Nuclear Reactor Kinetics and Plant Control

क्यूआर कोड

Nuclear Reactor Kinetics and Plant Control

में बचाया:

ग्रंथसूची विवरण
मुख्य लेखक:	Oka, Yoshiaki
स्वरूप:	पुस्तक
भाषा:	English
प्रकाशित:	Springer 2016
विषय:	Nuclear Reactor Kinetics
ऑनलाइन पहुंच:	https://scholar.dlu.edu.vn/thuvienso/handle/DLU123456789/60660
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समान संसाधन

Reaction kinetics and reactor design
द्वारा: Butt, John B
प्रकाशित: (2014)

Nuclear Reactor Theory
द्वारा: Sekimoto, Hiroshi
प्रकाशित: (2012)

Introduction to nuclear reactor theory
द्वारा: Lamarsh, John R
प्रकाशित: (2013)

Introduction to nuclear reactor theory
द्वारा: Lamarsh, John R.
प्रकाशित: (1966)

Nuclear reactor physics
द्वारा: Stacey, Weston M
प्रकाशित: (2014)

Nuclear Reactor Engineering: Reactor Systems Engineering
द्वारा: Glasstone, Samuel, और अन्य
प्रकाशित: (2014)

Dynamics of nuclear reactors
द्वारा: Hetrick, David L
प्रकाशित: (2013)

Nuclear Reactor Hazards Ongoing Dangers of Operating Nuclear Technology in the 21st Century
द्वारा: Hirsch, Helmut, और अन्य
प्रकाशित: (2014)

Nuclear reactor analysis
द्वारा: Duderstadt, James J, और अन्य
प्रकाशित: (2014)

Nuclear reactor theory
द्वारा: Bell, George I, और अन्य
प्रकाशित: (2013)

Nuclear-reactor analysis
द्वारा: Henry, Allan F
प्रकाशित: (2014)

Elementary introduction to nuclear reactor physics
द्वारा: Liverhant, S E
प्रकाशित: (2014)

Super light water reactors and super fast reactors : supercritical-pressure light water cooled reactor
द्वारा: Yoshiaki Oka
प्रकाशित: (2015)

Supercritical-pressure light water cooled reactors
द्वारा: Yoshiaki Oka, और अन्य
प्रकाशित: (2015)

Development and diffusion of the nuclear power reactor :
द्वारा: Deleon, Peter
प्रकाशित: (1979)

Design of delay-tolerant controller for remote control of nuclear reactor power /
द्वारा: Lee, Yoon-Joon.

DOE fundamentals handbook: Nuclear physics and reactor theory. Volume 2
द्वारा: Washington DC USDOE
प्रकाशित: (2013)

Characterization and testing of materials for nuclear reactors: Proceedings of a technical meeting held in Vienna, May 29--June 2, 2006
द्वारा: Paranjpe, Shriniwas K
प्रकाशित: (2013)

Fundamentals and recent developments of reactor physics methods /
द्वारा: Cho, Nam Zin.

Reactor core fuel management
द्वारा: Silvennoinen, P
प्रकाशित: (2014)

Development of best practice guidelines for CFD in nuclear reactor safety /
द्वारा: Mahaffy, J.

Nuclear power systems, an introductory text
द्वारा: King, Cecil Dudley Gregg
प्रकाशित: (2014)

Design and validation of robust and autonomous control for nuclear reactors /
द्वारा: Shaffer, Roman A.

Assessment of CFD codes used in nuclear reactor safety simulations /
द्वारा: Smith, B.L..

Reactor physics
द्वारा: Zweifel, P F
प्रकाशित: (2014)

Thermophysical properties of materials for nuclear engineering: A tutorial and collection of data.
द्वारा: International Atomic Energy Agency
प्रकाशित: (2013)

Nuclear heat transport
द्वारा: Wakil, M M El
प्रकाशित: (2014)

Evolution of nuclear fuel management and reactor operational aid tools /
द्वारा: Turinsky, Paul J.

Status and perspective of nuclear data production, evaluation and validation /
द्वारा: Trkov, A.

Nuclear Reactor Physics
द्वारा: Dam, H. van, और अन्य
प्रकाशित: (2014)

Reactor physics challenges in gen-iv reactor design /
द्वारा: Driscoll, Michael J.

Tokamak reactor system analysis code for the conceptual development of demo reactor /
द्वारा: Hong, Bong-Guen.

Multiphase Flow Dynamics 5: Nuclear Thermal Hydraulics
द्वारा: Kolev, Nikolay Ivanov
प्रकाशित: (2016)

The assessment of safety systems in Wwer-1000 nuclear reactor using IAEA simulator = Đánh giá hệ thống an toàn trong lò phản ứng Wwer-1000 bằng phần mềm mô phỏng IAEA /
द्वारा: Tran Dang Khoa.

Reactor dosimetry in the 21st century : proceedings of the 11th International Symposium on Reactor Dosimetry : Brussels, Belgium, 18-23 August 2002 /
प्रकाशित: (2003)

Fundamentals of nuclear reactor physics
द्वारा: Lewis, Elmer E
प्रकाशित: (2013)

Chemical reactor design, optimization, and scaleup
द्वारा: Nauman, E. Bruce
प्रकाशित: (2001)

Pile neutron research.
द्वारा: Hughes, Donald James, 1915-
प्रकाशित: (1953)

Statistical modelling of graphite brick cracking in advanced gas-cooled reactors /
द्वारा: Maul, Philip R.

Development and validation of coupled dynamics code 'trikin' for VVER reactors /