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Results 1 to 25 of 96599

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Stress state dependence of in-reactor creep and swelling Part I: Continuum plasticity modelHALL, M. M.Journal of nuclear materials. 2010, Vol 396, Num 1, pp 112-118, issn 0022-3115, 7 p.Article

SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTSANGHAIE, Samim.Nuclear technology. 2010, Vol 170, Num 1, issn 0029-5450, 281 p.Serial Issue

Pin power factor decrease and fuel economy during LEU refueling of 14 MW triga coreIORGULIS, C; PREDA, M; CIOCANESCU, M et al.International symposium on nuclear energy. 1999, pp 385-389, 2VolConference Paper

Safety analysis of abnormal reactivity events in HTTRNAKAGAWA, S; SAWA, K; OHASHI, K et al.Journal of Nuclear Science and Technology. 1993, Vol 30, Num 6, pp 579-588, issn 0022-3131Article

The design of the prestressed concrete reactor vessel for gas-cooled heating reactorsBECKER, G; STEFFEN, G; NOTHEISEN, C et al.Nuclear engineering and design. 1989, Vol 117, Num 3, pp 333-340, issn 0029-5493Article

Burning of reactor grade plutonium mixed with thorium in a hybrid reactorACTR, Adem; UBEYLI, Mustafa.Journal of fusion energy. 2007, Vol 26, Num 3, pp 293-298, issn 0164-0313, 6 p.Article

Flow blockage analysis of a channel in a typical material test reactor coreQING LU; SUIZHENG QIU; SU, G. H et al.Nuclear engineering and design. 2009, Vol 239, Num 1, pp 45-50, issn 0029-5493, 6 p.Article

A subcritical, gas-cooled fast transmutation reactor with a fusion neutron sourceSTACEY, W. M; BEAVERS, V. L; LORIO, R. A et al.Nuclear technology. 2005, Vol 150, Num 2, pp 162-188, issn 0029-5450, 27 p.Article

A revised description of graphite irradiation induced creepDAVIES, Mark A; BRADFORD, Mark.Journal of nuclear materials. 2008, Vol 381, Num 1-2, pp 39-45, issn 0022-3115, 7 p.Article

A nuclear reactor core as a thermodynamic systemORLOV, V. N; DOLGOV, Yu. A.Atomic energy (New York, N.Y.). 2001, Vol 91, Num 4, pp 862-865, issn 1063-4258Article

Application of MCP4B for criticality analysis of FRJ-2NABBI, R; WOLTERS, J.International topical meeting on research reactor fuel management. 2000, pp 37-41Conference Paper

Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM projectZUOYI ZHANG; YULIANG SUN.Nuclear engineering and design. 2007, Vol 237, Num 23, pp 2265-2274, issn 0029-5493, 10 p.Article

Development of advanced core noise monitoring system for BWRsMORI, Michitsugu; KAINO, Masaru; KANEMOTO, Shigeru et al.Progress in nuclear energy (New series). 2003, Vol 43, Num 1-4, pp 43-49, issn 0149-1970, 7 p.Conference Paper

Evaluation of local power distribution with fine-mesh core model for high temperature engineering test reactor (HTTR)MURATA, I; YAMASHITA, K; MARUYAMA, S et al.Journal of Nuclear Science and Technology. 1994, Vol 31, Num 1, pp 62-72, issn 0022-3131Article

RAPID operator-free fast reactor concept without any control rods reactor concept and plant dynamics analysesKAMBE, Mitsuru.Journal of Nuclear Science and Technology. 2005, Vol 42, Num 6, pp 525-536, issn 0022-3131, 12 p.Article

Neutronic simulation of a pebble bed reactor considering its double heterogeneous natureABEDI, Amin; VOSOUGHI, Naser.Nuclear engineering and design. 2012, Vol 253, pp 277-284, issn 0029-5493, 8 p.Article

Compatibility of structural materials with sodium according to data from the experience gained in 40 years of operation of the BR-5/BR-10 reactorKARPOV, A. V; KONONYUK, M. Kh; MAMAEV, L. I et al.Atomic energy (New York, N.Y.). 2002, Vol 91, Num 5, pp 951-955, issn 1063-4258Conference Paper

Calculation of the Dancoff factor for pebble bed reactorsVALKO, J; TSVETKOV, P. V; HOOGENBOOM, J. E et al.Nuclear science and engineering. 2000, Vol 135, Num 3, pp 304-307, issn 0029-5639Article

Grossexperimente mit repräsentativer Kernschmelze im Hinblick auf die Beherrschung eines Kernschmelzunfalls : Massnahmen zur Beherrschung von Kernschmelze im Sicherheitsbehälter = Representative experiments on nuclears meltdownsSTEINWARZ, W; HÄFNER, W; ALKAN, Z et al.Atw. Internationale Zeitschrift für Kernenergie. 1999, Vol 44, Num 7, issn 1431-5254, 414, 436-441 [6 p.]Conference Paper

Metallic core internals of the modular HTRROTHFUSS, H; STAUSEBACH, D; ULLRICH, M et al.Nuclear engineering and design. 1993, Vol 147, Num 1, pp 93-100, issn 0029-5493Article

The analytic nodal method in cylindrical geometryPRINSLOO, Rian H; TOMASEVIC, Djordje I.Nuclear engineering and design. 2008, Vol 238, Num 11, pp 2898-2907, issn 0029-5493, 10 p.Conference Paper

Fluiddynamik von Differential-Kreislauf-Reaktoren unterschiedlicher Durchmischung und Konstruktion = Fluid dynamics of differential loop reactors with various degrees of mixing and of various designsREISENER, G; SCHREIER, M; HESSELBARTH, B et al.Chemieingenieurtechnik. 2000, Vol 72, Num 6, pp 584-589, issn 0009-286XConference Paper

Evaluation of the reactivity expansion defect for small solid-core reactors and componentsJAHSHAN, S; ANGHAIE, S.Nuclear technology. 1994, Vol 105, Num 2, pp 291-292, issn 0029-5450Article

Anwendung von Künstlichen Neuronalen Netzen (Multilayer Perzeptron) in der Reaktorsicherheitsforschung = Application of artificial neural networks (Multilayer Perceptron) in reactor safety researchKRATZSCH, A; KÄSTNER, W; HAMPEL, R et al.Atw. Internationale Zeitschrift für Kernenergie. 2007, Vol 52, Num 10, issn 1431-5254, 619, 646-647 [3 p.]Article

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