuclear physics. This paper will review some of the scenarios where nuclear physics plays an important role, including Big Bang Nucleosynthesis, neutrino production by our sun, nucleosynthesis in novae, the creation of elements heavier than iron, and neutron stars. Big-bang nucleosynthesis is concerned with the formation of elements with A nuclear physics inputs required are few-nucleon reaction cross sections. The nucleosynthesis of heavier elements involves a variety of proton-, alpha-, neutron-, and photon-induced reactions, coupled with radioactive decay. The advent of radioactive ion beam facilities has opened an important new avenue for studying these processes, as many involve radioactive species. Nuclear physics also plays an important role in neutron stars: both the nuclear equation of state and cooling processes involving neutrino emission play a very important role. Recent developments and also the interplay between nuclear physics and astrophysics will be highlighted.

Carl R. Brune

2005-02-28T23:59:59.000Z

346

Countering Nuclear Terrorism and Trafficking | National Nuclear...  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism and Trafficking | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

347

Space Nuclear  

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

Space Nuclear Today the INL is preparing to assist with the Multi-Mission RTG (MMRTG). The INL is assigned the final assembly and testing of the RTG for the project which is...

348

Nuclear Golf  

E-Print Network [OSTI]

Broadcast Transcript: Pay no attention to that nuclear warhead behind the 18th hole; just shout "Fore!" and drive your Titleist down the fairway. In a development that is bizarre even by North Korean standards, the country ...

Hacker, Randi; Tsutsui, William

2006-12-06T23:59:59.000Z

349

Nuclear Hydrogen  

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

Hydrogen High temperature options for nuclear generation of hydrogen on a commercial basis are several years in the future. Thermo-chemical water splitting has been proven to be...

350

Nuclear forces  

SciTech Connect (OSTI)

These lectures present an introduction into the theory of nuclear forces. We focus mainly on the modern approach, in which the forces between nucleons emerge from low-energy QCD via chiral effective field theory.

Machleidt, R. [Department of Physics, University of Idaho, Moscow, Idaho 83844 (United States)

2013-06-10T23:59:59.000Z

351

OPERATOR PERFORMANCE IN LONG DURATION, LOW TASK LOAD CONTROL OPERATIONS  

E-Print Network [OSTI]

and conducted. Overall, 36 participants operated a digital nuclear power plant control workstation simulation In the United States, a major effort is underway to modernize existing nuclear power plants and their control rooms, as well as design new, advanced nuclear power plants. Current control rooms for nuclear power

Cummings, Mary "Missy"

352

advanced control room: Topics by E-print Network  

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

for nuclear power and conducted. Overall, 36 participants operated a digital nuclear power plant control workstation simulation Cummings, Mary "Missy" 110 Proposal for the...

353

active load control: Topics by E-print Network  

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

for nuclear power and conducted. Overall, 36 participants operated a digital nuclear power plant control workstation simulation Cummings, Mary "Missy" 47 Real-Time Deferrable...

354

advanced control rooms: Topics by E-print Network  

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

for nuclear power and conducted. Overall, 36 participants operated a digital nuclear power plant control workstation simulation Cummings, Mary "Missy" 110 Proposal for the...

355

Nuclear Nonproliferation Programs | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium

356

Nuclear Thermal Rockets: The Physics of the Fission Reactor  

E-Print Network [OSTI]

Nuclear Thermal Rockets: The Physics of the Fission Reactor Shane D. Ross Control and Dynamical heats up when it passes through a nuclear reactor, where controlled fission of some fissionable material, with the nuclear fission reactor as a heat source [Lawrence, Witter, and Humble, 1992]. it works essentially

Ross, Shane

357

Nuclear Detonation Detection | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls | National NuclearDetonation

358

Nuclear Radiological Threat Task Force Established | National Nuclear  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclear PairsNuclearSecurity

359

Nuclear Weapons Testing Resumes | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguardsResearchNuclear

360

Hot particle laundry monitoring at a nuclear power facility  

E-Print Network [OSTI]

by adjusting a knob on the control console. The control console contains the control unit, the upper detector control system and the nuclear electronics. The ACM-120 uses a microprocessor to analyze the data and monitor for various system malfunctions..., monitoring method, detector type, alarm levels and the storage and disposal limits. In the second part, a detailed evaluation was conducted on three automated laundry monitors; National Nuclear LCM-15A, I. R. T. ACM-120, Interstate Nuclear Services ALM...

Farver, Douglas Floyd

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Nuclear reactor safety device  

DOE Patents [OSTI]

A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.

Hutter, E.

1983-08-15T23:59:59.000Z

362

Nuclear Forensics | National Security | ORNL  

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

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363

Nuclear Physics from Lattice QCD  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclear PairsNuclear Physicsfrom Lattice

364

Nuclear Sciences | More Science | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguards andScienceNuclear

365

Nuclear scales  

SciTech Connect (OSTI)

Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the {pi}-{gamma} force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

Friar, J.L.

1998-12-01T23:59:59.000Z

366

Nuclear Forensics  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchives Events/NewsYouNuclearNuclear Forensics

367

Nuclear Nonproliferation Programs | ORNL  

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

Nuclear Nonproliferation Programs SHARE Nuclear Nonproliferation Programs image Oak Ridge National Laboratory covers the entire spectrum of nuclear nonproliferation work, from...

368

NUCLEAR PROXIMITY FORCES  

E-Print Network [OSTI]

One might summarize of nuclear potential energy has beendegree of freedom) for the nuclear interaction between anyUniversity of California. Nuclear Proximity Forces 'I< at

Randrup, J.

2011-01-01T23:59:59.000Z

369

Global Nuclear Security  

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

Global Nuclear Security Both DOE and the National Nuclear Security Administration are working to reduce the risk of nuclear proliferation and provide technologies to improve...

370

Nuclear Reactors and Technology  

SciTech Connect (OSTI)

This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

Cason, D.L.; Hicks, S.C. [eds.

1992-01-01T23:59:59.000Z

371

Nuclear Science/Nuclear Chemistry  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Regionat Cornell BatteriesArchivesNuclear Science/Nuclear Chemistry

372

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

SciTech Connect (OSTI)

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

Pawloski, G A

2012-01-30T23:59:59.000Z

373

Nuclear reactor safety device  

DOE Patents [OSTI]

A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

Hutter, Ernest (Wilmette, IL)

1986-01-01T23:59:59.000Z

374

Nuclear divisional reactor  

SciTech Connect (OSTI)

A nuclear divisional reactor including a reactor core having side and top walls, a heat exchanger substantially surrounding the core, the heat exchanger including a plurality of separate fluid holding and circulating chambers each in contact with a portion of the core, control rod means associated with the core and external of the heat exchanger including control rods and means for moving said control rods, each of the chambers having separate means for delivering and removing fluid therefrom, separate means associated with each of the delivering and removing means for producing useable energy external of the chambers, each of the means for producing useable energy having separate variable capacity energy outputs thereby making available a plurality of individual sources of useable energy of varying degrees.

Administratrix, A.P.; Rugh, J.L.

1982-11-02T23:59:59.000Z

375

Distribution and Ratios of 137Cs and K in Control and K-treated Coconut Trees at Bikini Island where Nuclear Test Fallout Occurred: Effects and Implications  

SciTech Connect (OSTI)

Coconut trees growing on atolls of the Bikini Islands are on the margin of K deficiency because the concentration of exchangeable K in coral soil is very low ranging from only 20 to 80 mg kg{sup -1}. When provided with additional K, coconut trees absorb large quantities of K and this uptake of K significantly alters the patterns of distribution of {sup 137}Cs within the plant. Following a single K fertilization event, mean total K in trunks of K-treated trees is 5.6 times greater than in trunks of control trees. In contrast, {sup 137}Cs concentration in trunks of K-treated and control trees is statistically the same while {sup 137}Cs is significantly lower in edible fruits of K treated trees. Within one year after fertilization (one rainy season), K concentration in soil is back to naturally, low concentrations, however, the tissue concentrations of K in treated trees stays very high internally in the trees for years while {sup 137}Cs concentration in treated trees remains very low in all tree compartments except for the trunk. Potassium fertilization did not change soil Cs availability. Mass balance calculations suggest that the fertilization event increased above ground plant K content by at least a factor of 5 or 2.2 kg. Potassium concentrations and content were higher in all organs of K fertilized trees with the greatest increases seen in organs that receive a portion of tissue K through xylem transport (trunk, fronds and fruit husks) and lowest in organs supplied predominantly with K via the phloem (palm heart, spathe, coco meat and fluid). {sup 137}Cesium concentrations and contents were dramatically lower in all organs of K treated trees with greatest proportional reductions observed in organs supplied predominantly with K via the phloem (palm heart, spathe, coco meat and fluid). All trees remobilize both K and {sup 137}Cs from fronds as they proceed toward senescence. In control trees the reduction in concentration of K and {sup 137}Cs in fronds as they age is logarithmic but K remobilization is linear in K-treated trees where K concentration is high. As a result of K treatment the {sup 137}Cs concentration in K-treated fronds is extremely low and constant with frond age. Fronds of K treated trees contain a greater amount of K than control tree fronds. As they fall to the ground and decay they provide a small continuing pool of K that is about 3% of the natural K in soil under the tree canopy. Results of K and {sup 137}Cs concentration and distribution in control and K-treated coconut trees suggest that the application of K reduces {sup 137}Cs uptake both in the short term immediately following K fertilization and in the long term, after soil K levels have returned to normal but while plant K stores remain high. These results suggests that high internal K concentration and not high soil K is primarily responsible for long-term reduction of {sup 137}Cs in edible fruits, and plays a significant role in limiting further uptake of {sup 137}Cs by roots, and affects allocation of {sup 137}Cs to edible fruits for years. Coconut trees are capable of luxury K accumulation when provided with excess K and in this example the additional K can effectively provide the K requirements of the plant for in excess of 10 years. The reduction of {sup 137}Cs uptake lasts for at least 10 y after K is last applied and greatly reduces the estimated radiation dose to people consuming local tree foods. Effectiveness and duration of K treatment provides important assurances that reduction in {sup 137}Cs is long term and the radiation dose from consuming local plant foods will remain low.

Robison, W L; Brown, P H; Stone, E L; Hamilton, T F; Conrado, C L; Kehl, S R

2008-05-19T23:59:59.000Z

376

Nuclear fission and nuclear safeguards: Common technologies and challenges  

SciTech Connect (OSTI)

Nuclear fission and nuclear safeguards have much in common, including the basic physical phenomena and technologies involved as well as the commitments and challenges posed by expanding nuclear programs in many countries around the world. The unique characteristics of the fission process -- such as prompt and delayed neutron and gamma ray emission -- not only provide the means of sustaining and controlling the fission chain reaction, but also provide unique ''signatures'' that are essential to quantitative measurement and effective safeguarding of key nuclear materials (notably /sup 239/Pu and /sup 235/U) against theft, loss, or diversion. In this paper, we trace briefly the historical emergence of safeguards as an essential component of the expansion of the nuclear enterprise worldwide. We then survey the major categories of passive and active nondestructive assay techniques that are currently in use or under development for rapid, accurate measurement and verification of safe-guarded nuclear materials in the many forms in which they occur throughout the nuclear fuel cycle. 23 refs., 14 figs.

Keepin, G.R.

1989-01-01T23:59:59.000Z

377

Nuclear Incident Team | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Incident Team | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear...

378

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

379

Nuclear reactor engineering: Reactor design basics. Fourth edition, Volume One  

SciTech Connect (OSTI)

This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in design and operation of nuclear power plants. Extensively updated, the fourth edition includes new material on reactor safety and risk analysis, regulation, fuel management, waste management, and operational aspects of nuclear power. This volume contains the following: energy from nuclear fission; nuclear reactions and radiations; neutron transport; nuclear design basics; nuclear reactor kinetics and control; radiation protection and shielding; and reactor materials.

Glasstone, S.; Sesonske, A.

1994-12-31T23:59:59.000Z

380

National Nuclear Security Administration  

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

FROM: SUBJECT: USIUK Memorandum of Understanding between National Nuclear Security Administration's (NNSA) Associate Administrator for Defense Nuclear Security (AADNS)...

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


381

UNCLASSIFIED//FOR OFFICIAL USE ONLY UNCLASSIFIED//FOR OFFICIAL USE ONLY  

E-Print Network [OSTI]

.gov/vhapublications/ViewPublication.asp?pub_ID=1158 See also, Depleted Uranium Fact Sheet http://www1.va.gov/gulfwar/docs/DepletedUraniumFAQSheet.doc EVALUATION PROTOCOL FOR NON-GULF WAR VETERANS WITH POTENTIAL EXPOSURE TO DEPLETED URANIUM (DU) http://www1.va.gov/vhapublications/ViewPublication.asp?pub_ID=315 EVALUATION PROTOCOL FOR GULF WAR AND IRAQI FREEDOM VETERANS WITH POTENTIAL EXPOSURE TO DEPLETED

Kasman, Alex

382

Nuclear Reactors and Technology; (USA)  

SciTech Connect (OSTI)

Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

Cason, D.L.; Hicks, S.C. (eds.)

1991-01-01T23:59:59.000Z

383

quantph/9811020 Complete quantum teleportation by nuclear  

E-Print Network [OSTI]

quantph/9811020 8 Nov 1998 Complete quantum teleportation by nuclear magnetic resonance M. A operation over interatomic distances using liquid state nuclear magnetic resonance (NMR). The inclusion. Finally, we demonstrate a controlled exploitation of decoherence as a tool to assist in the performance

Crpeau, Claude

384

Nuclear photonics  

SciTech Connect (OSTI)

With the planned new {gamma}-beam facilities like MEGa-ray at LLNL (USA) or ELI-NP at Bucharest (Romania) with 10{sup 13}{gamma}/s and a band width of {Delta}E{gamma}/E{gamma} Almost-Equal-To 10{sup -3}, a new era of {gamma} beams with energies up to 20MeV comes into operation, compared to the present world-leading HI{gamma}S facility at Duke University (USA) with 10{sup 8}{gamma}/s and {Delta}E{gamma}/E{gamma} Almost-Equal-To 3 Dot-Operator 10{sup -2}. In the long run even a seeded quantum FEL for {gamma} beams may become possible, with much higher brilliance and spectral flux. At the same time new exciting possibilities open up for focused {gamma} beams. Here we describe a new experiment at the {gamma} beam of the ILL reactor (Grenoble, France), where we observed for the first time that the index of refraction for {gamma} beams is determined by virtual pair creation. Using a combination of refractive and reflective optics, efficient monochromators for {gamma} beams are being developed. Thus, we have to optimize the total system: the {gamma}-beam facility, the {gamma}-beam optics and {gamma} detectors. We can trade {gamma} intensity for band width, going down to {Delta}E{gamma}/E{gamma} Almost-Equal-To 10{sup -6} and address individual nuclear levels. The term 'nuclear photonics' stresses the importance of nuclear applications. We can address with {gamma}-beams individual nuclear isotopes and not just elements like with X-ray beams. Compared to X rays, {gamma} beams can penetrate much deeper into big samples like radioactive waste barrels, motors or batteries. We can perform tomography and microscopy studies by focusing down to {mu}m resolution using Nuclear Resonance Fluorescence (NRF) for detection with eV resolution and high spatial resolution at the same time. We discuss the dominating M1 and E1 excitations like the scissors mode, two-phonon quadrupole octupole excitations, pygmy dipole excitations or giant dipole excitations under the new facet of applications. We find many new applications in biomedicine, green energy, radioactive waste management or homeland security. Also more brilliant secondary beams of neutrons and positrons can be produced.

Habs, D.; Guenther, M. M.; Jentschel, M.; Thirolf, P. G. [Ludwig-Maximilians-Universitaet Muenchen, D-85748 Garching (Germany); Max Planck Institut fuer Quantenoptik, D-85748 Garching (Germany); Institut Laue-Langevin, F-38042 Grenoble (Germany); Ludwig-Maximilians-Universitaet Muenchen, D-85748 Garching (Germany)

2012-07-09T23:59:59.000Z

385

Tag: nuclear deterrence  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystallineForeign ObjectOUR TableE9. TotalNumberSecurityglobal20/all en

386

Nuclear Data Links  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D Consortium includes Los Alamos April

387

Nuclear Energy Institute  

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

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388

Nuclear Data Links  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls | National Nuclear SecurityLinks to

389

Nuclear and Particle Futures  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls |NavyNuclearLife Cycle |

390

Nuclear testing continues  

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

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391

Contaminant Boundary at the Faultless Underground Nuclear Test  

SciTech Connect (OSTI)

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

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

2003-04-01T23:59:59.000Z

392

The administration, Congress and nuclear testing  

SciTech Connect (OSTI)

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

393

Protection of Use Control Vulnerabilities and Designs  

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

This Manual establishes a general process and provides direction for controlling access and dissemination of Sigma 14 and 15 Weapon Data at the Department of Energy (DOE). It supplements DOE O 452.4, SECURITY AND CONTROL OF NUCLEAR EXPLOSIVES AND NUCLEAR WEAPONS, which establishes DOE requirements and responsibilities to prevent the deliberate unauthorized use of U.S. nuclear explosives and U.S. nuclear weapons. Canceled by DOE M 452.4-1A. Does not cancel other directives.

1999-07-01T23:59:59.000Z

394

Toward a nuclear weapons free world?  

SciTech Connect (OSTI)

Doubts about the wisdom of relying on nuclear weapons are as old as nuclear weapons themselves. But despite this questioning, nuclear weapons came to be seen as the indispensable element of American (indeed Western) security during the Cold War. By the 1970s and 1980s, however, discontent was growing about the intense US-Soviet nuclear arms competition, as it failed to provide any enduring improvement in security; rather, it was seen as creating ever greater risks and dangers. Arms control negotiations and limitations, adopted as a means to regulate the technical competition, may also have relieved some of the political pressures and dangers. But the balance of terror, and the fears of it, continued. The Strategic Defense Initiative (SDI) under President Reagan was a very different approach to escaping from the precarious protection of nuclear weapons, in that it sought a way to continue to defend the US and the West, but without the catastrophic risks of mutual deterrence. As such, SDI connoted unhappiness with the precarious nuclear balance and, for many, with nuclear weapons in general. The disappearance of the Warsaw Pact, the disintegration of the Soviet Union, and the sudden end of the Cold War seemed to offer a unique opportunity to fashion a new, more peaceful world order that might allow for fading away of nuclear weapons. Scholars have foreseen two different paths to a nuclear free world. The first is a fundamental improvement in the relationships between states such that nuclear weapons are no longer needed. The second path is through technological development, e.g., missile defenses which could provide effective protection against nuclear attacks. The paper discusses nuclear weapon policy in the US, views of other nuclear states, the future of nuclear weapons, and issues in a less-nuclear world.

Maaranen, S.A. [Los Alamos National Lab., NM (United States). Center for International Security Affairs

1996-09-01T23:59:59.000Z

395

Nuclear Forensics  

National Nuclear Security Administration (NNSA)

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396

Nuclear Science  

Office of Environmental Management (EM)

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397

Nuclear Astrophysics  

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

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398

Nuclear Technology Programs  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

Harmon, J.E. (ed.)

1990-10-01T23:59:59.000Z

399

AQUATIC PLANT CONTROL RESEARCH PROGRAM  

E-Print Network [OSTI]

States. Since East Africa forms part of the natural distribution of hydrilla, a search for potential;Unclassified SECURITY CLASSIFICATION C' [HIS PAGE(Wh., D.t.£nle,ed) 20. ABSTRACT (Continued). distribution, despite an intensive search, only a single population, probably of exotic origin, was found. The range

US Army Corps of Engineers

400

Nuclear criticality safety: 2-day training course  

SciTech Connect (OSTI)

This compilation of notes is presented as a source reference for the criticality safety course. At the completion of this training course, the attendee will: be able to define terms commonly used in nuclear criticality safety; be able to appreciate the fundamentals of nuclear criticality safety; be able to identify factors which affect nuclear criticality safety; be able to identify examples of criticality controls as used as Los Alamos; be able to identify examples of circumstances present during criticality accidents; have participated in conducting two critical experiments; be asked to complete a critique of the nuclear criticality safety training course.

Schlesser, J.A. [ed.] [comp.

1997-02-01T23:59:59.000Z

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


401

Nuclear Navy Turns 50 | National Nuclear Security Administration  

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

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402

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

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

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403

Nuclear Waste Policy Act Signed | National Nuclear Security Administration  

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

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404

Managing nuclear predominant generating capacity  

SciTech Connect (OSTI)

The most common belief, associated with nuclear power plant, leads to the conclusion that it can only operate, as a base load plant. This observation can be reversed, by just looking at large generating capacity, using an important nuclear generation mix. Nuclear plants may certainly load follow and contribute to the grid frequency control. The French example illustrates these possibilities. The reactor control of French units has been customized to accommodate the grid requests. Managing such a large nuclear plant fleet requires various actions be taken, ranging from a daily to a multi-annual perspective. The paper describes the various contributions leading to safe, reliable, well accepted and cost competitive nuclear plants in France. The combination of all aspects related to operations, maintenance scheduling, nuclear safety management, are presented. The use of PWR units carries considerable weight in economic terms, with several hundred million francs tied in with outage scheduling every year. This necessitates a global view of the entire generating system which can be mobilized to meet demand. There is considerable interaction between units as, on the one hand, they are competing to satisfy the same need, and, on the other hand, reducing maintenance costs means sharing the necessary resources, and thus a coordinated staggering of outages. In addition, nuclear fuel is an energy reserve which remains in the reactor for 3 or 4 years, with some of the fuel renewed each year. Due to the memory effect, the fuel retains a memory of past use, so that today's choices impact upon the future. A medium-term view of fuel management is also necessary.

Bouget, Y.H.; Herbin, H.C.; Carbonnier, D.

1998-07-01T23:59:59.000Z

405

Long-Term Nuclear Industry Outlook - 2004  

SciTech Connect (OSTI)

The nuclear industry has become increasingly efficient and global in nature, but may now be poised at a crossroads between graceful decline and profound growth as a viable provider of electrical energy. Predicted population and energy-demand growth, an increased interest in global climate change, the desire to reduce the international dependence on oil as an energy source, the potential for hydrogen co-generation using nuclear power reactors, and the improved performance in the nuclear power industry have raised the prospect of a nuclear renaissance in which nuclear power would play an increasingly more important role in both domestic and international energy market. This report provides an assessment of the role nuclear-generated power will plan in the global energy future and explores the impact of that role on export controls.

Reichmuth, Barbara A.; Wood, Thomas W.; Johnson, Wayne L.

2004-09-30T23:59:59.000Z

406

Nuclear Forensics | More Science | ORNL  

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

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407

Nuclear Forensics | More Science | ORNL  

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

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408

Nuclear Fuels | Department of Energy  

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

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409

Nuclear Medicine | More Science | ORNL  

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

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410

Nuclear Safeguards and Security Challenge:  

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

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411

Nuclear Science | More Science | ORNL  

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

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412

Nuclear Sciences | More Science | ORNL  

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

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413

Nuclear Energy | Argonne National Laboratory  

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

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414

Reactor & Nuclear Systems Publications | ORNL  

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

Nuclear Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications...

415

Undergraduate reactor control experiment  

SciTech Connect (OSTI)

A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise.

Edwards, R.M.; Power, M.A.; Bryan, M. (Pennsylvania State Univ., University Park (United States))

1992-01-01T23:59:59.000Z

416

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

SciTech Connect (OSTI)

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

417

Nuclear Weapon Surety Interface with the Department of Defense  

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

The Order prescribes how the Department of Energy participates with the Department of Defense (DoD) to ensure the surety (safety, security and control) of military nuclear weapon systems deployed around the world. The Order establishes National Nuclear Security Administration requirements and responsibilities for addressing joint nuclear weapon and nuclear weapon system surety activities in conjunction with the DoD. Cancels DOE O 5610.13. Canceled by DOE O 452.6A.

2006-10-19T23:59:59.000Z

418

Nuclear Explosive Safety  

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

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, or successor directive, for routine and planned nuclear explosive operations (NEOs).

2015-01-26T23:59:59.000Z

419

Nuclear Explosive Safety  

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

The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

2014-07-10T23:59:59.000Z

420

RELATIVISTIC NUCLEAR COLLISIONS: THEORY  

E-Print Network [OSTI]

Effects in Relativistic Nuclear Collisions", Preprint LBL-Pion Interferometry of Nuclear Collisions. 18.1 M.Gyulassy,was supported by the Office of Nuclear Physics of the U.S.

Gyulassy, M.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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 STRUCTURE DATABASE  

E-Print Network [OSTI]

CALIFORNIA NUCLEAR STRUCTURE DATABASE R. B. Firestone and E.11089 NUCLEAR STRUCTURE DATABASE by R.B. Firestone and E.iii- NUCLEAR STRUCTURE DATABASE R.B Firestone and E. Browne

Firestone, R.B.

2010-01-01T23:59:59.000Z

422

Nuclear Safety (Pennsylvania)  

Broader source: Energy.gov [DOE]

The Nuclear Safety Division conducts a comprehensive nuclear power plant oversight review program of the nine reactors at the five nuclear power sites in Pennsylvania. It also monitors the...

423

ATTACHMENT 1 Export Control Decision Tree 1  

E-Print Network [OSTI]

Information with Foreign Nationals United States export controls exist to protect the national security applicability (examples are nuclear, biological, or chemical weapons and satellite technology with military

Howitt, Ivan

424

Nuclear Fuel Cycle & Vulnerabilities  

SciTech Connect (OSTI)

The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

Boyer, Brian D. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

425

Control Categories Control Category  

E-Print Network [OSTI]

/ Conversion Controls Controls over moving data between computer systems. Process used to migrate data fromControl Categories Control Category Legend Description Example Authorization Approval policies and procedures. Authorization limits. Configuration/ Account Mapping "Switches" to secure data

426

Nuclear Safeguards | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

427

Nuclear Forensics | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

428

Nuclear Power Overview  

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

San Onofre Nuclear Generating Station San Onofre Nuclear Generating Station Bob Ashe-Everest Southern California Edison 10 Incoming New Fuel Inspecting New Fuel SONGS Unit 1 Fuel...

429

Nuclear weapons modernizations  

SciTech Connect (OSTI)

This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

Kristensen, Hans M. [Federation of American Scientists, Washington, DC (United States)

2014-05-09T23:59:59.000Z

430

Nuclear Energy Advisory Committee  

Broader source: Energy.gov [DOE]

The Nuclear Energy Advisory Committee (NEAC), formerly the Nuclear Energy Research Advisory Committee (NERAC), was established on October 1, 1998, to provide independent advice to the Office of...

431

National Nuclear Security Administration  

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

the safety, security and effectiveness of the nuclear deterrent without underground nuclear testing, consistent with the principles of the Stockpile Management Program...

432

Nuclear Waste Reduction  

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

Nuclear Waste Reduction Pyroprocessing is a promising technology for recycling used nuclear fuel and improving the associated waste management options. The process...

433

Control of Improvised Nuclear Device Information  

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

This Manual is for OFFICIAL USE ONLY and will not be distributed on the Directives Portal. For distribution please contact Randall Weidman, 202-586-4582, internet: randall.weidman@nnsa.doe.gov. Canceled by DOE O 457.1A.

2006-08-10T23:59:59.000Z

434

Nonproliferation and Arms Control | National Nuclear Security  

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

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435

Material Control & Accountability | National Nuclear Security  

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

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436

AEC and control of nuclear weapons  

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

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437

Nuclear sensor signal processing circuit  

DOE Patents [OSTI]

An apparatus and method are disclosed for a compact and temperature-insensitive nuclear sensor that can be calibrated with a non-hazardous radioactive sample. The nuclear sensor includes a gamma ray sensor that generates tail pulses from radioactive samples. An analog conditioning circuit conditions the tail-pulse signals from the gamma ray sensor, and a tail-pulse simulator circuit generates a plurality of simulated tail-pulse signals. A computer system processes the tail pulses from the gamma ray sensor and the simulated tail pulses from the tail-pulse simulator circuit. The nuclear sensor is calibrated under the control of the computer. The offset is adjusted using the simulated tail pulses. Since the offset is set to zero or near zero, the sensor gain can be adjusted with a non-hazardous radioactive source such as, for example, naturally occurring radiation and potassium chloride.

Kallenbach, Gene A. (Bosque Farms, NM); Noda, Frank T. (Albuquerque, NM); Mitchell, Dean J. (Tijeras, NM); Etzkin, Joshua L. (Albuquerque, NM)

2007-02-20T23:59:59.000Z

438

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

E-Print Network [OSTI]

Security of the National Nuclear Security Administration, USof Energys National Nuclear Security Administration (NNSA)

Quiter, Brian

2012-01-01T23:59:59.000Z

439

Nuclear Energy!  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory | NationalJohnSecurityControls | National

440

Nuclear reactor  

DOE Patents [OSTI]

A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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

Exhibit G / working draft  

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

have access to or process any LANL Controlled Unclassified Information such as OUO, LPI, PII, UCI, UCNI, or any other sensitive unclassified data that needs to be protected in...

442

The Joys of Nuclear Engineering  

SciTech Connect (OSTI)

Nuclear fuels researcher Jon Carmack talks about the satisfactions of a career in nuclear engineering.

Jon Carmack

2009-10-02T23:59:59.000Z

443

The Joys of Nuclear Engineering  

ScienceCinema (OSTI)

Nuclear fuels researcher Jon Carmack talks about the satisfactions of a career in nuclear engineering.

Jon Carmack

2010-01-08T23:59:59.000Z

444

Gas Centrifuges and Nuclear Proliferation  

SciTech Connect (OSTI)

Gas centrifuges have been an ideal enrichment method for a wide variety of countries. Many countries have built gas centrifuges to make enriched uranium for peaceful nuclear purposes. Other countries have secretly sought centrifuges to make highly enriched uranium for nuclear weapons. In more recent times, several countries have secretly sought or built gas centrifuges in regions of tension. The main countries that have been of interest in the last two decades have been Pakistan, Iraq, Iran, and North Korea. Currently, most attention is focused on Iran, Pakistan, and North Korea. These states did not have the indigenous abilities to make gas centrifuges, focusing instead on illicit and questionable foreign procurement. The presentation covered the following main sections: Spread of centrifuges through illicit procurement; Role of export controls in stopping proliferation; Increasing the transparency of gas centrifuge programs in non-nuclear weapon states; and, Verified dismantlement of gas centrifuge programs. Gas centrifuges are important providers of low enriched uranium for civil nuclear power reactors. They also pose special nuclear proliferation risks. We all have special responsibilities to prevent the spread of gas centrifuges into regions of tension and to mitigate the consequences of their spread into the Middle East, South Asia, and North Asia.

Albright, David

2004-09-15T23:59:59.000Z

445

NEW - DOE O 452.1E, Nuclear Explosive and Weapon Surety Program  

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

All nuclear explosives and nuclear explosive operations require special safety, security, and use control consideration because of the potentially unacceptable consequences of an accident or unauthorized act; therefore, a Nuclear Explosive and Weapon Surety (NEWS) Program is established to prevent unintended/unauthorized detonation and deliberate unauthorized use of nuclear explosives.

446

395NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 CONSTRUCTION OF AN ENVIRONMENTAL RADON  

E-Print Network [OSTI]

395NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 CONSTRUCTION OF AN ENVIRONMENTAL RADON MONITORING SYSTEM USING CR-39 NUCLEAR TRACK DETECTORS GIL HOON AHN* and JAI-KI LEE1 National Nuclear Management & Control Agency 305-600, POX 114 Yuseong, Daejeon, Korea 1 Dept. of Nuclear

447

Advanced nuclear fuel  

ScienceCinema (OSTI)

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-15T23:59:59.000Z

448

Advanced nuclear fuel  

SciTech Connect (OSTI)

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-14T23:59:59.000Z

449

Focus Article Nuclear winter  

E-Print Network [OSTI]

the climatic effects of nuclear war. Smoke from the fires started by nuclear weapons, especially the black in recorded human history. Although the number of nuclear weapons in the world has fallen from 70,000 at its and Russia could still produce nuclear winter. This theory cannot be tested in the real world. However

Robock, Alan

450

INSTRUCTIONS FOR SUBMITTING NUCLEAR  

E-Print Network [OSTI]

. Decommissioning 13 I. Performance 13 J. Nuclear Fuel 14 K. Nuclear Insurance 14 L. Relicensing or Plant RetirementCALIFORNIA ENERGY COMMISSION INSTRUCTIONS FOR SUBMITTING NUCLEAR POWER PLANT-RELATED DATA of Submitted Data 3 NUCLEAR POWER PLANT DATA REQUESTS 6 A. Environmental Impacts 6 B. Spent Fuel Generation 8 C

451

Nuclear Science & Engineering  

E-Print Network [OSTI]

. 1 Nuclear Science & Engineering Nuclear Energy Present and Future Ian H. Hutchinson Head, Department of Nuclear Science and Engineering CoPrincipal, Alcator Tokamak Project, Plasma Science and Fusion Science & Engineering Nuclear Power Plants Worldwide · US: 103 plants in operation, none under

452

Protection of Use Control Vulnerabilities and Design  

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

This manual establishes a general process and provides direction for controlling access to and disseminating Sigma 14 and 15 nuclear weapon data (NWD) at the Department of Energy (DOE). It supplements DOE O 452.4A, Security and Control of Nuclear Explosives and Nuclear Weapons, dated 12-17-01, which establishes DOE requirements and responsibilities to prevent the deliberate unauthorized use of U.S. nuclear explosives and nuclear weapons. Cancels DOE M 452.4-1. Canceled by DOE O 452.7, 5-14-2010

2004-03-11T23:59:59.000Z

453

PLC-Based Safety Critical Software Development for Nuclear Power Plants  

E-Print Network [OSTI]

PLC-Based Safety Critical Software Development for Nuclear Power Plants Junbeom Yoo1 , Sungdeok Cha development technique for nuclear power plants'I&C soft- ware controllers. To improve software safety, we in developing safety-critical control software for a Korean nuclear power plant, and experience to date has been

454

National Center for Nuclear Security - NCNS  

ScienceCinema (OSTI)

As the United States embarks on a new era of nuclear arms control, the tools for treaty verification must be accurate and reliable, and must work at stand-off distances. The National Center for Nuclear Security, or NCNS, at the Nevada National Security Site, is poised to become the proving ground for these technologies. The center is a unique test bed for non-proliferation and arms control treaty verification technologies. The NNSS is an ideal location for these kinds of activities because of its multiple environments; its cadre of experienced nuclear personnel, and the artifacts of atmospheric and underground nuclear weapons explosions. The NCNS will provide future treaty negotiators with solid data on verification and inspection regimes and a realistic environment in which future treaty verification specialists can be trained. Work on warhead monitoring at the NCNS will also support future arms reduction treaties.

None

2015-01-09T23:59:59.000Z

455

National Center for Nuclear Security - NCNS  

SciTech Connect (OSTI)

As the United States embarks on a new era of nuclear arms control, the tools for treaty verification must be accurate and reliable, and must work at stand-off distances. The National Center for Nuclear Security, or NCNS, at the Nevada National Security Site, is poised to become the proving ground for these technologies. The center is a unique test bed for non-proliferation and arms control treaty verification technologies. The NNSS is an ideal location for these kinds of activities because of its multiple environments; its cadre of experienced nuclear personnel, and the artifacts of atmospheric and underground nuclear weapons explosions. The NCNS will provide future treaty negotiators with solid data on verification and inspection regimes and a realistic environment in which future treaty verification specialists can be trained. Work on warhead monitoring at the NCNS will also support future arms reduction treaties.

None

2014-11-12T23:59:59.000Z

456

Isotope Development & Production | Nuclear Science | ORNL  

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

Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery |...

457

Economic Globalization and a Nuclear Renaissance  

SciTech Connect (OSTI)

The phenomenon of globalization has become increasingly well recognized, documented, and analyzed in the last several years. Globalization, the integration of markets and intra-firm competition on a worldwide basis, involves complex behavioral and mindset changes within a firm that facilitate global competition. The changes revolve around efficient information flow and rapid deployment of technology. The objective of this report is to examine the probable characteristics of a global nuclear renaissance and its broad implications for industry structure and export control relative to nuclear technology. The question of how a modern renaissance would affect the trend toward globalization of the nuclear industry is addressed.

Wood, Thomas W.; Johnson, Wayne L.; Parker, Brian M.

2001-10-22T23:59:59.000Z

458

Nuclear Physics Technology Saves Lives | Jefferson Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclear PairsNuclear Physics

459

Nuclear Physics: User/Researcher Information  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclear PairsNuclear

460

Nuclear Science & Engineering Monthly Reports | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguards and Nuclear Science

Note: This page contains sample records for the topic "unclassified controlled nuclear" 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.


461

Nuclear Structure Aspects in Nuclear Astrophysics  

SciTech Connect (OSTI)

Nuclear Astrophysics as a broad and diverse field of study can be viewed as a magnifier of the impact of microscopic processes on the evolution of macroscopic events. One of the primary goals in Nuclear Astrophysics is the understanding of the nucleosynthesis processes that take place in the cosmos and the simulation of the correlated stellar and explosive burning scenarios. These simulations are strongly dependent on the input from Nuclear Physics which sets the time scale for all stellar dynamic processes--from giga-years of stellar evolution to milliseconds of stellar explosions--and provides the basis for most of the signatures that we have for the interpretation of these events--from stellar luminosities, elemental and isotopic abundances to neutrino flux from distant supernovae. The Nuclear Physics input comes through nuclear structure, low energy reaction rates, nuclear masses, and decay rates. There is a common perception that low energy reaction rates are the most important component of the required nuclear physics input; however, in this article we take a broader approach and present an overview of the close correlation between various nuclear structure aspects and their impact on nuclear astrophysics. We discuss the interplay between the weak and the strong forces on stellar time scales due to the limitations they provide for the evolution of slow and rapid burning processes. The effects of shell structure in nuclei on stellar burning processes as well as the impact of clustering in nuclei is outlined. Furthermore we illustrate the effects of the various nuclear structure aspects on the major nucleosynthesis processes that have been identified in the last few decades. We summarize and provide a coherent overview of the impact of all aspects of nuclear structure on nuclear astrophysics.

Smith, Michael Scott [ORNL

2006-12-01T23:59:59.000Z

462

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

463

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

464

Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station  

U.S. Energy Information Administration (EIA) Indexed Site

Pilgrim Nuclear Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License...

465

Arkansas Nuclear Profile - Arkansas Nuclear One  

U.S. Energy Information Administration (EIA) Indexed Site

Nuclear One" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

466

Nucleon sigma term and quark condensate in nuclear matter  

SciTech Connect (OSTI)

We study the bound nucleon sigma term and its effect on the quark condensate in nuclear matter. In the quark-meson coupling (QMC) model it is shown that the nuclear correction to the sigma term is small and negative. Thus, the correction decelerates the decrease of the quark condensate in nuclear matter. However, the quark condensate in nuclear matter is controlled primarily by the scalar-isoscalar sigma field of the model. It appreciably moderates the decrease relative to the leading term at densities around and larger than the normal nuclear matter density.

K. Tsushima; K. Saito; A. W. Thomas; A. Valcarce

2007-03-01T23:59:59.000Z

467

Dynamics of nuclear envelope and nuclear pore complex formation  

E-Print Network [OSTI]

Limited expression of nuclear pore membrane glycoprotein 210suggests cell-type specific nuclear pores in metazoans. Expand Dultz, E. (2008). Nuclear pore complex assembly through

Anderson, Daniel J.

2008-01-01T23:59:59.000Z

468

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network [OSTI]

Organizations, accidents, and nuclear weapons. Princeton,the likelihood of a nuclear accident (Sagan 1993, 1995). potential for a nuclear accident. Yet it seems implausible

Kroenig, Matthew

2006-01-01T23:59:59.000Z

469

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network [OSTI]

nature of the nuclear recipients security environment. ThisKeywords: Nuclear weapons proliferation; security; securitynature of the nuclear recipients security environment. This

Kroenig, Matthew

2006-01-01T23:59:59.000Z

470

Nuclear Materials Management Program at the NNSS  

SciTech Connect (OSTI)

The Nevada National Security Site (NNSS), formerly the Nevada Test Site, was established in 1951 mainly for weapons testing; because special nuclear materials (SNM) were expended during the tests, a nuclear material management program was not required. That changed in December 2004 with the receipt of Category I SNM for purposes other than weapons testing. At that time, Material Control and Accountability and Nuclear Material Management were a joint laboratory (Los Alamos and Lawrence Livermore) effort with nuclear material management being performed at the laboratories. That changed in March 2006 when the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office appointed sole responsibility to the Management and Operations (M&O) contractor, National Security Technologies, LLC (NSTec). Since 2006 the basic nuclear material management work was completed by a combination of M&O employees and subcontractors, but a true Nuclear Material Management (NMM) Program was not determined to be necessary until recently. With expanding missions and more nuclear material (NM) coming to the NNSS, it became imperative to have an organization to manage these materials; therefore, an NMM Manager was officially appointed by NSTec in 2012. In June 2011 a Gap Analysis and white paper was completed by a subcontractor; this presentation will include highlights from those documents along with our plans to resolve the gaps and stand up a functional and compliant NMM Program at the NNSS.

,

2012-06-08T23:59:59.000Z

471

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

E-Print Network [OSTI]

Nuclear Laboratories, AECL, Chalk River, Ontario, Canada.Nuclear Laboratories, AECL, Chalk River, Ontario, Canada. 1.Nuclear Laboratories, AECL, Chalk River, Ontario, Canada. 1.

Authors, Various

2011-01-01T23:59:59.000Z

472

Nuclear Safety Research and Development...  

Energy Savers [EERE]

Nuclear Safety Research and Development Proposal Review and Prioritization Process and Criteria Nuclear Safety Research and Development Program Office of Nuclear Safety Office of...

473

What is spent nuclear fuel?  

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

What is Spent Nuclear Fuel? Spent nuclear fuel (SNF) is irradiated fuel or targets containing uranium, plutonium, or thorium that is permanently withdrawn from a nuclear reactor or...

474

Is Nuclear Energy the Solution?  

E-Print Network [OSTI]

009-0270-y Is Nuclear Energy the Solution? Milton H. Saier &in the last 50 years, nuclear energy subsidies have totaledadministration, the Global Nuclear Energy Partnership (GNEP)

Saier, Milton H.; Trevors, Jack T.

2010-01-01T23:59:59.000Z

475

NUCLEAR SCIENCE ANNUAL REPORT 1975  

E-Print Network [OSTI]

Gove and A. H. Wapstra, Nuclear Data Tables 11, 127 (1972).P. Jackson, Chalk River Nuclear Laboratories Report (1975)national Conference on Nuclear Structure and Spec troscopy,

Authors, Various

2010-01-01T23:59:59.000Z

476

Nuclear & Radiological Activity Center (NRAC)  

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

Nuclear & Radiological Activity Center (NRAC) Where nuclear research and deployment capabilities come together to solve nuclear nonproliferation challenges. Skip Navigation Links...

477

Responsible stewardship of nuclear materials  

SciTech Connect (OSTI)

The ability to tap the massive energy potential of nuclear fission was first developed as a weapon to end a terrible world war. Nuclear fission is also a virtually inexhaustible energy resource, and is the only energy supply in certain areas in Russia, Kazakhstan and elsewhere. The potential link between civilian and military applications has been and continues to be a source of concern. With the end of the Cold War, this issue has taken a dramatic turn. The U.S. and Russia have agreed to reduce their nuclear weapons stockpiles by as much as two-thirds. This will make some 100 tonnes of separated plutonium and 500 tonnes of highly enriched uranium available, in a form that is obviously directly usable for weapons. The total world inventory of plutonium is now around 1000 tonnes and is increasing at 60-70 tonnes per year. There is even more highly enriched uranium. Fortunately the correct answer to what to do with excess weapons material is also the most attractive. It should be used and reused as fuel for fast reactors. Material in use (particularly nuclear material) is very easy to monitor and control, and is quite unattractive for diversion. Active management of fissile materials not only makes a major contribution to economic stability and well-being, but also simplifies accountability, inspection and other safeguards processes; provides a revenue stream to pay for the necessary safeguards; and, most importantly, limits the prospective world inventory of plutonium to only that which is used and useful.

Hannum, W.H.

1994-10-01T23:59:59.000Z

478

Internal Control Program  

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

To ensure sound internal controls and overall consistency in exercising the statutory authorities that vest in the Secretary, the Administrator, National Nuclear Security Administration (NNSA), and Department's Chief Financial Officer (CFO), and to implement the Federal Managers' Financial Integrity Act of 1982 and related central agency guidance. Cancels DOE O 413.1A.

2008-10-28T23:59:59.000Z

479

Climate Change, Nuclear Power and Nuclear  

E-Print Network [OSTI]

Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters Rob Goldston MIT IAP plays a large role in replacing coal red plants. al hydro electricity options penetrate in the climate way across scenarios, showing a slight severe climate targets. In Industry, the climate target has

480

Self-Reliability and Motivation in a Nuclear Security Culture Enhancement Program  

SciTech Connect (OSTI)

The threat of nuclear terrorism has become a global concern. Many countries continue to make efforts to strengthen nuclear security by enhancing systems of nuclear material protection, control, and accounting (MPC&A). Though MPC&A systems can significantly upgrade nuclear security, they do not eliminate the "human factor." This paper will describe some of the key elements of a comprehensive, sustainable nuclear security culture enhancement program and how implementation can mitigate the insider threat.

Crawford,C.; de Boer,G.; De Castro, K; Landers, Ph.D., J; Rogers, E

2009-10-19T23:59:59.000Z

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


481

Triangle Universities Nuclear Laboratory  

SciTech Connect (OSTI)

This report contains brief papers that discusses the following topics: Fundamental Symmetries in the Nucleus; Internucleon Interactions; Dynamics of Very Light Nuclei; Facets of the Nuclear Many-Body Problem; and Nuclear Instruments and Methods.

Not Available

1991-01-01T23:59:59.000Z

482

Hegemony and nuclear proliferation  

E-Print Network [OSTI]

Contrary to longstanding of predictions of nuclear tipping points, the number of states interested in nuclear weapons has sharply declined in recent decades. In contrast to existing explanations, this dissertation argues ...

Miller, Nicholas L. (Nicholas LeSuer)

2014-01-01T23:59:59.000Z

483

Promulgating Nuclear Safety Requirements  

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

Applies to all Nuclear Safety Requirements Adopted by the Department to Govern the Conduct of its Nuclear Activities. Cancels DOE P 410.1. Canceled by DOE N 251.85.

1996-05-15T23:59:59.000Z

484

Nuclear Engineer (Criticality Safety)  

Broader source: Energy.gov [DOE]

This position is located in the Nuclear Safety Division (NSD) which has specific responsibility for managing the development, analysis, review, and approval of non-reactor nuclear facility safety...

485

Nuclear radiation actuated valve  

DOE Patents [OSTI]

A nuclear radiation actuated valve for a nuclear reactor. The valve has a valve first part (such as a valve rod with piston) and a valve second part (such as a valve tube surrounding the valve rod, with the valve tube having side slots surrounding the piston). Both valve parts have known nuclear radiation swelling characteristics. The valve's first part is positioned to receive nuclear radiation from the nuclear reactor's fuel region. The valve's second part is positioned so that its nuclear radiation induced swelling is different from that of the valve's first part. The valve's second part also is positioned so that the valve's first and second parts create a valve orifice which changes in size due to the different nuclear radiation caused swelling of the valve's first part compared to the valve's second part. The valve may be used in a nuclear reactor's core coolant system.

Christiansen, David W. (Kennewick, WA); Schively, Dixon P. (Richland, WA)

1985-01-01T23:59:59.000Z

486

General Engineer (Nuclear Safety)  

Broader source: Energy.gov [DOE]

The Chief of Nuclear Safety (CNS) reports the US/M&P; in serving as the Central Technical Authority (CTA) for M&P; activities, ensuring the Departments nuclear safety policies and...

487

Nuclear Multifragmentation Critical Exponents  

E-Print Network [OSTI]

We show that the critical exponents of nuclear multi-fragmentation have not been determined conclusively yet.

Wolfgang Bauer; William Friedman

1994-11-14T23:59:59.000Z

488

Nuclear Explosive Safety Manual  

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

This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

2009-04-14T23:59:59.000Z

489

3D NUCLEAR SEGMENTAT  

Energy Science and Technology Software Center (OSTI)

003029WKSTN00 Delineation of nuclear structures in 3D multicellular systems https://vision.lbl.gov/Software/3DMorphometry/

490

Nuclear power browning out  

SciTech Connect (OSTI)

When the sad history of nuclear power is written, April 26, 1986, will be recorded as the day the dream died. The explosion at the Chernobyl plant was a terrible human tragedy- and it delivered a stark verdict on the hope that nuclear power will one day replace fossil fuel-based energy systems. Nuclear advocates may soldier on, but a decade after Chernobyl it is clear that nuclear power is no longer a viable energy option for the twenty-first century.

Flavin, C.; Lenssen, N.

1996-05-01T23:59:59.000Z

491

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

E-Print Network [OSTI]

of the Institute of Nuclear Material Management, Tucson, AZ,Assay, Institute of Nuclear Materials Management 51st Annual

Quiter, Brian

2012-01-01T23:59:59.000Z

492

Nuclear Explosive Safety  

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

This Order establishes requirements to implement the nuclear explosive safety elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations. Cancels DOE O 452.2C. Admin Chg 1, 7-10-13

2009-04-14T23:59:59.000Z

493

Nuclear Explosive Safety  

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

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs). Cancels DOE O 452.2C. Admin Chg 1, dated 7-10-13, cancels DOE O 452.2D.

2009-04-14T23:59:59.000Z

494

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

495

Nuclear explosives testing readiness evaluation  

SciTech Connect (OSTI)

This readiness evaluation considers hole selection and characterization, verification, containment issues, nuclear explosive safety studies, test authorities, event operations planning, canister-rack preparation, site preparation, diagnostic equipment setup, device assembly facilities and processes, device delivery and insertion, emplacement, stemming, control room activities, readiness briefing, arming and firing, test execution, emergency response and reentry, and post event analysis to include device diagnostics, nuclear chemistry, and containment. This survey concludes that the LLNL program and its supporting contractors could execute an event within six months of notification, and a second event within the following six months, given the NET group`s evaluation and the following three restraints: (1) FY94 (and subsequent year) funding is essentially constant with FY93, (2) Preliminary work for the initial event is completed to the historical sic months status, (3) Critical personnel, currently working in dual use technologies, would be recallable as needed.

Valk, T.C.

1993-09-01T23:59:59.000Z

496

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 m