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Books & more: Hits 1 - 20 of 55

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Comparison of decay calculations of ORIGEN-Jül and ORIGEN 2.2 /

Pohl, Christoph
2010

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C++ coding standards : 101 rules, guidelines, and best practices /

Sutter, Herb
2005

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Properties of ATR-2E graphite and property changes due to fast neutron irradiation /

Haag, Gerd
2005

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Introducing Fortran 95 /

Chivers, Ian.
2000

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Refactoring : improving the design of existing code /

Fowler, Martin
1999

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Energiemodelle in der Bundesrepublik Deutschland : Stand der Entwicklung : IKARUS-Workshop am 24. und 25. Januar 1996, Haus der Wirtschaft, Stuttgart : eine Veranstaltung des Bunde...

Molt, Stephan
1997

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Study on temperature coefficients of actinide burning HTGRs /

Fujimoto, N.
1997

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Numerical simulation of severe water ingress accidents in a modular high temperature gas cooled reactor /

Zhang, Zuoyi
1996

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V. S. O. P. 1994: computer code system for reactor physics and fuel cycle simulation: input manual and comments /

Teuchert, Eberhard
1994

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Modelling of neutron absorbers in high temperature reactors by combined transport diffusion methods /

Fen, V.
1992

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Experimental investigation of corrosion of IG-110 graphite by steam /

Hinssen, Hans-Klemens
1990

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Cassell's German - English, English - German dictionary /

Betteridge, Harold T.
1987

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Comparison of high purity fine grain graphites from different suppliers with regard to physical, mechanical and thermal properties : Final report. Als ms. Gedr. /

Delle, Wolfgang W.
1987

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Materials investigations for the SNQ Target Station : progress report 1985 /

Lohmann, W.
1986

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The modified BLAST code for simulation of high temperature reactor steam generator dynamics /

Cleveland, J. C.
1983

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User's manual for ASTERIX-2 : a two-dimensional modular code system for the steady state and xenon transient analysis of a pebble bed high temperature reactor /

Lauer, Achim
1982

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Modelling of steam condensation in the primary flow channel of a gas heated steam generator /

Kawamura, H.
1982

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Graphitic matrix materials for spherical HTR fuel elements : results of material development and irradiation testing : catalogue of pictures and tables /

Schulze, R.-E.
1982

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Mechanisms of surface scale formation in HTR helium /

Lupton, D. F.
1980

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VSOP : computer code system for reactor physics and fuel cycle simulation /

Teuchert, Eberhard
1980

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Print Edition 55

Book 55

Report 27 Handbook, Textbook 4 Conference Publication 4 Theses 1

From:

To:

IEK-6-RSF ZB 12 IEK-4 3 IKP 2 IBN-1-2 1 IEK-3 1 more ... IEK-STE 1 INM-5 1 INM-8 1 JCNS-2 1 PTJ 1 see all ... less ...

Scherer, Winfried 4 Delle, Wolfgang W. 2 Haas, K. A. 2 Hansen, U. 2 Meister, G. 2 Rütten, Hans-Jochem 2 more ... Teuchert, Eberhard 2 Alexandrescu, Andrei 1 Allen, Deryck Norman de Garrs 1 Barnes, D. E. 1 Bergerfurth, Antonius 1 Bernard, Harold W. 1 Betteridge, Harold T. 1 Broadbent, T. A. A. 1 Brockmann, H. 1 Buckingham, R. A. 1 Chapman, Alan J. 1 Chase, Grafton. D. 1 Chivers, Ian. 1 Cleveland, J. C. 1 Cooper, B. E. 1 Cords, H. 1 Cowan, C. L. 1 Dean, A. V. 1 El-Wakil, M. M. 1 Etherington, Harold 1 Fahl, Ulrich 1 Fen, V. 1 Fowler, Martin 1 Fujimoto, N. 1 see all ... less ...

heat transfer 4 graphite 3 high temperature gas cooled reactors ( htgr type reactors ) 3 convection 2 nuclear engineering 2 reactor physics 2 more ... reactor technology 2 steam generator 2 Bessel function 1 C plus-plus (programming language) 1 Camac 1 FORTRAN (programming language) 1 absorption 1 boundary layer 1 carbon 1 corrosion 1 cross section 1 diffusion 1 energy economy 1 energy model 1 energy policy 1 fluid flow 1 fuel cycle 1 germanium 1 heat conduction 1 heat flux 1 helium embrittlement 1 laminar fluid flow 1 mathematical physics 1 neutron absorption analysis 1 see all ... less ...

TND - Gas cooled reactor types 9 TNI - Reactor physics 5 FNX - Carbon, carbon materials 3 THM - Heat transfer, mass transfer - technical aspects 3 TNJB - Nuclear reactor materials 3 ACE - Germanic languages, Indo-Germanic languages 2 more ... FDFC - Radiation effects in metals, nuclear radiation effects 2 MNA - Numerical mathematics - general 2 TNA - Nuclear engineering - general 2 TNDF - Gas cooled reactor fuel elements 2 TNE - Water cooled reactors 2 TNL - Nuclear fuel, nuclear fuel elements - general 2 TNS - Hot cells, irradiation facilities 2 011 - Simulation Science (advanced reading) 1 CR - Nuclear chemistry, radiation chemistry 1 DMAF - Object oriented programming 1 DMF - Software engineering 1 DOFC - Programming language - C plus-plus 1 DOI - Programming language - FORTRAN 1 EVP - Energy models, energy system analysis 1 FJKB - Elemental semiconductors 1 FMEB - Metallurgical analysis 1 FMX - Metal gas systems 1 HCN - Nuclear medicine 1 MAF - Mathematics - general series 1 MRB - Special functions, special polynomials 1 MSD - Mathematical methods in physics 1 PKS - Spallation neutron source, spallation reactions, ESS 1 TCH - Data transmission 1 TGN - Control engineering 1 see all ... less ...

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