Magnetic pressure drop and heat transfer of sodium-argon two-phase flow in annular channel under transverse magnetic fieldKUMAMARU, H.Journal of Nuclear Science and Technology. 1984, Vol 21, Num 6, pp 438-449, issn 0022-3131Article

FLEXIBLE AND ECONOMICAL ANALOG AND DIGITAL OPTICAL TRANSMISSION LINKSTAKIMOTO H; TSUJII K; KUMAMARU H et al.1979; FOC '79. INTERNATIONAL FIBER OPTICS AND COMMUNICATIONS EXPOSITION IN THE U.S. 2/1979/CHICAGO; USA; BROOKLINE MA: INFORMATION GATEKEEPERS; DA. 1979; PP. 53-58Conference Paper

PWR cold-leg small-break LOCA with total HPI failure : effect of break area on core dryout and international depressurization for prevention of excess core dryoutKUMAMARU, H; KUKITA, Y.Journal of Nuclear Science and Technology. 1992, Vol 29, Num 12, pp 1162-1172, issn 0022-3131Article

JELLY FILLED OPTICAL FIBER CABLESHORIMA H; TANAKA S; NAKAHARA T et al.sdOPTICAL COMMUNICATION CONFERENCE. EUROPEAN CONFERENCE ON OPTICAL COMMUNICATION. 5/1979/AMSTERDAM; NLD; DA. S.D.; PP. 7.2.1-7.2.4Conference Paper

Magnetohydrodynamic flow in rectangular channel : Effect of wall thickness and interaction of parallel channel flowsKUMAMARU, H; FUJIWARA, Y.Journal of Nuclear Science and Technology. 1999, Vol 36, Num 1, pp 110-113, issn 0022-3131Article

Pressure drop and heat transfer of magnetohydrodynamic annular two-phase flow in rectangular channelKUMAMARU, H; FUJIWARA, Y.Journal of fluids engineering. 1998, Vol 120, Num 1, pp 152-159, issn 0098-2202Article

LAMINAR MASS TRANSFER COEFFICIENTS IN A HYDROGEN WINDOW FOR A D-T FUSION REACTOR.MITSUISHI N; YAMANAKA A; KUMAMARU H et al.1978; J. CHEM. ENGNG JAP.; JPN; DA. 1978; VOL. 11; NO 1; PP. 75-77; BIBL. 11 REF.Article

JELLY-FILLED OPTICAL CABLEHORIMA H; YAMANISHI T; TANAKA S et al.1980; FIBER INTEGR. OPT.; ISSN 0146-8030; USA; DA. 1980; VOL. 3; NO 2-3; PP. 149-163; BIBL. 5 REF.Article

CHARACTERISTICS OF GRADED-INDEX FIBER BY VAD METHODSUZUKI S; KUWAHARA T; TANAKA G et al.sdOPTICAL COMMUNICATION CONFERENCE. EUROPEAN CONFERENCE ON OPTICAL COMMUNICATION. 5/1979/AMSTERDAM; NLD; DA. S.D.; PP. 12.6.1-12.6.4; BIBL. 4 REF.Conference Paper

Amlodipine is comparable to angiotensin-converting enzyme inhibitor for long-term renoprotection in hypertensive patients with Renal dysfunction : A one-year, prospective, randomized studyKUMAGAI, H; HAYASHI, K; KUMAMARU, H et al.American journal of hypertension. 2000, Vol 13, Num 9, pp 980-985, issn 0895-7061Article

Five percent break BWR LOCA/ECC test at ROSA-III without HPCS actuation two dimensional core thermal-hydraulic phenomenaKUMAMARU, H; KOIZUMI, Y; TASAKA, K et al.Nuclear engineering and design. 1985, Vol 86, Num 2, pp 219-239, issn 0029-5493Article

Void-fraction distribution under high-pressure boil-off conditions in rod bundle geometryKUMAMARU, H; KONDO, M; MURATA, H et al.Nuclear engineering and design. 1994, Vol 150, Num 1, pp 95-105, issn 0029-5493Article

Critical heat flux for annulus under high-pressure, low-flow and mixed inlet conditionsKUMAMARU, H; KOIZUMI, Y; TASAKA, K et al.Journal of Nuclear Science and Technology. 1990, Vol 27, Num 1, pp 68-80, issn 0022-3131Article

Investigation of pre- and post-dryout heat transfer in upward steam-water two-phase flow at low flow rate with improved surface temperature measurementKOIZUMI, Y; KUMAMARU, H; TASAKA, K et al.Journal of Nuclear Science and Technology. 1984, Vol 21, Num 12, pp 965-968, issn 0022-3131Article

RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following SBLOCAS with totally failed HPIKUMAMARU, H; KUKITA, Y; ASAKA, H et al.Nuclear technology. 1999, Vol 126, Num 3, pp 331-339, issn 0029-5450Article

High-pressure reflooding experiments of multi-rod bundle at ROSA-IV TPTFKOIZUMI, Y; ANODA, Y; KUMAMARU, H et al.Nuclear engineering and design. 1990, Vol 120, Num 2-3, pp 301-310, issn 0029-5493Article

Pool-boiling/bubbling void fraction in an annular fow channelKOIZUMA, Y; KUMAMARU, H; MIMURA, Y et al.Nuclear engineering and design. 1992, Vol 132, Num 3, pp 381-391, issn 0029-5493Article

Temporary core liquid level depression during a cold-leg small-break loss-of-coolant accident : the effect of break size and power levelKOIZUMI, Y; KUMAMARU, H; MIMURA, Y et al.Nuclear technology. 1991, Vol 96, Num 3, pp 290-301, issn 0029-5450Article

Slug to annular flow transition during Boiloff in a rod bundle under high-pressure conditionsOSAKABE, M; KOIZUMI, Y; YONOMOTO, T et al.Nuclear engineering and design. 1986, Vol 98, Num 1, pp 69-76, issn 0029-5493Article

Recirculation pump discharge line break tests at Rosa-III for a boiling water reactorSUZUKI, M; TASAKA, K; ANODA, Y et al.Nuclear technology. 1985, Vol 70, Num 2, pp 189-203, issn 0029-5450Article

Rosa-III double-ended break test series for a loss-of-coolant accident in a boiling water reactorTASAKA, K; SUZUKI, M; ANODA, Y et al.Nuclear technology. 1985, Vol 68, Num 1, pp 77-93, issn 0029-5450Article

ROSA/AP600 testing : Facility modifications and initial test resultsKUKITA, Y; YONOMOTO, T; ASAKA, H et al.Journal of Nuclear Science and Technology. 1996, Vol 33, Num 3, pp 259-265, issn 0022-3131Article