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Oyama, Yukio; Ikeda, Yujiro; Arai, Masatoshi; Morii, Yukio
Nihon Genshiryoku Gakkai-Shi ATOMO
, 51(1), p.14 - 19, 2009/01
The beam commissioning of the J-PARC facilities of which the construction was started in 2001 is now progressed toward completion at the end of JFY2008. Of the J-PARC facilities, especially the pulsed neutron source with the world highest performance is able to open a new era of neutron application research. In this article, the outline of J-PARC, the pulsed neutron source which will start the user operation on December 2008, and their neutron instruments which is under construction are introduced. The neutron research is one of the important applications of quantum beam technology and expected to expand to broad research area such as bio-science, materials science, industrial use, etc. by start of J-PARC utilization. The latest achievement of neutron research mostly conducted at the JRR-3 research reactor in operation and future prospect are overviewed.
Harjo, S.; Moriai, Atsushi; Torii, Shuki; Suzuki, Hiroshi; Suzuya, Kentaro; Morii, Yukio; Arai, Masatoshi; Tomota, Yo*; Akita, Koichi*; Akiniwa, Yoshiaki*
Materials Science Forum, 524-525, p.199 - 204, 2006/00
An engineering diffractometer designed to solve many problems in materials science and engineering including investigations of stresses and crystallographic structures within engineering components is now being developed at J-PARC project. This instrument views a decoupled-poisoned liquid H
moderator, and the primary and the secondary flight paths are 40 m and 2.0 m, respectively, for 90 degree scattering detector banks. The optimization of this instrument has been performed with a Monte Carlo simulation, and an appropriate resolution of less than 0.2 % in 
d/d has been confirmed. A prototyped radial collimator to define a gauge width of 1 mm has been designed and manufactured. From performance tests conducted at the neutron diffractometer for residual stress analysis RESA, the normal distribution with a full width at half maximum of 1.0 mm was obtained in a good agreement with the simulation.
Koike, Yoshihiro; Metoki, Naoto; Morii, Yukio; Kobayashi, Tatsuo*; Ishii, Tomohiko*; Yamashita, Masahiro*
Journal of the Physical Society of Japan, 69(12), p.4034 - 4042, 2000/12
Times Cited Count：6 Percentile：46.5(Physics, Multidisciplinary)no abstracts in English
Morii, Yukio; Isshiki, Masahiko
Kessho Kaiseki Handobukku, p.111 - 114, 1999/09
no abstracts in English
Morii, Tadashi*; *; Okamoto, Michiaki*; *
PNC TJ9216 98-003, 96 Pages, 1998/02
It is necessary for conforming the validity of the design based leak(DBL) of a FBR SG to evaluate the phenomena of sodium-water reaction. In this work, in order to analyze the temperature distribution in the sodium-water reaction area, we carried out the following work with using the multi-phase hydrodynamics analysis code 'CHAMPAGNE'. (1)The verification of validity of the code by the parameter analysis of the SWAT-3 Run-19 system. (2)The analyses of the actual SG. The following results have been obtained by these work. (a)The appropriate mesh division model of the helical type tubes and the boundary condition of the Run-19 system have been set. (b)The effects of the main model element (such as pressure drop in the tube group, the distributing method of reaction heat to liquid and gas phase and the reaction rate constant) on the analyses have been well understood. (c)The results of the analyses of the Run-19 system by the present optimal parameters have shown that maximum temperature level is proper. However, non-reaction steam area have been estimated more widely than originally. Therefor, it is necessary for improvement to improve the tube model and to expand the 2 dimension model to the 3 dimension model. (d)The result of the analysis which treated the cover-gas pressure as parameter have shown that the reaction temperature rises by about 50
C when the cover-gas pressure rises from 1.45 to 3.8kg/cm
. (e)The results of the analysis of the actual SG with the flow of sodium has shown that the flow of sodium causes the vertical vibration of the reaction area, and high-temperature area doesn't exist stably. It indicates that it is difficult for tubes overheating rupture to happen. It is necessary to ascertain whether or not the vertical vibration occurs under the other condition.
Igawa, Naoki; Nagasaki, Takanori*; Ishii, Yoshinobu; Noda, Kenji; Ono, Hideo; Morii, Yukio; Fernandez-Baca, J. A.*
J. Mater. Sci., 33, p.4747 - 4758, 1998/00
Times Cited Count：6 Percentile：31.55(Materials Science, Multidisciplinary)no abstracts in English
Morii, Yukio; Isshiki, Masahiko
Radioisotopes, 45(11), p.717 - 721, 1996/11
no abstracts in English
D
nni, A.*; Kitazawa, Hideaki*; Fischer, P.*; Tang, J.*; Kogi, M.*; Endo, Yasuo*; Morii, Yukio
Journal of Physics; Condensed Matter, 7, p.1663 - 1678, 1995/00
Times Cited Count：32 Percentile：83.43(Physics, Condensed Matter)no abstracts in English
TiS
*; *; *; Morii, Yukio
Physica B; Condensed Matter, 213-214, p.396 - 398, 1995/00
Times Cited Count：11 Percentile：57.83(Physics, Condensed Matter)no abstracts in English
X (X=Ge,Si)S.Purwanto*; *; *; Morii, Yukio; Funahashi, Satoru; *; *
Physica B; Condensed Matter, 213-214, p.318 - 320, 1995/00
Times Cited Count：3 Percentile：25.65(Physics, Condensed Matter)no abstracts in English
-UN
Serizawa, Hiroyuki; Fukuda, Kosaku; Ishii, Yoshinobu; Morii, Yukio; *
Journal of Nuclear Materials, 208, p.128 - 134, 1994/00
Times Cited Count：16 Percentile：78.48(Materials Science, Multidisciplinary)no abstracts in English
O
*; *; Morii, Yukio; *; Funahashi, Satoru; *; *; *; *
Journal of Solid State Chemistry, 112, p.429 - 437, 1994/00
Times Cited Count：33 Percentile：82.25(Chemistry, Inorganic & Nuclear)no abstracts in English
Igawa, Naoki; Ishii, Yoshinobu; Nagasaki, Takanori; Morii, Yukio; Funahashi, Satoru; Ono, Hideo
Journal of the American Ceramic Society, 76(10), p.2673 - 2676, 1993/10
Times Cited Count：49 Percentile：93.3(Materials Science, Ceramics)no abstracts in English
P
Si amorphous alloysOnuma, Masato*; *; Kuwano, Hisashi*; Katano, Susumu; Morii, Yukio; Funahashi, Satoru; H.R.Child*; *
Mater. Trans. JIM, 34(10), p.874 - 881, 1993/10
Times Cited Count：12 Percentile：69.33(Materials Science, Multidisciplinary)no abstracts in English
SrYCuO
(
=0,1.67) by powder neutron diffraction*; *; Morii, Yukio; Funahashi, Satoru
Physica C, 210, p.529 - 535, 1993/00
Times Cited Count：5 Percentile：34.09(Physics, Applied)no abstracts in English
*; *; *; *; *; *; *; Morii, Yukio; ; Funahashi, Satoru
JJAP Series, 7(7), p.59 - 67, 1992/00
no abstracts in English
NiO
*; *; *; *; *; *; *; *; Morii, Yukio; ; et al.
Physica C, 185-189, p.579 - 580, 1991/00
Times Cited Count：16 Percentile：69.08(Physics, Applied)no abstracts in English
Chitose, Keiko*; Morii, Tadashi*
PNC TJ9214 90-004, 123 Pages, 1990/06
In the experimental fast reactor "JOYO", PNC(Power Reactor and Nuclear Fuel Development Corpolation) schedules to move two control rods from the third row of core to the fifth row, for the expansion of irradiation space, as the preparation for the shift to high power core, Firstly, only one control rod is moved. In this case, the reactivity worth of the control rod will decrease, because the control rod is shifted to outer region which has small reactivity worth. This study investigates the effect of the decrease of the reactivity worth of control rods on the transient of the accidents described in the present application of license. If the scram worth is about 0.067K/K(decreasing from 0.074 K/K), the maximum temperatures of core increase. The change of the scram worth has an effect on the TOP(Transient overpower) accidents, but little effect on the LOF(Loss of Flow) and LOHS(Loss of Heat Sink) accidents. Then it proves that all of these maximum temperatures satisfy the safety criteria.
Morii, Tadashi*; *
PNC TJ9214 90-002, 93 Pages, 1990/04
In the experimental fast reactor "JOYO", PNC (Power Reactor and Nuclear Fuel Development Corporation) schedules to move one control rod from the inner third row of the core to the outer fifth row. Two topics have been studied in order to get a license for the shift of control rod. Firstly, the work energy generated from expansion of the disruptive core material after the hypothetical core disruptive accident have been calculated by the VENUS code. The results show that the work energy of the core after the shift of one control rod increase by about 5MJ to 78 MJ compared with that of the core before the shift, but is still smaller than 120 MJ of the work energy described in the present documentation for petition of a license. Secondary, the effect of the reactor scram under the condition of the two rods stuck has been analyzed to examine a decrease of the safety margin of the scram worth. The calculated results of the HARHO-IN code shows that the consequences of the representative 4 accidents which are described in the present documentation for petition of a license are acceptably small.
Morii, Tadashi*; Kinjo, Hidehito*
PNC TJ9214 89-008, 74 Pages, 1989/11
Effects of pin failure during Power-to-Melt test performed in the experimental fast reactor "JOYO" have been analyzed in the present study in order to obtain a license for the test. The accident scenario of the present study is that after a clad failure of a test pin, melted fuel is released and forms blockage of fuel and stainless steel debris in a coolant flow area of a compartment in the test assembly. The follwing subjects have been investigated in the present study. (1)Blockage in the coolant flow area. (2)Contact of melted fuel with compartment. Conclusions are summarized as follows. (1)Under a hypothetical assumption in which all 4 test pins are melted and form a blockage, if the outer surface of the compartment is cooled by Na flow of an about 2200kg/(m
s), the integrity of the compartment is assured. (2)If melted fuel released from the test pin directly come in contact with the inner surface of the compartment, the calculated results show that the fuel can not melt through the compartment.
