Statistical modelling of graphite brick cracking in advanced gas-cooled reactors /

क्यूआर कोड

Statistical modelling of graphite brick cracking in advanced gas-cooled reactors /

में बचाया:

ग्रंथसूची विवरण
मुख्य लेखक:	Maul, Philip R.
अन्य लेखक:	Northrop, Paul J., Robinson, Peter C.
स्वरूप:	लेख
भाषा:	English
विषय:	Blind predictions Graphite Model performance Nuclear reactors System variability
टैग :	टैग जोड़ें कोई टैग नहीं, इस रिकॉर्ड को टैग करने वाले पहले व्यक्ति बनें!

Thư viện lưu trữ:	Thư viện Trường Đại học Đà Lạt

समान संसाधन

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

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

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

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

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

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

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

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

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

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

Nuclear Reactor Kinetics and Plant Control
द्वारा: Oka, Yoshiaki
प्रकाशित: (2016)

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)

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

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)

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

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

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

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

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

Graphite intercalation compounds and applications
द्वारा: Enoki, Toshiaki
प्रकाशित: (2003)

Development of MARS-GCR/V1 for thermal-hydraulic safety analysis of gas-cooled reactor systems /

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

Safety studies on hydrogen production system with a high temperature gas-cooled reactor /
द्वारा: Takeda, Tetsuaki.

Communication development in congenitally blind and severely vision impaired children : Principles and strategies /
द्वारा: Blackall, Loretta.
प्रकाशित: (1990)

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

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

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

A blind child in my Classroom : A handbook for primary teachers /
द्वारा: Cronin, Peter.
प्रकाशित: (1990)

A blind student in the regular primary classroom methods of teaching /
द्वारा: Cronin, Peter.
प्रकाशित: (1992)

High-performance supercapacitors based on hierarchically porous graphite particles /

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

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

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

Status and perspective of two-phase flow modelling in the neptune multiscale thermal-hydraulic platform for nuclear reactor simulation /
द्वारा: Bestion, Dominique.

Hydrodynamic characteristics and gas-liquid mass transfer in a biofilm airlift suspension reactor /

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

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

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

MSET performance optimization through regularization /
द्वारा: Hines, J. Wesley.