Isao Murata

Prof. Dr. Isao Murata

orcid

Research Focus & Metrics

Academic Career Length

36Years (1991-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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1 March 2022 in Applied Radiation and Isotopes
Verified
Journal Article
Closed access
IMIsao Murata
Isao Murata
Sachie KusakaSachie Kusaka
Sachie Kusaka
KMKentaro Minami
Kentaro Minami
NSNobuhide Saraue
Nobuhide Saraue
STShingo Tamaki
Shingo Tamaki
FSFuminobu Sato
Fuminobu Sato

1 January 2014 in Progress in Nuclear Science and Technology
Verified
Journal Article
Open access
IMIsao Murata
Isao Murata
ITIehito Tsuda
Iehito Tsuda
RNRyotaro Nakamura
Ryotaro Nakamura
SNShoko Nakayama
Shoko Nakayama
MMMasao Matsumoto
Masao Matsumoto
HMHiroyuki Miyamaru
Hiroyuki Miyamaru

12 May 1999 in Nuclear Science and Engineering
Verified
Journal Article
Closed access
KOKokoo
Kokoo
IMIsao Murata
Isao Murata
ATAkito Takahashi
Akito Takahashi
A two-dimensional energy and time-of-flight charged-particle spectrometer has been developed and used to measure the double-differential cross-section (DDX) data of (n, xp) and (n, xα) reactions for several elements with 14.1-MeV incident neutrons at OKTAVIAN, the Intense 14-MeV Neutron Source Facility of Osaka University. The DDX data of the 51V(n, xp), 51V(n, xα), natFe(n, xp), natFe(n, xα), 59Co(n, xp), 59Co(n, xα), natNi(n, xα), natCu(n, xα), 93Nb(n, xp), 93Nb(n, xα), and natMo(n, xp) reactions are measured. The angle-integrated energy differential cross-section (EDX) data were deduced from the measured DDX data and compared with other experimental results [except for the 59Co(n, xp) reaction] and evaluated nuclear data of JENDL fusion file (JENDL-FF). A comparison was also done with the ENDF/B-VI for the total reaction cross sections of all measured reactions except for the natMo(n, xp) reaction and the EDX of the natNi(n, xα) and natCu(n, xα) reactions. The theoretical calculations were done...

3 March 2022 in Biology
Verified
Journal Article
Open access
PDF file
Sachie KusakaSachie Kusaka
Sachie Kusaka
YMYuri Morizane
Yuri Morizane
YTYugo Tokumaru
Yugo Tokumaru
STShingo Tamaki
Shingo Tamaki
IMIndah Rosidah Maemunah
Indah Rosidah Maemunah
IMIsao Murata
Isao Murata
Recently, exploitation of cerebrospinal fluid (CSF) circulation has become increasingly recognized as a feasible strategy to solve the challenges involved in drug delivery for treating brain tumors. Boron neutron capture therapy (BNCT) also faces challenges associated with the development of an efficient delivery system for boron, especially to brain tumors. Our laboratory has been developing a system for boron delivery to brain cells using CSF, which we call the “boron CSF administration method”. In our previous study, we found that boron was efficiently delivered to the brain cells of normal rats in the form of small amounts of L-p-boronophenylalanine (BPA) using the CSF administration method. In the study described here, we carried out experiments with brain tumor model rats to demonstrate the usefulness of the CSF administration method for BNCT. We first investigated the boron concentration of the brain cells every 60 min after BPA administration into the lateral ventricle of normal rats. Second, we measured and compared the boron concentration in the melanoma model rats after administering boron via either the CSF administration method or the intravenous (IV) administration method, with estimation of the T/N ratio. Our results revealed that boron injected by the CSF administration method was excreted quickly from normal cells, resulting in a high T/N ratio compared to that of IV administration. In addition, the CSF administration method resulted in high boron accumulation in tumor cells. In conclusion, we found that using our developed CSF administration method results in more selective delivery of boron to the brain tumor compared with the IV administration method.

1 January 1991
Verified
Book Chapter
Closed access
PDF file
YTYoshinobu Tsuji
Yoshinobu Tsuji
TYTakashi Yanuma
Takashi Yanuma
IMIsao Murata
Isao Murata
CFChizuru Fujiwara
Chizuru Fujiwara

1 April 2019 in Review of Scientific Instruments
Verified
Journal Article
Closed access
PDF file
ETEiji Takada
Eiji Takada
TAT. Amitani
T. Amitani
AFA. Fujisaki
A. Fujisaki
KOKunihiro Ogawa
Kunihiro Ogawa
Takeo NishitaniTakeo Nishitani
Takeo Nishitani
IMIsao Murata
Isao Murata
Time-resolved triton burnup studies have been carried out to estimate the behavior of alpha particles in DD fusion experimental devices. In those studies, 14 MeV neutrons emitted through DT reactions in DD plasmas should be measured selectively in the backgrounds of DD neutrons and gamma rays. For this purpose, a scintillating-fiber (Sci-Fi) based fast-neutron detector has been adapted because of its advantages such as fast response, design flexibility in detection efficiency by changing the number of Sci-Fi, and discrimination property against 2.4 MeV neutrons produced through DD reactions and gamma rays. However, its length had conventionally been set to around 10 cm without an optimization study of its design parameters to meet the requirements as 14 MeV neutron detector. In the present study, we tested three types of Sci-Fi detectors with three different lengths and compared with the simulated results of energy deposition, through which we tried to understand the phenomena in the detection process of fast neutrons. From the results, it has been shown that, due to the self-shielding of neutrons by Sci-Fi and the attenuation of scintillation photons during the transmission process to the photomultiplier tube, the optimal length of Sci-Fi is concluded to be about 6 cm.