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کتابونه (53)
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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

Primary system fission product release and transport : a state-of-the-art report to the Committee on the Safety of Nuclear Installations

Primary system fission product release and transport : a state-of-the-art report to the Committee on the Safety of Nuclear Installations

U.S. Nuclear Regulatory Commission

A L Wright, Oak Ridge National Laboratory., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., et al

کال:

1994

ژبه:

english

فایل:

PDF, 14.45 MB

0 / 0

english, 1994

3

Parametric study of the effect of burnable poison rods for PWR burnup credit

Parametric study of the effect of burnable poison rods for PWR burnup credit

Division of Systems Analysis and Regulatory Effectiveness Office of Nuclear Regulatory Research

J C Wagner, C V Parks, Oak Ridge National Laboratory., U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness

کال:

2002

ژبه:

english

فایل:

PDF, 1.05 MB

0 / 0

english, 2002

4

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

5

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

6

Detection of pump degradation

Detection of pump degradation

U.S. Nuclear Regulatory Commission

R H Greene, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Oak Ridge National Laboratory., et al

کال:

1995

ژبه:

english

فایل:

PDF, 8.68 MB

0 / 0

english, 1995

7

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

8

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

9

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

10

Primary system fission product release and transport: A state-of-the-art report to the committee on the safety of nuclear installations

Primary system fission product release and transport: A state-of-the-art report to the committee on the safety of nuclear installations

U.S. Nuclear Regulatory Commission

A. L. Wright, Oak Ridge National Laboratory

کال:

1994

ژبه:

english

فایل:

PDF, 22.44 MB

0 / 0

english, 1994

11

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

12

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

13

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

14

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

15

High temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research quarterly progress report, April 1-June 30, 1979

High temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research quarterly progress report, April 1-June 30, 1979

J C Cleveland, J C Conklin, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Oak Ridge National Laboratory

کال:

1975

ژبه:

english

فایل:

PDF, 2.57 MB

0 / 0

english, 1975

16

Designing Equipment for Use in Gamma Radiation Environments

Designing Equipment for Use in Gamma Radiation Environments

Vandergriff, K.U., (US), Oak Ridge National Laboratory., United States. Dept. of Energy. Office of Scientific and Technical Information

ژبه:

english

فایل:

PDF, 4.26 MB

0 / 0

english

17

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

18

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

19

Limiting values of radionuclide intake and air concentration and dose conversion factors for for inhalation, submersion, and ingestion : derived guides for control of occupational exposure and exposure-to-dose conversion factors for general application, b

Limiting values of radionuclide intake and air concentration and dose conversion factors for for inhalation, submersion, and ingestion : derived guides for control of occupational exposure and exposure-to-dose conversion factors for general application, b

Oak Ridge National Laboratory

Keith F Eckerman, Allan C B Richardson, Anthony B Wolbarst, United States. Environmental Protection Agency. Office of Radiation Programs., Oak Ridge National Laboratory

کال:

1988

ژبه:

english

فایل:

PDF, 15.20 MB

0 / 0

english, 1988

20

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

21

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

22

Low-order dynamic modeling of the experimental breeder reactor II

Low-order dynamic modeling of the experimental breeder reactor II

R C Berkan, B R Upadhyaya, R A Kisner, United States. Office of Technology Support Programs., Oak Ridge National Laboratory. Instrumentation and Controls Division., All authors

کال:

1990

ژبه:

english

فایل:

PDF, 6.11 MB

0 / 0

english, 1990

23

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

24

Materials testing reactor project handbook

Materials testing reactor project handbook

Oak Ridge, Tenn., United States Atomic Energy Commission, Technical Information Service, [1955?]

John Henry Buck, Carl F Leyse, Argonne National Laboratory., Oak Ridge National Laboratory

کال:

1951

ژبه:

english

فایل:

PDF, 38.88 MB

0 / 0

english, 1951

25

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

26

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

27

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

28

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

29

ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and VVER Reactor Designs

ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and VVER Reactor Designs

BD Murphy, 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, 1.05 MB

0 / 0

english, 2004

30

Transport of Radioactive Material by Alpha Recoil

Transport of Radioactive Material by Alpha Recoil

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

کال:

2005

ژبه:

english

فایل:

PDF, 308 KB

0 / 0

english, 2005

31

5th FORUM ON NEW MATERIALS PART B Proceedings of the 5th Forum on New Materials, part of CIMTEC 2010-12 th International Ceramics Congress and 5th Forum on New Materials Montecatini Terme, Italy, June 13-18, 2010

5th FORUM ON NEW MATERIALS PART B Proceedings of the 5th Forum on New Materials, part of CIMTEC 2010-12 th International Ceramics Congress and 5th Forum on New Materials Montecatini Terme, Italy, June 13-18, 2010

Edited by Pietro VINCENZINI World Academy of Ceramics and National Research Council, Italy Co-edited by Hua-Tay LIN, Oak Ridge National Laboratory, USA Kevin FOX, Savannah River National Laboratory, USA

کال:

2010

ژبه:

english

فایل:

PDF, 39.26 MB

0 / 0

english, 2010

32

Experience with the SCALE criticality safety cross-section libraries

Experience with the SCALE criticality safety cross-section libraries

S M Bowman, U.S. Nuclear Regulatory Commission. Spent Fuel Project Office., Oak Ridge National Laboratory., et al

کال:

2000

ژبه:

english

فایل:

PDF, 1.92 MB

0 / 0

english, 2000

33

K-infinite trends with burnup, enrichment, and cooling time for BWR fuel assemblies

K-infinite trends with burnup, enrichment, and cooling time for BWR fuel assemblies

Broadhead, B.L., Oak Ridge National Laboratory., United States. Dept. of Energy. Assistant Secretary for Human Resources and Administration., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1998

ژبه:

english

فایل:

PDF, 287 KB

0 / 0

english, 1998

34

Radiation Detection from Fission

Radiation Detection from Fission

J Mihalczo, 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, 656 KB

0 / 0

english, 2004

35

Fusion Energy Division annual progress report

Fusion Energy Division annual progress report

Oak Ridge National Laboratory

Oak Ridge National Laboratory. Fusion Energy Division

کال:

1992

ژبه:

english

فایل:

PDF, 27.11 MB

0 / 0

english, 1992

36

Fusion Energy Division annual progress report

Fusion Energy Division annual progress report

Oak Ridge National Laboratory

Oak Ridge National Laboratory. Fusion Energy Division

کال:

1995

ژبه:

english

فایل:

PDF, 27.38 MB

0 / 0

english, 1995

37

Termination of light-water reactor core-melt accidents with a chemical core catcher : the core-melt source reduction system (COMSORS)

Termination of light-water reactor core-melt accidents with a chemical core catcher : the core-melt source reduction system (COMSORS)

Rudolph, J.C., Parker, G.W., Forsberg, C.W., Osborne-Lee, I.W., Kenton, M.A., Oak Ridge National Laboratory., United States. Dept. of Energy. Office of Energy Research., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

1996

ژبه:

english

فایل:

PDF, 9.10 MB

0 / 0

english, 1996

38

Advanced Reactor Licensing : Experience with Digital I&C Technology in Evolutionary Plants

Advanced Reactor Licensing : Experience with Digital I&C Technology in Evolutionary Plants

RT Wood, 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, 5.45 MB

0 / 0

english, 2004

39

Analysis of Rod Removal Transient Experiments in VVER Reactors at Zero Power

Analysis of Rod Removal Transient Experiments in VVER Reactors at Zero Power

Difillippo, F.C., USDOE Office of Fissile Materials Disposition (MD) (US), Oak Ridge National Laboratory., United States. Dept. of Energy. Office of Scientific and Technical Information

ژبه:

english

فایل:

PDF, 639 KB

0 / 0

english

40

Metallurgy Division annual progress report for period ending

Metallurgy Division annual progress report for period ending

Oak Ridge National Laboratory

Oak Ridge National Laboratory. Metallurgy Division., Union Carbide Corporation

ژبه:

english

فایل:

PDF, 56.45 MB

0 / 0

english

41

Proceedings

Proceedings

[Washington, U.S. Atomic Energy Commission, Technical Information Center; available from the Nationa

W L Greenstreet, G C Battle, AEC Graphite Coordination Working Group., Oak Ridge National Laboratory

کال:

1972

ژبه:

english

فایل:

PDF, 46.34 MB

0 / 0

english, 1972

42

Minimum Critical Values Study

Minimum Critical Values Study

P B Fox, Oak Ridge National Laboratory. ., United States. Dept. of Energy., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2005

ژبه:

english

فایل:

PDF, 1.43 MB

0 / 0

english, 2005

43

Precursors to potential severe core damage accidents : a status report

Precursors to potential severe core damage accidents : a status report

Oak Ridge National Laboratory., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs

کال:

1999

ژبه:

english

فایل:

PDF, 10.92 MB

0 / 0

english, 1999

44

Precursors to potential severe core damage accidents : a status report

Precursors to potential severe core damage accidents : a status report

Oak Ridge National Laboratory., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs

کال:

1993

ژبه:

english

فایل:

PDF, 49.67 MB

0 / 0

english, 1993

45

San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses

San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses

Hermann, O.W., USDOE Office of Fissile Materials Disposition (MD) (US), Oak Ridge National Laboratory., United States. Dept. of Energy. Office of Scientific and Technical Information

کال:

2000

ژبه:

english

فایل:

PDF, 432 KB

0 / 0

english, 2000

46

Homogeneous reactor project quarterly progress report for the period ending

Homogeneous reactor project quarterly progress report for the period ending

Oak Ridge National Laboratory

Oak Ridge National Laboratory., Union Carbide Corporation., U.S. Atomic Energy Commission

ژبه:

english

فایل:

PDF, 33.99 MB

0 / 0

english

47

Homogeneous reactor project quarterly progress report for the period ending

Homogeneous reactor project quarterly progress report for the period ending

Oak Ridge National Laboratory

Oak Ridge National Laboratory., Union Carbide Corporation., U.S. Atomic Energy Commission

کال:

1956

ژبه:

english

فایل:

PDF, 20.51 MB

0 / 0

english, 1956

48

The Tower Shielding Facility : Its glorious past

The Tower Shielding Facility : Its glorious past

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

کال:

1997

ژبه:

english

فایل:

PDF, 46.05 MB

0 / 0

english, 1997

49

Precursors to potential severe core damage accidents : a status report

Precursors to potential severe core damage accidents : a status report

Oak Ridge National Laboratory., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs

کال:

1995

ژبه:

english

فایل:

PDF, 16.37 MB

0 / 0

english, 1995

50

Precursors to potential severe core damage accidents : a status report

Precursors to potential severe core damage accidents : a status report

Oak Ridge National Laboratory., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data., U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs

کال:

1997

ژبه:

english

فایل:

PDF, 17.74 MB

0 / 0

english, 1997