Experimental study on thermal-hydraulics and neutronics coupling effect on flow instability in a heated channel with THYNC facility

Iguchi, Tadashi; Shibamoto, Yasuteru; Asaka, Hideaki; Nakamura, Hideo

Proceedings of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), 16 Pages, 2003/10

Thermal-hydraulic and neutronic dynamics are always interrelated in BWR core. This is called thermal-hydraulic and neutronic (T/N) coupling. Channel stability experiments with T/N coupling under non-nuclear condition are very limited. This is mainly due to the difficulties in the real-time simulation of neutron dynamics and in the fast-response void fraction measurement under high-pressure and temperature conditions. Authors have developed techniques to solve the above difficulties, and have succeeded in experimentally simulating T/N coupling under non-nuclear conditions with the THYNC facility. Using THYNC facility, T/N coupling effect on channel stability was investigated. Experiments were performed under Pressure=2-7MPa, Subcooling=10-40K, and Mass flux=270-660kg/ms. THYNC results indicated T/N coupling lowered the channel stability threshold. The reduction of channel stability threshold due to T/N coupling was small within 10% at 7MPa in the present THYNC experiment, although the experimental condition was set to be more severe than that supposed in a reactor.

Study on reactivity feedback effects in the TRACY transient experiments

Nakajima, Ken; ;

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 3, p.1286 - 1292, 1999/00

no abstracts in English

Benchmark problems on transmutation calculation by the OECD/NEA task force on physics aspects of different transmutation concepts

R.P.Rulko*; Takano, Hideki; C.Broeders*; Wakabayashi, Toshio*; Sasa, Toshinobu; *; D.Lutz*; Mukaiyama, Takehiko; C.Nordborg*

Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 2, p.1462 - 1469, 1998/00

no abstracts in English

Double heterogeneity effect of fuel pin and subassembly in a fast power reactor

Nakagawa, Masayuki; *

Nuclear Science and Engineering, 53(2), p.214 - 228, 1983/00

no abstracts in English

Study of Analytical Method for Sodium Void Reactivity in Fast Critical Assemblies

Nakagawa, Masayuki

JAERI-M 8138, 197 Pages, 1979/01

JAERI-M-8138.pdf:4.5MB

no abstracts in English

Analysis of Heterogeneity Effect of Gas Cooled Fast Reactor

; ; *

JAERI-M 7608, 110 Pages, 1978/03

JAERI-M-7608.pdf:2.59MB

no abstracts in English

Analysis of sodium void reactivity measured in FCA V-1 assembly

Nakagawa, Masayuki; ; Katsuragi, Satoru

Journal of Nuclear Science and Technology, 10(7), p.419 - 427, 1973/07

https://doi.org/10.3327/jnst.10.419

no abstracts in English