JOPSS - Search Results

Journal Articles

New estimation method for void reactivity coefficient using the TRACY transient data

Ogawa, Kazuhiko; Kaminaga, Fumito*

Journal of Nuclear Science and Technology, 46(1), p.1 - 5, 2009/01

https://doi.org/10.3327/jnst.46.1

Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

In the safety research regarding a criticality accident in nuclear reprocessing plants, prediction of nuclear fission yields is essential to evaluate its influence on a radiation of neutrons/-rays to the public. For numerical calculations of the number of fissions in a criticality accident, a void reactivity coefficient due to the formation of radiolytic gas voids in the solution is required to evaluate the negative feedback reactivity. Small oscillations of both the power and the core pressure are measured after the first power pulse in a slow transient operation in TRACY. The small power oscillations are due to the reactivity feedback effect of the change of the volume of gas voids. In this paper, we propose a new estimation method of the void reactivity coefficient and estimate the coefficient using the TRACY transient data. The present estimated void reactivity coefficient is less than the calculated values in the uniform distribution of gas voids.

Journal Articles

Estimation of generated volume of radiolytic gas voids during prompt criticality with 10% enriched uranium nitrate solution in TRACY

Ogawa, Kazuhiko; Kaminaga, Fumito*

Journal of Nuclear Science and Technology, 45(10), p.1028 - 1035, 2008/10

https://doi.org/10.3327/jnst.45.1028

Times Cited Count：3 Percentile：23.55(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Research on the fundamental process of thermal-hydraulic behaviors in severe accident; Boiling heat transfer in a narrow channel, JAERI's nuclear research promotion program, H10-027-4 (Contract research)

Kaminaga, Fumito*

JAERI-Tech 2002-012, 68 Pages, 2002/03

JAERI-Tech-2002-012.pdf:2.45MB

no abstracts in English

JAEA Reports

Mercury flow tests, 2; Characteristic of gear pump for mercury circulation

Kaminaga, Masanori; Kinoshita, Hidetaka; Haga, Katsuhiro; Hino, Ryutaro; Nakamura, Fumihito*; Ohashi, Masahisa*

JAERI-Tech 2000-044, 25 Pages, 2000/06

JAERI-Tech-2000-044.pdf:4.64MB

no abstracts in English

Journal Articles

Evaluation method of performance of siphon break value as core covering system for water-cooled test and research reactors

; Kumada, Hiroaki; Kaminaga, Fumito*

Nihon Genshiryoku Gakkai-Shi, 42(4), p.325 - 333, 2000/04

https://doi.org/10.3327/jaesj.42.325

Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Basic study for nonlinear instable phenomena of free surface -Response of free surface to down flow- (Report of collaboration study)

*; *; *

JNC TY9400 2000-003, 99 Pages, 1999/08

JNC-TY9400-2000-003.pdf:6.48MB

no abstracts in English

Journal Articles

Design of JMTR high-performance fuel element

; Shimakawa, Satoshi; ; ; Kaminaga, Fumito*

Nihon Genshiryoku Gakkai-Shi, 41(1), p.57 - 65, 1999/00

https://doi.org/10.3327/jaesj.41.57

Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal and hydraulic design of mercury target; Cross flow type

Kaminaga, Masanori; Hino, Ryutaro; *; *; Nakamura, Fumihito*; *

Proc. of 14th Meeting of the Int. Collaboration on Advanced Neutron Sources (ICANS-14), 1, p.269 - 277, 1998/00

no abstracts in English

JAEA Reports

Preliminary conceptual design of target system, 1; System configuration

Hino, Ryutaro; Haga, Katsuhiro; Kaminaga, Masanori; Aso, Tomokazu; Kogawa, Hiroyuki; Ishikura, Shuichi*; *; Nakamura, Fumihito*; *; *

JAERI-Tech 97-035, 194 Pages, 1997/07

JAERI-Tech-97-035.pdf:6.83MB

no abstracts in English

JAEA Reports

A Study on gap heat transfer between boron carbide pellet and cladding (IV)

*; *

PNC TJ9613 89-001, 75 Pages, 1989/06

PNC-TJ9613-89-001.pdf:2.35MB

The purpose of this study is to investigate gap heat transfer between a boron carbide pellet (B $_{4}$ C) and a cladding in a control rod of the Fast Breeder Reactor. The present report describes discussions of the experimental data obtained previously and results of the following two experiments and one analytical calculation. The first experiment was performed to measure conductances of an annular gap between the B $_{4}$ C pellet and the cladding. The test piece used a sheath heater to obtain an accurate heat transfer rate and ceramic spacers to minimize an axial heat dissipation and an eccentric effect. The gap width was 0.5 mm and the test range was up to 600 $^{circ}$ C on a surface temperature of the B $_{4}$ C pellet. The second experiment was to measure an emissivity of radiative heat of the B $_{4}$ C and the stainless steel materials. The analytical calculation was made by the finite element method to evaluate an eccentric effect on a circumferential profile of the heat transfer rate. The results were summarized as follows. The emissivities of the B $_{4}$ C and the stainless were 0.85 and 0.25, respectively. When the minimum gap width was 0.125 mm due to the eccentricity of the B $_{4}$ C and the cladding, heat transfer rates in the circumferential direction distributed within 25%. If the gap width is around 0.5 mm and the gap is charged with helium gas, the gap conductance can be predicted by thermal conductance and radiation.