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اعانه 15 سپتمبر 2024 – 1 اکتبر2024 د پیسو د راټولولو په اړه

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اعانه 15 سپتمبر 2024 – 1 اکتبر2024

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دقیق مطابقت والی

دقیق مطابقت والی

کتابونه (211)
مشهورترین
لیسټ
- لیسټ
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1

Flywheel energy storage workshop

Flywheel energy storage workshop

O'Kain, D., Carmack, J., Oak Ridge National Laboratory., United States. Dept. of Energy. Office of Energy Efficiency and Renewable Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1995

ژبه:

english

فایل:

PDF, 33.51 MB

0 / 0

english, 1995

2

Nuclear air cleaning handbook : design, construction, and testing of high-efficiency air cleaning systems for nuclear application

Nuclear air cleaning handbook : design, construction, and testing of high-efficiency air cleaning systems for nuclear application

C A Burchsted, J E Kahn, A B Fuller, Oak Ridge National Laboratory

کال:

1969

ژبه:

english

فایل:

PDF, 36.75 MB

0 / 0

english, 1969

3

Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors : Comparison of UO2 and MOX Fuels

Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors : Comparison of UO2 and MOX Fuels

J J Carbajo, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2004

ژبه:

english

فایل:

PDF, 2.17 MB

0 / 0

english, 2004

4

Thermophysical Properties of Heat Resistant Shielding Material

Thermophysical Properties of Heat Resistant Shielding Material

W D Porter, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2004

ژبه:

english

فایل:

PDF, 1.03 MB

0 / 0

english, 2004

5

Advanced Molten-Salt Reactor Using High-Temperature Tech [pres. slides]

Advanced Molten-Salt Reactor Using High-Temperature Tech [pres. slides]

کال:

2004

ژبه:

english

فایل:

PDF, 756 KB

0 / 0

english, 2004

6

Elevated-Temp Ferritic, Martensitic Steels - Applications to Future Nuclear Reactors

Elevated-Temp Ferritic, Martensitic Steels - Applications to Future Nuclear Reactors

کال:

2004

ژبه:

english

فایل:

PDF, 3.02 MB

0 / 0

english, 2004

7

On angular momentum

On angular momentum

Julian Schwinger

کال:

1952

ژبه:

english

فایل:

PDF, 5.47 MB

0 / 0

english, 1952

8

Design Parameters - Natural Uranium-Fuelled Nuclear Reactor

Design Parameters - Natural Uranium-Fuelled Nuclear Reactor

کال:

2002

ژبه:

english

فایل:

PDF, 265 KB

0 / 0

english, 2002

9

An updated nuclear criticality slide rule

An updated nuclear criticality slide rule

C M Hopper, B L Broadhead, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Regulatory Applications., Oak Ridge National Laboratory

کال:

1998

ژبه:

english

فایل:

PDF, 2.40 MB

0 / 0

english, 1998

10

Carbon-Carbon Composite Molten-Salt Cooled Space Reactors [pres. slides]

Carbon-Carbon Composite Molten-Salt Cooled Space Reactors [pres. slides]

کال:

2005

ژبه:

english

فایل:

PDF, 1.97 MB

0 / 0

english, 2005

11

Early Test Facilities, Analytical Methods for Radiation Shielding

Early Test Facilities, Analytical Methods for Radiation Shielding

کال:

1992

ژبه:

english

فایل:

PDF, 14.20 MB

0 / 0

english, 1992

12

Nuclear Hydrogen for Peak Electricity Production and Spinning Reserve

Nuclear Hydrogen for Peak Electricity Production and Spinning Reserve

C W Forsberg, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2004

ژبه:

english

فایل:

PDF, 1.20 MB

0 / 0

english, 2004

13

Reactors with Molten Salts - Options and Missions [pres. slides]

Reactors with Molten Salts - Options and Missions [pres. slides]

کال:

2004

ژبه:

english

فایل:

PDF, 3.16 MB

0 / 0

english, 2004

14

Packaging supplier inspection guide

Packaging supplier inspection guide

H M Stromberg, U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards. Division of Safeguards and Transportation., Idaho National Engineering Laboratory., EG & G Idaho., et al

کال:

1998

ژبه:

english

فایل:

PDF, 41.87 MB

0 / 0

english, 1998

15

Characterization of Large Liquid Scintillation Detectors

Characterization of Large Liquid Scintillation Detectors

S A Pozzi, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2003

ژبه:

english

فایل:

PDF, 305 KB

0 / 0

english, 2003

16

Computational Instrumentation for Nano- and Condensed Matter Sciences

Computational Instrumentation for Nano- and Condensed Matter Sciences

کال:

2005

ژبه:

english

فایل:

PDF, 1.94 MB

0 / 0

english, 2005

17

Check Valve Degradation, Failure Exper. in Nucl. Pwr Ind. (1984-1990) Vol 1

Check Valve Degradation, Failure Exper. in Nucl. Pwr Ind. (1984-1990) Vol 1

کال:

1994

ژبه:

english

فایل:

PDF, 20.17 MB

0 / 0

english, 1994

18

Economics of Future Electric Power Generation Options [fusion]

Economics of Future Electric Power Generation Options [fusion]

کال:

2000

ژبه:

english

فایل:

PDF, 226 KB

0 / 0

english, 2000

19

High Flux Isotope Reactor Cold Neutron Source Reference Design

High Flux Isotope Reactor Cold Neutron Source Reference Design

Selby, Lucas, Hyman, Freels, Wiliams, Chang, Hill, various

کال:

1998

ژبه:

english

فایل:

PDF, 22.49 MB

0 / 0

english, 1998

20

Advanced Neutron Src Reactor Thermal-Hydraulic Transients [2-element core]

Advanced Neutron Src Reactor Thermal-Hydraulic Transients [2-element core]

chen, wendel, yoder

کال:

1995

ژبه:

english

فایل:

PDF, 11.55 MB

0 / 0

english, 1995

21

Nuclear Hydrogen Production - Separating Reactor, Chemical Facils [pres. slides]

Nuclear Hydrogen Production - Separating Reactor, Chemical Facils [pres. slides]

کال:

2002

ژبه:

english

فایل:

PDF, 291 KB

0 / 0

english, 2002

22

Syetems Analysis of the CANDU-3 Reactor

Syetems Analysis of the CANDU-3 Reactor

J. R. Wolfgong, M. A. Linn, A. L. Wright, M. Olszewski, M. H. Fontana

کال:

1993

ژبه:

english

فایل:

PDF, 21.00 MB

0 / 0

english, 1993

23

Uranium Hexafluoride - Safe Handling, Processing, Storage

Uranium Hexafluoride - Safe Handling, Processing, Storage

کال:

1988

ژبه:

english

فایل:

PDF, 27.83 MB

0 / 0

english, 1988

24

TRISO-Coated Fuel Processing to Support High Temperature Gas-Cooled Reactors

TRISO-Coated Fuel Processing to Support High Temperature Gas-Cooled Reactors

Del Cul, G.D., Oak Ridge National Laboratory., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2002

ژبه:

english

فایل:

PDF, 3.66 MB

0 / 0

english, 2002

25

Neutronics Benchmarks for the Utilization of Mixed-Oxide Fuel : Joint U.S./Russian Progress Report for Fiscal Year 1997

Neutronics Benchmarks for the Utilization of Mixed-Oxide Fuel : Joint U.S./Russian Progress Report for Fiscal Year 1997

Akkurt, H, Oak Ridge National Laboratory., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1997

ژبه:

english

فایل:

PDF, 22.27 MB

0 / 0

english, 1997

26

Tritium Monitoring Techniques

Tritium Monitoring Techniques

کال:

1996

ژبه:

english

فایل:

PDF, 3.94 MB

0 / 0

english, 1996

27

Molten Salt Reactors [pres. slides]

Molten Salt Reactors [pres. slides]

کال:

2002

ژبه:

english

فایل:

PDF, 848 KB

0 / 0

english, 2002

28

Nuclear, Fundamental Physics Instrumentation for ANS Project

Nuclear, Fundamental Physics Instrumentation for ANS Project

کال:

1996

ژبه:

english

فایل:

PDF, 8.98 MB

0 / 0

english, 1996

29

Solid State Reactor Final Report

Solid State Reactor Final Report

G T Mays, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2003

ژبه:

english

فایل:

PDF, 8.74 MB

0 / 0

english, 2003

30

Molten Salt [reactor] Coolants [pres. slides]

Molten Salt [reactor] Coolants [pres. slides]

کال:

2003

ژبه:

english

فایل:

PDF, 793 KB

0 / 0

english, 2003

31

MSRE DESIGN AND OPERATIONS REPORT. PART I. DESCRIPTION OF REACTOR DESIGN

MSRE DESIGN AND OPERATIONS REPORT. PART I. DESCRIPTION OF REACTOR DESIGN

Robertson, R.C., Oak Ridge National Laboratory., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1965

ژبه:

english

فایل:

PDF, 38.76 MB

0 / 0

english, 1965

32

Advanced High-Temp Reactor for Hydrogen Production [pres. slides]

Advanced High-Temp Reactor for Hydrogen Production [pres. slides]

کال:

2002

ژبه:

english

فایل:

PDF, 586 KB

0 / 0

english, 2002

33

Reactor Design, Feasability - High Flux Research Reactor

Reactor Design, Feasability - High Flux Research Reactor

کال:

1956

ژبه:

english

فایل:

PDF, 7.35 MB

0 / 0

english, 1956

34

Plutonium process control using an advanced on-line gamma monitor for uranium, plutonium, and americium

Plutonium process control using an advanced on-line gamma monitor for uranium, plutonium, and americium

Miller, M.C., Marsh, S.F., Los Alamos National Laboratory., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2002

ژبه:

english

فایل:

PDF, 143 KB

0 / 0

english, 2002

35

Molten-Salt Reactor Experience Applicable to LS-VHTR Refueling [pres. slides]

Molten-Salt Reactor Experience Applicable to LS-VHTR Refueling [pres. slides]

کال:

2006

ژبه:

english

فایل:

PDF, 2.18 MB

0 / 0

english, 2006

36

Average Neutron Total Cross Sections in the Unresolved Energy Range From ORELA High Resolutio Transmission Measurements

Average Neutron Total Cross Sections in the Unresolved Energy Range From ORELA High Resolutio Transmission Measurements

H Derrien, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2004

ژبه:

english

فایل:

PDF, 625 KB

0 / 0

english, 2004

37

Development of Improved Burnable Poisons for Commercial Nuclear Power Reactors

Development of Improved Burnable Poisons for Commercial Nuclear Power Reactors

Renier, J.A., Oak Ridge National Laboratory., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2001

ژبه:

english

فایل:

PDF, 25.48 MB

0 / 0

english, 2001

38

Computation of Normal Conducting and Superconducting Linear Accelerator (LINAC) Availabilities

Computation of Normal Conducting and Superconducting Linear Accelerator (LINAC) Availabilities

Haire, M.J., Oak Ridge National Laboratory., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1999

ژبه:

english

فایل:

PDF, 88 KB

0 / 0

english, 1999

39

Estimating the Effect of Isotopic Uncertainties in Spent Nuclear Fuel

Estimating the Effect of Isotopic Uncertainties in Spent Nuclear Fuel

کال:

2001

ژبه:

english

فایل:

PDF, 105.02 MB

0 / 0

english, 2001

40

Molten-Salt Reactors - Minimizing Inventory of Weapons-Usable Mtls [pres. slides]

Molten-Salt Reactors - Minimizing Inventory of Weapons-Usable Mtls [pres. slides]

کال:

2000

ژبه:

english

فایل:

PDF, 4.21 MB

0 / 0

english, 2000

41

Fusion Energy Division annual progress report : period ending December 31, 1989

Fusion Energy Division annual progress report : period ending December 31, 1989

Oak Ridge National Laboratory. Fusion Energy Division

کال:

1991

ژبه:

english

فایل:

PDF, 21.96 MB

0 / 0

english, 1991

42

Criticality Safety Analysis of Nuclear-Cycle Facilities for Weapons-Grade Plutonium

Criticality Safety Analysis of Nuclear-Cycle Facilities for Weapons-Grade Plutonium

کال:

2001

ژبه:

english

فایل:

PDF, 737 KB

0 / 0

english, 2001

43

HFIR FUEL ELEMENT STEADY STATE HEAT TRANSFER ANALYSIS. REVISED VERSION

HFIR FUEL ELEMENT STEADY STATE HEAT TRANSFER ANALYSIS. REVISED VERSION

McLain, H.A., Oak Ridge National Laboratory., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1967

ژبه:

english

فایل:

PDF, 7.65 MB

0 / 0

english, 1967

44

Nuclear Criticality Safety of the DOT 9975 Container for237NpO2Storage, Handling, and Transport

Nuclear Criticality Safety of the DOT 9975 Container for237NpO2Storage, Handling, and Transport

D A Reed, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2003

ژبه:

english

فایل:

PDF, 759 KB

0 / 0

english, 2003

45

The KFM, A Homemade Yet Accurate and Dependable Fallout Meter

The KFM, A Homemade Yet Accurate and Dependable Fallout Meter

Kearny, C.H., Oak Ridge National Laboratory., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1978

ژبه:

english

فایل:

PDF, 3.03 MB

0 / 0

english, 1978

46

Molten-Salt and Moten-Salt-Cooled Reactors [pres. slides]

Molten-Salt and Moten-Salt-Cooled Reactors [pres. slides]

کال:

2001

ژبه:

english

فایل:

PDF, 84 KB

0 / 0

english, 2001

47

Multidimensional shielding analysis of the JASPER in-vessel fuel storage experiments

Multidimensional shielding analysis of the JASPER in-vessel fuel storage experiments

Bucholz, J.A., Oak Ridge National Laboratory., United States. Office of the Assistant Secretary for Nuclear Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1993

ژبه:

english

فایل:

PDF, 18.79 MB

0 / 0

english, 1993

48

Atomic Data for Fusion [light atoms] Vol 1 (data tables, charts)

Atomic Data for Fusion [light atoms] Vol 1 (data tables, charts)

کال:

1990

ژبه:

english

فایل:

PDF, 24.97 MB

0 / 0

english, 1990

49

Emerging Technologies in [nuclear] Instrumentation and Controls

Emerging Technologies in [nuclear] Instrumentation and Controls

کال:

2003

ژبه:

english

فایل:

PDF, 1.59 MB

0 / 0

english, 2003

50

Nuclear Reactor Power for Exploration of the Moon, Mars & Beyond [pres. slides]

Nuclear Reactor Power for Exploration of the Moon, Mars & Beyond [pres. slides]

کال:

2005

ژبه:

english

فایل:

PDF, 866 KB

0 / 0

english, 2005