Thermal-hydraulic characteristics inside in-core structure test section (T $_{2}$ ) of helium engineering demonstration loop (HENDEL) under loss of forced circulation condition

Takada, Shoji; Inagaki, Yoshiyuki; Ioka, Ikuo ; Sudo, Yukio

no abstracts in English

Language	:	English
Journal	:	The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2
Volume	:	0
Number	:
Pages	:	p.1087 - 1092
Publication Year/Month	:	1995/00
Meeting title	:	3rd Int. Conf. on Nuclear Engineering; ICONE-3
Held date	:	1995/04
Location (city)	:	京都
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DOI for research data	:
Keywords	:	MHTRG; HTGR; HENDEL; T $_{2}$ ; パッシブセーフティ; パッシブクーリング; 炉床部; LOCA; 数値解析; 漏れ流れ
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Registration No. : B19941618
JAEA Abstracts No. : 230467
Paper Submission No. : 13084

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Thermal-hydraulic characteristics inside in-core structure test section (T) of helium engineering demonstration loop (HENDEL) under loss of forced circulation condition

Thermal-hydraulic characteristics inside in-core structure test section (T $_{2}$ ) of helium engineering demonstration loop (HENDEL) under loss of forced circulation condition