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1S01 Decommissioning of Fukushima Daiichi
NPP with Radiochemistry
YAMANA, H.
(Nuclear
DamageCompensation
andDecommissioning Facilitation Corporation)
For the decommissioning of Fukushima Daiichi
NPP (1F), which suffered from severe accident in2011, various measures have been taken for theunprecedentedly difficult challenges, such as
contaminated water issue, recovery of fuel-debris
and spent nuclear fuels, radioactive waste
management, etc. In this report, the latest statusof 1F decommissioning will be given with a
special focus on the importance and points ofradiochemical subjects.
In the three units of 1F, essential boundaries (fuelcladding, PCV and RPV) were lost, and as aresult, some of nuclear fuel materials and fission
products are existing in an extremely abnormal
condition. They are fuel-debris in reactor
building, spent nuclear fuels stored in storage
pools, massive amount of rubbles contaminatedwith leaked radioactive nuclides, radioactive
contaminated water, secondary wastes generated
from water purification, etc. Thanks to theemergency measures taken during these 9 years,
stability has been ensured, and it is expected tostart mid and long-term operation to lower withspecially devised methods the existing
radiological risks by dissolving abnormal
situations.
Lot of difficulty is expected in future, in terms ofsevereradiation
conditions,insufficientunderstanding on the property and behavior of
the contaminated substances, and massive
amount and diversity of the contaminatedsubstances. The “uncertainty” is the substantial
key of this challenge, in which utilization of
remote devices and other special technologies,
and, it will need thorough and careful preparationand operation to get over this big “uncertainty”.
Reduction of the uncertainty will surely improve
the safety and cost, but there still exist many
problems to be solved, particularly of theinsufficient understandings on the radiochemical
properties and behaviors of the damaged facilities

and the site. The operation will be greatly
improved by radiochemical affairs, such as theenhanced elucidation of the properties andchemical behavior of the wastes and fuel-debris,strengthened capability in analysis and chemical
design for decontamination and stabilization, as
well as for the contaminated water management,
and strengthened evaluation of radiologicalsafety and environmental behaviors.
The importance of the radiochemical approach iscommon for the clean-up of the world
nuclear-legacy sites, which are the results ofimproper operations in the past. In this paper, theauthor wants to focus on the importance ofsharing among the members of JNRS themeaning and direction of radiochemical
researchesfortheresponsetothenuclear-legacies.
1A01
Creation of chemical separation
methods and the determination of excitation
functions for Np-spike production
NAKAJIMA,
A.1,
SAKAGUCHI,
A.1,
2
3
HAYAKAWA, Y. , HABA, H. , MATSUMURA,
N.2, TERANISHI, K2., MORITA, R.2,
YOKOKITA, T.3, KOMORI, Y.3, YANG, W.3,
MORI, D.3, HARIN, K.4, YAMASAKI, S.1,
ZHENG, J.5, SUEKI, K.5, YOKOYAMA, A.2(1Univ. of Tsukuba., 2Kanazawa Univ., 3RIKEN.,
4
Vienna Univ., 5QST)
237
Np (T1/2=2.14×106 y), which is released into
the environment through human nuclear activity
and remains in the environment as a harmful
mobile nuclide for long periods of time, is also a
useful environmental dynamics tracer. However,no comprehensive research has been conducted
due to the unavailability of an Np ‘spike’ that canbe used to correct chemical yields and determine
instrument efficiency. In our search for a new
Np-spike we focused on 236gNp (T1/2=1.54×105 y),and attempted to produce such spike through232
Th(7Li, xn)239-xNp reactions. With this as ourstated purpose, we conducted experiments
wherein we irradiated a 7Li2+ beam onto 232Th.
We also created appropriate chemical separation
methods to extract and purify the Np isotopes

from the irradiated Th. We successfully createdchemical separation methods for theseexperiments using TEVA, TK400 and UTEVA
resins. The generation of 236mNp was confirmedin stacked Th foils, and the cross sections of232
Th(7Li, 3n) 236mNp for some Li energies wereobtained through experiments. The 236gNp and237
Np ratios and concentrations will be given
using AMS and SF-ICP MS.
1A02 An effect of incomplete fusion on the Np
production in the 232Th + 7Li reaction
TERANISHI, K.1, MORITA, R.1, HAYAKAWA,
Y.1, SAKAGUCHI, A.2, NAKAJIMA, A.2,
KOMORI, Y.3, YOKOKITA, T.3, MORI, D.3,
HABA, H.3, YOKOYAMA, A.1(1Kanazawa University, 2University of Tsukuba,
3
RIKEN)237
Np (t1/2 = 2.1×106 y), which is produced innuclear facilities and needs to be investigated forenvironmental pollution, is expected to beanalyzed by accelerator mass spectrometry(AMS). The measurement of 237Np by AMS
needs 236gNp (t1/2 = 1.5×105 y) as a spike. Our
research group has collected the reaction crosssections in the 232Th + 7Li reaction as afundamental data for the spike production. As
well as complete fusion reaction (CF),incomplete fusion reaction (ICF) occurs
especially in the reaction of 7Li which splits into
D and t and only a part of the projectile fuses withthe target nucleus. In this study, the excitation
function of Pa, a product of ICF, was measured,and the mechanism of ICF was discussed bycomparing the experimental values with those
calculated by code EMPIRE. In addition, we
estimated the total reaction cross sections of Pa
and Np formation and investigated the effect ofincomplete fusion reaction on the whole reaction.
1A03 A recoil correction method of fission
cross section measurement in the 232Th+7Li
reaction
MORITA, R.1, TERANISHI, K.1, HAYAKAWA,
Y.1, SAKAGUCHI, A.2, NAKAJIMA, A.2,

KOMORI, Y.3, YOKOKITA, T.3, HABA, H.3,
YOKOYAMA, A.1(1Kanazawa Univ., 2Univ. of Tsukuba,3Riken.)
We are much interested in the 232Th+7Li reaction
owing to a possible candidate for the productionof 236gNp. The nuclide is expected to be produced
mainly at incident energies less than 40 MeV. We
aim to measure the fission cross sections at therelevant energies as fundamental data. However,catcher foils for fission fragments make muchenergy loss of Li projectiles and prevent one fromobtaining several data points in one stack at thesame irradiation. In this study, we derived aformula for the probability of fragments recoilingout from targets. Comparing the calculated datawith the recoil data we measured in the same
system, apparent fission cross section for eachfoil in a stack was corrected. The method wasfound to be useful not only in obtaining several
data in one stack irradiation, but also in reducing
the cost of experiment.
1A04
Production of 225Ac in the14Th( N,xnyp)225Ac reaction
YIN, X., NAMBU, A., KOMORI, Y., MORI, D.,
HABA, H.
(1RIKEN Nishina Center)225
Ac is one of the most promising alpha-particle
emitting radionuclides for targeted radionuclide
therapy. However, a stable supply system of 225Ac
has not been established yet in Japan even at thebasic research scale (~100 MBq). In this work,
we investigated the production of 225Ac in the232
Th(14N,xnyp)225Ac reaction by the RIKEN
multitracer technique. Production cross sectionsof 225Ac and its precursor 225Ra were determinedat 132 and 116 MeV/u by irradiating metallic
232
Th targets (69 mg/cm2 × 6) and 27Al energy
degraders (415 mg/cm2 × 2) with a 132 MeV 14N
beam (20 pnA) extracted from RIKEN Ring
Cyclotron. The cross sections were discussed bycomparing with those calculated by the PHITS(Particle and Heavy Ion Transport code System)
code. Based on our typical experimental
conditions (incident beam energy: 132 MeV;
beam intensity:  Sȝ$ WDUJHW WKLFNQHVV 232

g/cm2; irradiation time: 2 days), it was estimatedthat 150 MBq of 225Ac can be produced at the endof the irradiation. In the symposium, the chemical
separation procedure of 225Ac and the quality ofthe purified 225Ac will also be presented.
1A05 Astatine chemistry elucidated in the
purification of no-carrier-added astatine bydry distillation
NISHINAKA, I.1,2, HASHIMOTO, K.1,
ISHIOKA, S.N.2, WATANABE, S2, SASAKI, I.2,
AZIM, M.A.3(1QST Tokai, 2QST Takasaki, 3BAEC NINMAS)
211
At was produced in the 209Bi(4He, 2n)209Bi
reaction. The yield was separated from theirradiated bismuth target by a simple method,
based on dry distillation. The optimized
conditions of the method were studied bymonitoring the astatine radioactivity with
CdZnTe gamma-ray spectrometers. Dry
distillation was accomplished within 6 min ofheating the bismuth targets at the bottom of the
WHVW WXEH ZLWK DQ HOHFWULF IXUQDFH DW  ႏ
Cooling the middle of the test tube enabled therecovery of 211At radioactivity in high yields. The
no-carrier-added 211At solutions were obtained inhigh yields (26-75%.) by rinsing with theutilization 1.6 mL of eluents, such as distilledwater, ethanol, methanol, or chloroform.
Thin-layer chromatography (TLC) analysis
revealed that the astatine forms stable anions, At–,
AtO3–, and AtO4–, in ethanol and aqueous
solutions, and these anions are readily oxidized
and/or reduced between them in dynamic
equilibria owing to the more electropositive
character of astatine than other halogens.
High-performanceliquidchromatography(HPLC) identified large amounts of AtO3– andAt–, with lower oxidation states. The observationof different composition profiles by TLC andHPLC suggests that the TLC results weredifferent from the composition profiles ofastatine species.

1A06 Production of an atomic beam by
ion-electron recombination for atomic-beamspectroscopy of superheavy elements
SUZUKI, H.1,2, ITO, Y.2, SATO, T.1,2, AOKI,
R.2,3, TSUKADA, K.2, ASAI, M.2, NAGAME,
Y.2(1Graduate school of science and engineering,
Ibaraki Univ., 2ASRC JAEA, 3Department ofscience, Ibaraki Univ.)
In the heavy element region, there is a possibilityof violation of periodicity on electronic structureof an atom by the influence of the relativistic
effect. Especially, focusing on the ground-stateelectronic configuration of Lr (Z = 103), thevalence electron orbital takes 7p1/2 rather than
6d3/2 assumed from the periodic rule. Our grouphas succeeded in measuring the first ionization
potential of Lr in recent years and obtained astrong support for the 7p1/2[1].
In this work, we have developed an ion-electron
recombination atomic beam source for atomic
beam
spectroscopy.
Anion-electron
recombination has an advantage of producing a
low-energy atomic beam and small chemical
dependence. In this system, the ion beam isadjusted by ion optics and injected into thehigh-density electron cloud. Then, it isrecombined with electrons to produce an atomic
beam.
In our experiments, the neutralization was
indirectly evaluated by measuring the decay of
the ion beam current using Rb+ beam. As a result,nearly 100 % reduction of the ion beam current
through the center of the electron cloud wasobserved. After improving the ion optics, we aredeveloping the detector for direct measurementof atom. In the presentation, we will report on theexperimental results and the future prospects.
[1] T.K. Sato, et al., Nature 520 209 (2015).
1A07
Direct mass measurement ofsuperheavy nuclei 257Db via MRTOF+Į-TOF
NIWASE, T.1,2,3, SCHURY, P.3, WADA, M.3,
BRIONNET, P.2, CHEN, S.4, HASHIMOTO, T.5,
HABA, H.2, HIRAYAMA, Y.3, HOU, D.S.6,7,8,
IIMURA, S.9,2,3, ISHIYAMA, H.2, ISHIZAWA,

S.10,2, ITO, Y.11, KAJI, D.2, KIMURA, S.2,
KOURA, H.11, LIU, J.J.4, MIYATAKE, H.3,
MOON, J.Y.5, MORIMOTO, K.2, MORITA, K.1,2,
NAGAE,
D.1,
ROSENBUSCH,
M.2,
TAKAMINE, A.2, WATANABE, Y.X.3, XIAN,
S.X.4, YAN, S.X.12, WOLLNIK, H.13
(1Kyushu Univ., 2RIKEN, Nishina Center.,
3
KEK., 4HongKong Univ., 5IBS., 6IMP., 7
University of Chinese Academy of Science,8
Lanzhou Univ., 9Osaka Univ., 10Yamagata Univ.,
11
JAEA, 12Jinan Univ. 13NMSU)
The atomic mass is an important quantity thatfaithfully reveals the interactions between
nucleons of each nuclide. According to the liquid
drop model, superheavy elements cannot exist
due to the fission barrier. Therefore, their
existence is permitted solely by the shell effect,
and mass is an exclusive quantity that can explore
for shell effect of each nucleus.
Previously, the mass of heavy nuclides includingtransfermium isotopes produced in fusion
reactions has been measured by using an
MRTOF-MS combined with GARIS-II. Recently,
a novel Į- TOF detector has been developed. It is
possible to measure mass and correlated decay
properties. The decay signal as a fingerprint ofsuperheavy nuclei also enables highly accurate
measurement to distinguish from backgroundswith just a few events per day.
Experiments were performed with RIKEN Ring
Cyclotron. We succeeded the first direct massmeasurement of the superheavy element 257Db
isotopes, produced in the 208Pb(51V, 2n) reaction,by use of the MRTOF-MS equipped with an
Į-TOF. We observed 11 events withtimes-of-flight consistent with that expected for257
Db followed by the detection of an alpha-decay
consistent with 257Db or one of its decay products.
In this presentation, we will report the details of
the experiment and result.
1A08 Development of an RF ion-collection
system for nuclear-chemistry studies
SHIGEKAWA, Y.1, YAMAGUCHI, A.1, SATO,
N.1, TAKAMINE, A.1, WADA, M.2, HABA, H.1(1RIKEN, 2KEK)The RF ion-collection apparatus, consisting of agas cell and an RF carpet, allows the rapid
deceleration and transportation of high-energy RIions, and has been used for nuclear-physics
studies such as precision mass measurement ofheavy nuclei. Applying this type of apparatus tonuclear-chemistry studies enables new studies
such as gas-phase chemistry of short-lived
superheavy elements (half-life <1 s). In this study,
we developed a new RF ion-collection apparatus
for nuclear-chemistry studies, and evaluated ion
extraction time and efficiency. The constructed
apparatus includes a cryogenic He gas cell, where
purified He gas is introduced; the cooling andpurification systems reduce impurities andprevent ions from reacting with impurities. The
ions decelerated inside the gas cell aretransported to an RF carpet with a DC electricfield gradient, then to the central hole of the
carpet with the RF-surfing technique, andsubsequently to a high vacuum through aquadrupole ion guide. To evaluate ion extraction
time and efficiency, we extracted 220Rn ionsrecoiling out of a 224Ra source at various
conditions. We determined the maximum
extraction efficiency to be 60–70%. The
extraction times were ~20 and ~30 ms at 100 and
200 mbar of He gas, respectively (the pressures
are obtained by converting the pressures at low
temperature to the ones at room temperature).
The developed apparatus allows efficient
extraction of ions with half-lives >100 ms,
leading to nuclear-chemistry studies using
short-lived RIs that have been difficult to study
thus far.
1A09 Half-life determination of nuclear
excited states of 229Th by WKH Į-Ȗ coincidence
measurement of 233USHIGEKAWA, Y.1, YAMAGUCHI, A.1,
SUZUKI, K.2, HABA, H.1, HIRAKI, T.2,
KIKUNAGA, H.3, NISHIMURA, S.1, SASAO,
N.2, YOSHIMI, A.2, YOSHIMURA, K.2(1RIKEN, 2Okayama Univ., 2Okayama Univ.,
3
Tohoku Univ.)

The first nuclear excited state of 229Th, 229mTh,
has an excitation energy as low as 8.3 eV, which
may allow nuclear half-life variation depending
on chemical environments and realization of an
ultraprecise nuclear clock. Although the internalconversion process of 229mTh has been recently
observed, the Ȗ-rays from 229mTh have never been
observed clearly. Elucidating the properties ofhighly excited states of 229Th is important toestimate the half-OLIH RI WKH Ȗ-ray emission of
229m
7KZKLFKKHOSVXVWRPHDVXUHWKHȖ-rays from229m
Th. In this study, we measured the half-livesof some highly excited states of 2297KWKURXJKĮ-Ȗcoincidence measurement of 233U. A 233U source
prepared by electrodeposition was placed in a
vacuum chamber. The detection timing and
HQHUJ\ RI Į SDUWLFOHV IURP WKH VRXUFH ZHUH
measurHG XVLQJ D 6L GHWHFWRU ZKLOH WKRVH RI Ȗ
rays were measured using a LaBr3(Ce) scintillator.
From the 4784-NH9ĮSDUWLFOHVDQGWKH-keVȖ UD\V ZH GHWHUPLQHG WKH KDOI-life of the42.4-keV state to be 171(4) ps, which isconsistent with the literature value. The half-life
determined for the 97.1-keV state was different
from the literature value. We successfully
determined the half-lives of the 163.2-keV and
71.8-keV states for the first time. Based on theobtained half-lives, we will estimate and report
the half-OLIHRIWKHȖ-ray emission of 229mTh.
1A10 Discovery of 234Np isomer and its decay
properties
ASAI, M.1,2, SUEKAWA, Y.2, HIGASHI, M.2,
KAMADA, H.3, TOBE, T.4, ANDREYEV,
A.N.1,5, HIROSE, K.1, ITO, Y.1, MAKII, H.1,
NISHIO, K.1, NIWASE, A.2, ORLANDI, R.1,
SAKAMA, M.6, SATO, T.K.1, SHIBATA, M.7,
SUZAKI, F.1, SUZUKI, H.1, TOKOI, K.1,
TOMITSUKA, T.1, TSUKADA, K.1(1JAEA, 2Kyushu Univ., 3Nagoya Univ., 4Kyoto
Sangyo Univ., 5Univ. York, 6Tokushima Univ.,
7
Nagoya Univ. RI)
A new isomer 234mNp with a half-life of ~9 min
has been discovered. It was produced in thereaction of 233U target with 6Li beam at JAEA
tandem accelerator, and was identified throughcharacteristic X-ray measurement and mass
separation with an on-line isotope separator(ISOL). Gamma-ray singles, gamma-gamma
coincidence, and internal-conversion electron
measurements were performed. It was revealed
that the 234mNp decays mostly through an
isomeric E4 transition followed by an M1
transition, and that the spin-parity of the 234mNp
should be 5+. The results are introduced in detail,and the nuclear structure of the 234mNp are
discussed.
1B01
A thermodynamic study on thecomplexation of actinides with transferrin
SUZUKI, T., KOBAYASHI, T., SASAKI, T.
(Kyoto Univ.)
In the present work, we focused on thecomplexation of actinides with transferrin.
Transferrin known as a transporter of ferric ionsin human blood can play an important role inin-vivo kinetics of actinides. However, a detailed
complexation mechanism of actinides with thecoordination sites of transferrin is not well known.
Thermodynamic data of the complexation ofactinides and transferrin would be importantwhen considering an elimination of actinides
from blood by using chelating medicines. In thiswork, complexations between transferrin anduranium (U(VI)), thorium (Th(IV)) andzirconium (Zr(IV)) as a chemical analog ofplutonium were investigated by UV-Vis
spectrometry.
Aliquots of U(VI) or Zr(IV) carbonate stock
solution equivalent to 0.2~10 mole were added
into transferrin solution in constant concentration(0.01~0.06 mM). Aliquots of thorium NTA stock
solution were also prepared and mixed with thetransferrin stock solutions.
An absorption peak at 240~250 nm appeared in
the mixture of U(VI) and transferrin. Under theconstant metal-transferrin ratio, an absorption
peak at 240~250 nm appeared and its intensity
depended on the total transferrin concentration
with a gradual shift of the peak position from 240
to 250 nm. Therefore, it seems that coordination

structures of metal complexes are different bytotal transferrin and metal concentration.
1B02 Development of a rapid analyticalmethod for U, Np, and Pu using ICP-MS and
ICP-MS/MS in urine samples for patient
screening after radiation accident
YANG, G., ZHENG, J., KIM, E., SENO, H.,
KOWATARI, M., KURIHARA, O.
(National Institutes for Quantum andRadiological Science and Technology)
Internal contamination with alpha-particle
emitting actinides, such as 238U, 237Np, 239Pu,
240
Pu, is likely to bring a large radiation exposure
dose to the patient even if the intake amount issmall. In order to provide timely information forprompting decision making in radiation
emergency medicine, we attempted to develop a
simple and rapid method based on the analysis ofultra-trace level of U, 237Np and Pu isotopes in asmall amount of urine samples (20–100 mL) by
the SF-ICP-MS and the ICP-MS/MS. A simple
single chromatographic column packed with 2
mL AG MP-1M resin (100–200 mesh, chloride
form, Bio-Rad, Hercules, CA, USA) was used forthe separation of targeted isotopes from thematrix elements and other potential interferences.
Uranium isotopes were measured using 233U as ayield tracer with a yield of ca. 10%. To avoid
polyatomic and tailing effects from U, 237Np and
Pu isotopes were collected after U fraction andmeasured using 242Pu as a yield tracer with a yieldof ca. 70%. Finally, 4 urine reference materials
with Pu addition and 3 urine reference materials
with U addition provided by the Association for
the PROmotion of Quality COntrol in
RADiotoxicological Analysis, France wereanalyzed by the proposed method and theconventional alpha spectrometry for validation.
1B03
Molecular-weight-dependent
distribution of humic acid induced by gammairradiation complexed with metal ions
ZHAO, Q., KOBAYASHI, T., SASAKI, T.
(Kyoto Univ.)

Gamma-irradiation field generated by radioactive
wastes has been recognized to affect theinteraction of the radionuclides leached out fromthe radioactive waste with humic acid in natural
groundwater. The molecular weight of thecomplexes would be critical for theenvironmental migration of radionuclides. In thepresent study, the effect of gamma-irradiation on
the chemical properties of humic acid (HA)
fractions, and the molecular-weight distributionof metal ions were investigated. The
gamma-irradiated humic acid fraction was
obtained by ultrafiltration into four fractions (>100, 50-100, 10-50, < 10 kDa). The experimental
results from total organic carbon measurement
and potentiometric titration suggested that someof irradiated HA molecules were degraded to thesmaller molecular weight, and phenolic –OH
would be a predominant functional group of thesmall-molecular-weight fractions after theradiolysis degradation. When an aliquot of Cs, Sr,
Eu (as an analog of trivalent actinides) stock
solution was added to the HA solutions, it isfound that more metal cations are graduallybelonging to the smaller molecular-weightfractions with dose.
1B04 Structure of ruthenium complex innitric acid solution estimated using DFT
calculation
KATO, A.1, KANEKO, M.2, NAKASHIMA,
S.1,3,4(1Grad. School of Sci., Hiroshima Univ., 2Japan
Atomic Energy Agency, 3N-BARD, Hiroshima
Univ., 4Grad. School of Advanced Sci. and Eng.,
Hiroshima Univ.)
The
Ru
atom
existsastrivalent3+
nitrosyl-ruthenium ion, [Ru(NO)] , in nitric acidsolution such as high-level liquid waste andforms the complex with H2O and NOí ligands.
The composition of the coordination species
varies depending on the concentration of nitricacid. In the previous experiment reports of[Ru(NO)(NO3)x(H2O)y] í[ í (x + y = 5 forunidentate NO3 coordination) system, thecomplexes with x = 0–4, especially,[Ru(NO)(NO3)3(H2O)2]
wereobserved
depending on the concentration of nitric acid.
However, such systematic properties of thenitrosyl-ruthenium complexes have not been
understood, although the precise modeling of
coordination geometries in nitric acid solution isrequired to understand the separation mechanism
in solvent extraction. Therefore, we performed
density functional theory calculation to thenitrosyl-ruthenium complexes, which included
the 12 patterns of geometrical structures of[Ru(NO)(NO3)x(H2O)í[] í[ í (x = 0–5), formodeling the stable coordination structures andcomplexation reactions of NO3í ligands toward[Ru(NO)(H2O)5]3+. The complexation reaction
withnitricacid
proceedingto[Ru(NO)(NO3)3(H2O)2] was confirmed byintroducing the effect of outer-sphere molecules.
In addition, the geometrical isomer, in which
NO3í was coordinated only to the equatorial
position of NO, was expected to be the moststable structure by using electron density
analyses.
1B05
Property of Dimetallofullerene
Encapsulating Promethium
SUWA, T.1, AKIYAMA, K.1, KIKUNAGA, H.2,
KUBUKI, S.1(1Grad. School Sci., Tokyo Metropolitan Univ.,
2
ELPH, Tohoku Univ.)
In recent years, it has been reported that thestability of dimetallofullerenes (di-EMF) with
two lanthanide atoms decreases with the increasein the atomic number of encapsulated lanthanides,
and also reported that the di-EMFs with heavy
lanthanides are stabilized by the reduction of
di-EMFs. In our previous work, we could nothave observed any promethium di-EMF species
under the atmospheric condition. In this work, we
reviewed the present scheme of metallofullerene
separation/extraction and tried to develop the
extraction apparatus under anaerobic condition.
About 1 g of Sm2O3 pellet was irradiated with 50
MeV bremsstrahlung radiation for 6 hours.
Produced promethium (Pm) was separated fromthis irradiated Sm pellet by the chemical

separation. The Pm tracer with a nitrate form wasdissolved to ethanol and mixed with Ce-139
radiotracer and La nitrate as a carrier. These Pm
solutions were adsorbed on a porous carbon rod
and sintered. These Pm carbon rods were set intoa fullerene generator and then discharged under
He atmosphere. Produced soot containing Pm
di-EMFs were refluxed under anaerobic
condition by using newly developed fullerene
extraction apparatus in this work. As a result, theradioactivity of extracted Pm under anaerobic
condition was found to be 3.3 times larger thanthat under atmospheric condition.
1B06 Development of mass spectrometricmethod for simultaneous determination ofhard-to-measure Pu isotopes in environmental
and reactor decommissioning waste samples
ZHENG, J.1, WANG, H.2, SHIKAMORI, Y.3, NI,
Y.4, AONO, T.1(1National Institutes for Quantum andRadiological Science and Technology, 2Univ.
South China, 3Agilent Technol., 4Peking Univ.
China)
Mass spectrometry, especially ICP-MS, as an
atom-counting approach, is gradually replacingalpha spectrometry as a main-stream techniquefor Pu isotopic analysis. However, as Pu is often
concomitant with a large (5-10 orders ofmagnitude) excess of U in environmental matrix,
which clearly obscures the determination of 238Pu
using any mass spectrometer due to the isobaric
interference from 238U. So far, there is noestablished mass spectrometric method for
simultaneous
determinationof
these
hard-to-measure 238Pu, 239Pu, 240Pu and 241Pu in
environmental mediums. In this study, wedeveloped an advanced mass spectrometry
method for simultaneous analysis of important
Pu isotopes (238,239,240,241Pu) using triple
quadrupole ICP-MS/MS by employing theion-molecule reaction separate 238U and 238Pu,
which was previously difficult to be measured.
By introducing a desolvation sample introduction
system, we succeeded in increasing 10 times thesensitivity of Pu isotopes and suppressing theproduction of uranium hydride, we achieved thedetection limit of fg level in on-mass mode. We
have developed a new low-temperature fusion
method for environmental and nuclear
decommissioning samples. By combining these
new sample preparation techniques with thedeveloped ICP-MS/MS detection, rapid Pu
isotope mass spectrometry methods forenvironmental samples and decommissioning
related waste samples were established.
1B07
Trace element composition ofradioactive particles
SUEKI, K.1, HASEGAWA, R.2, MATSUO, K.2,
ISHII, T.2, ADACHI, K.3, SATOU, Y.4(1Faculty Pure Applied Sci., Univ. Tsukuba,
2
Grad. Sch. Pure Applied Sci., Univ. Tsukuba,
3
MRI, 4JAEA CLADS)
There are radioactive particles that are insoluble
in water and are mainly composed of silicate,released by the Fukushima Daiichi Nuclear
Power Plant accident. Radioactive particles are
known to be roughly divided into two types andare characterized by the 134Cs/137Cs radioactivity
ratio. In this study, we carried out total
decomposition of type B radioactive particles bymixed acid, and measured multi-element
quantitative analysis by triple quadrupole
inductively coupled plasma mass spectrometry(ICP-QQQ-MS). It isn't possible to analyze thesilicon and the oxygen which are a main elementof a radioactive particle by ICP - QQQ - MS. We
added a result of the elemental analysis of aradioactive particle from a result of SEM/EDS
about several elements and got the wholeanalytical value. When correlation with Si waschecked, many elements had positive correlation,
but the coefficient of correlations of the several
elements (As, Se, Ag, Cd, Sn, Sb, Cs, Ba, Pb, andU) were not good. The 133Cs/137Cs ratio ranged
from 1 to 5, especially 6 out of 10 radioactive
particles were about 1, which was close to theratio that would be encountered in 235U neutron
induced fission. The included amount of U
showed with 1.0X10-3 - 4.6 ng. In particular, theparticle which included 4.6 ng indicated 10 to'

100 times compared with other particles. We
expect to contribute to guess at the process of theradioactive particle production as a result of theminor element constitution of obtained particles.

ー

1B08 Fluorescence
propertyofradiocesium-bearing microparticles emitted
from Fukushima Daiichi Nuclear Accident
ABE, Y.1,2, ONOZAKI, S.2, ISHIKAWA, M.1,
NAKAI, I.1, KITA, K.3, IGARASHI, Y.3,4,
OURA, Y.5, TSURUTA, H.6, MORIGUCHI, Y.7(1Tokyo Denki Univ., 2Tokyo Univ. Sci., 3Ibaraki
Univ., 4KURNS, 5Tokyo Met. Univ., 6RESTEC,
7
Univ. Tokyo)
Considerable amounts of radioactive materials
were released into the environment following the
Fukushima Daiichi Nuclear Power Plant(FDNPP) accident in March 2011. As a form ofradioactive materials emitted from the FDNPP,
radiocesium-bearing microparticles (CsMPs)
have been investigated by numerous researchers.
In this study, we focused on Type A of CsMP
which was widespread over the Eastern Japan at
the early stage of the accident, and investigatedits fluorescence property with the aim to propose
the rapid and easy detection method of CsMPsfrom environment. We isolated some Type A
CsMPs from aerosol samples collected just after
the accident and measured fluorescence spectrum
and fluorescence distribution of individual
particles using a multi-photon excitation
microscope. As the result, this study first
demonstrated that CsMPs emit characteristic
green fluorescence in response to certain
wavelengths of light. X-ray analyses of CsMPs
using synchrotron radiation X-ray microbeam
were carried out at SPring-8 and revealed thatthey contain a trace amount of U in the form of
UO22+ ion. We thus concluded that thefluorescence from Type A CsMP originate to
UO22+ ion, one of well-known strong
fluorescence species in silicate glass matrix.
1B09 Application of Kelvin Probe ForceMicroscopy to the measurement of surface

potentialofradiocaesium-bearing
microparticles
OKUDA, T.1, SHINKE, Y.1, KUROSAWA, K.1,
IWATA, A.1, SATOU, Y.2, ABE, Y.3, IGARASHI,
Y.4(1Keio Univ., 2JAEA, 3Tokyo Denki Univ.,
4
Kyoto Univ.)
The Fukushima Daiichi Nuclear Power Plant
accident
causedseriousemissionofradionuclides into the atmosphere. After several
years,
insoluble
radiocaesium-bearing
microparticles (CsMP) have been found in someregions in Japan. These insoluble solid particles
remain as a particle in human airways andcontinue emitting radiation when they are inhaled.
Therefore, these particles have a potentiallysignificant adverse effect on human health.
Because of the continuous emission of the Ⱦ-rays,
which is energetic electron beam, previous
studies reported that the radioactive particles
would have specific electrostatic charging
characteristics.
Also,
severallaboratory
experiments and numerical simulations haveshown that the electrostatically charged particles
are more deposited on the human respiratory
airway. Therefore, the electrostatic charging
characterization of the CsMP is important for theaccurate evaluation of its health effects. In thisstudy, we used Kelvin Probe Force Microscopy tomeasure the surface potential of CsMP. Charge
number controlled NaCl particles were alsomeasured to calibrate the surface potential
determined by KPFM and the actual charge
number. As a result, linear relationship between
charge number and surface potential wereobtained.
1B10 Analysis and simulated generation of
the radioactive particles emitted from the
Fukushima nuclear accident
INAGAKI, M.1, SATO, R.2, SEKIMOTO, S.1,
TAKAMIYA, K.1, OKI, Y.1, OHTSUKI, T.1(1KURNS, 2Kyoto Univ.)
After the Fukushima Daiichi Nuclear Power
Plant accident, various kinds of radioactive
materials were released to the surrounding

environment. Among those materials, large
amounts of glassy particles have been found. To
study physical and chemical properties of thoseglassy particles can make us understand what
happened in the nuclear reactors during theaccident. Therefore, we generated the simulated
glassy particles, and aimed at elucidation of theformation process of the particles. In this study,
we analyzed the actual glassy particles andconducted the simulated generation of theparticles. As a result of SEM observation of theactual glassy particles, diatomaceous earth was
discovered from the surfaces of the particles.
Diatomaceous earth is a strong candidate for thesource material of the particles. The simulatedparticles were produced by heating a mixture ofdiatomaceous earth and artificial seawater. Then,the simulated particles generated were studied by
SEM-EDS analysis. As a result of the analysis,
the simulated particles were similar to the actualglassy particles. One hypothesis is thatdiatomaceous earth and seawater that existed in
the reactor at the accident were heated, andradioactive materials were taken in and the glassy
particles were generated.
2S01 Studies on Transfer Parameters in the
Living-sphere for Estimation of Radiation
Dose to Humans from Environmental
Radionuclides
TAGAMI, K.
(Natl. Inst. Quantum Radiol. Sci. Technol.)
One important purpose to study transfer ofradionuclides in the environment is to assess theradiation effects to human beings. Accurate
measurements of low-level radionuclides in theenvironment
aretherefore
necessary;“radiochemistry” is a strong tool for these works.
Besides such data in environmental materials canprovide useful information, that is, transfer
parameters to express the ratio of radionuclidetransfer rate from one compartment to the other,i.e., from soil to plant. Parameter values havebeen used in mathematical models for dose
assessments; because we know that parametervalues have ranges so single datum is not trustful.

Thus collating parameter data as many as
possible by measuring of environmental samples,
doing tracer experiments and surveying
radiochemically sense literature values needs tobe carried out to make the dose estimation results
more accurate. I have been involved to measure
and collate parameter values obtained in Japanand that experience was highly helpful when the
Fukushima Daiichi Nuclear Power Plant accident
occurred. After the accident, using manymeasurement results of environmental samples,
we could provide transfer parameter values. At
the presentation, I will summarize our almost 10
years study results related to the accident.
2A01 Coprecipitation experiment of alkaline
earth elements with Barium sulfate, towards
the experiment of element 102, No.
HAYAMI, S.1, KASAMATSU, Y.1, WATANABE,
E.1,
NAKANISHI,
R.1,
TONAI,
K.1,
TAKAMIYA, K.2, SHINOHARA, A.1(1Grad. Sch. of Sci., Osaka Univ., 2KURNS,
Kyoto Univ.)
Nobelium (102No) belongs to an actinide series. It
is reported that stable oxidation state of No is +2
although those of other heavy actinide elements
are all +3. The chemical behavior of No in HCl
was reported to be similar to that of Group 2elements. Our group has investigatedcoprecipitation of No with the Sm hydroxide. For
newly investigating the chemical behavior of thedivalent elements and nobelium, we focused on
the reaction with sulfate ion.
In this study, we investigated sulfate
coprecipitation behavior for alkaline earth
elements using 47Ca, 85Sr, 133Ba, and 226Ra tracers
and discussed the applicability of this method tonobelium experiment. As a result, clear
differences in coprecipitation behaviors among
these elements were observed. The tendency ofthe sulfate coprecipitation yields for the elements
is consistent with the order of their solubility
products. We also found that there are no clear
differences between coprecipitation andprecipitation behaviors of alkaline earth elements.
Based on these results, we concluded that thismethod is able to be applied to the experiment ofNo.
2A02
On-lineIsothermal
Gas
Chromatographic Behavior of Oxychlorides
of Group-5 Elements, Nb, Ta, and Db
SATO, T.K.1,2, CHIERA, N.M.1,3, TOMITSUKA,
T.1, TOKOI, T.4, SUZUKI, H.1,2, ITO, Y.1, ASAI,
M.1, TSUKADA, K.1, SHIRAI, K.5, INOUE, H.5,
ADACHI, S.6, KASHIHARA, A.6, MAKII, H.1,
HIROSE, K.1, NISHIO, K.1, WATANABE, E.4,
SAKAMA, M.7, GOTO, S.5, NAGAME, Y.1(1Japan Atomic Energy Agency, 2Ibaraki Univ.,
3
Paul Scherrer Institute, 4Osaka Univ., 5Niigata
Univ., 6Univ. of Tsukuba, 7Tokushima Univ.)
The influence of strong relativistic effects on
chemical properties has been interesting in the
superheavy element region. Their chemical
properties, however, have not been investigatedsufficiently because of experimental difficulties
owing to their low production rates and shorthalf-lives. In order to elucidate the chemical
properties of dubnium (Db, Z = 105), we haveconducted
on-lineisothermalgaschromatographic experiments of oxychloride ofgroup-5 elements. We confirmed the formation ofvolatile oxychlorides of Db and its lighter
homologs Nb and Ta by using 262Db (half-life,
T1/2 = 33.8 s), 88Nb (T1/2 = 14.5 min.), and 170Ta(T1/2 = 6.76 min.), respectively. We successfully
determined the adsorption enthalpies of theoxychlorides of each element on the quartz
surfacefrom
theirisothermalgaschromatographic behavior. The obtained
volatility sequence of the group-5 elements is
IRXQGWREH1E!7D'E
2A03 Anion-exchange behavior of Db in
HF/HNO3 solution
KATO, M.1, ADACHI, S.1, TOYOSHIMA, A.2,
TSUKADA, K.3, ASAI, M.3, HABA, H.4,
YOKOKITA, T.4, KOMORI, Y.4, WANG, Y.4,
SHIGEKAWA, Y.4, MORI, D.4, KASHIHARA,
A.1, NAKAJIMA, A.1, SUZUKI, Y.1,
NISHIZUKA, K.1, TOKOI, K.2, SUEKI, K.1

(1Univ. of Tsukuba., 2 Osaka Univ., 3JAEA,
4
RIKEN)
A few studies have been so far performed on
aqueous chemistry of Db, the group-5
superheavy element, by anion-exchange
experiments in HF and HF/HNO3 mixture
solutions. Although the distribution coefficient(Kd) of Db showed the trend of Ta>Nb>Db>Pa in
the group-5 homologs and pseudo-homolog
elements, its chemical species has not beenclarified. In this work, for identification offluoride species of Db, we performed
anion-exchange experiments of Nb, Ta, and Db
in HF/1.0 M HNO3 mixture solutions by using an
automated rapid chemistry apparatus, ARCA.
88g
Nb, 170Ta, and 262Db were produced in thenat
Ge(19F, xn)88gNb, natGd(19F, xn)170Ta, and248
Cm(19F, 5n) 262Db reactions, respectively, at the
RIKEN K70 AVF cyclotron. The reaction
products, transported by a He/KCl gas-jet system,
were dissolved with HF/1.0 M HNO3 mixture
solution at a flow rate of 1.0 mL min-1. For Db,
after elution of HF/1.0 M HNO3 from theanion-exchange column filled with CA08Y resin,the 2nd stripping solution was fed into the column.
:H PHDVXUHG Į-particles for dried samples,
which were prepared from the above-mentioned
HOXHQWV E\ XVLQJ DQ DXWRPDWHG UDSLG Į6)
detection system.
We evaluated the Kd values of Nb and Ta
obtained in the online column experiment. The
results were almost the same as those of the batch
experiment performed previously. In the Db
experiments, we repeated anion exchange
experiments 350 times and observed alpha eventsof 262Db in the 1st and 2nd fractions, respectively.

It is difficult to obtain the distribution data atequilibrium for the short-lived 261Rf in 2-phase
distribution experiments, but such data arenecessary to discuss in detail the chemical
properties of Rf. To obtain distribution
coefficients (Kd) of Rf, a batch-type solid-liquid
extraction apparatus called AMBER wasdeveloped. We have been studying the sulfate
complexation of Rf by an anion-exchange
method. In our previous study, we successfully
obtained the Kd value of Rf at 0.11 M H2SO4. The
obtained Kd value of Rf is low (Kd < 15 mL gí1),
probability indicating that Rf does not form
anionic species, or counter ions of HSO4í andSO4í are preferentially adsorbed on theanion-exchange resin. In this study, we
performed the anion-exchange experiment of Rf
at several H2SO4 concentrations including thelower concentration of 0.060 M H2SO4.
We performed anion-exchange experiments of261
Rf and 169Hf by using AMBER. 261Rf and 169Hf
were produced in the 248Cm(18O,xn)261Rf andnat
Gd(18O,xn)169Hf reactions, respectively, byusing the AVF cyclotron at RIKEN. The products
were transported from the target chamber to
AMBER with a He/KCl gas-jet system. After theanion exchange with AMBER, radioactivities of261
Rf and 169Hf were investigated by using an
automated rapid Į6) GHWHFWLRQ V\VWHP DQG *H
detectors, respectively.
We obtained the Kd value of Rf in 0.060–0.46 M
H2SO4. The Kd values of Rf are low in all the
H2SO4 concentrations studied, suggesting that Rf
does not form anionic species and the sulfate
complexation strength of Rf is lower than thoseof Zr and Hf.

2A04 Anion exchange of Rf in H2SO4: H2SO4
concentration dependence of distribution
coefficients
YOKOKITA,
T.1,
KASAMATSU,
Y.2,
WATANABE, E.2, KOMORI, Y.1, SHIGEKAWA,
Y.1, MORI, D.1, WANG, Y.1, NINOMIYA, H.2,
HAYAMI, S.2, TONAI, K.2, GHOSH, K.1,
SHINOHARA, A.2, HABA, H.1(1RIKEN, 2Osaka Univ.)

2A05 The method to reduce “particle mixing”
under automated particle measurement(APM) condition of LG-SIMS
TOMITA, R., ESAKA, F., YOMOGIDA, T.,
MIYAMOTO, Y.
(JAEA)
Large Geometry Secondary Ion Mass
Spectrometry (LG-SIMS) is one of the strongest
tools for analyzing isotope ratios of micron sizeduranium particle. LG-SIMS has high spatial
resolution of less than 1 µm with microprobe
mode. However, this capability is bit less underautomated particle measurement (APM)
condition. If two or more particles are located in aquite narrow area, APM may detect the cluster as
one particle. This “particle mixing” effect shows
analytical results including false isotope ratios. In
order to investigate how often particle mixing
happens and how to solve this problem, we
implemented APM to mixed uranium particle
standard (U010, U100, U350 and U850) and try
to apply particle manipulation with APM. In our
experiment, each area (350 × 350 µm2) was
scanned with an O2+ primary beam with a currentof 1.5 nA for 9 sec. Then, secondary ion images
were recorded for circular area with a radius of
8500 µm on the center of a sample planchet. The
APM detected 5976 particles, and 1943 particles(32%) in them showed false isotope ratios. In
addition to “particle mixing”, U850 cluster was
shifted down to around 75% enrichment. The
sample showed too high hydride rate, so that235
UH interfered 236U. This interference caused
false 236U abundance and lead to false 235U
abundance. To solve these problems, 50-80
particles were manipulated randomly fromanother mixed standards planchet and analyzed
them by APM.
2A06 An examination of environmental
sample analyses for safeguard using
multi-collector ICP-MS
TOMITA, J., TOMITA, R., SUZUKI, D.,
YASUDA, K., MIYAMOTO, Y.
(Japan Atomic Energy Agency)
Multi-collector type ICP-MS (MC-ICP-MS) is a
powerful tool to precisely and accurately analyze
the amount and isotopic ratios of ultra-trace (fg to
ng level) U and Pu in an IAEA environmental
safeguards sample. Clean Laboratory for
Environmental Analysis and Research (CLEAR)
of JAEA installed a MC-ICP-MS instrument, andis preparing the measurement protocol for
uranium and plutonium isotope ratios. In thispresentation, the accurate measuring method of

uranium isotope ratios with high precision using
MC-ICP-MS was examined.
Quantitative contribution of tailing and hydrationof major isotopes (235U, 238U) to minor isotopes(234U, 236U) were evaluated by measuring
uranium certified reference materials (BNL CRM
U015, U0002). The results measured the U0002
solution showed that the ratio of 238U tailing at
236
U to 238U+ was 10-8. Relative standard
deviations of uranium isotope ratios of U015
were measured to optimize the number of cycles
for measuring a sample. The significant
differences among the mean values of 5, 10 and
20 cycles were not found for 234U/238U, 235U/238U
and 236U/238U isotopic ratios. The frequency forthe correction of mass bias and ion counter
efficiencies for accurate measurements of U
isotopic ratios will be discussed in thepresentation.
2A07 Composition of Slags Produced from
Domestic Waste Determined by Photon
Activation Analysis 2
AKIYAMA, K.1, SAITO, R.1, SUWA, T.1, ALI,
A.1, KIKUNAGA, H.2, KUBUKI, S.1(1Grad. School Sci., Tokyo Metropolitan Univ.,
2
ELPH, Tohoku Univ.)
Mineral resource including rare metals are
considered to be an extremely important resourcethat support many industrial fields in the world. It
is well known that various mineral resources areimported because of the poor resource in ourcountry. On the other hands, it is also well known
that the waste from consumer electronics andmobile phone that we emitted contain a great dealof mineral resources and is called “Urban Mine”.
Recently, many researchers and engineers have
tried to recycle mineral resources from suchurban mines for reducing the amount of theimported rare metals. As a part of such a resource
recycling research, we have studied thecomposition of a domestic waste slag, which iskind of an artificial sand produced fromincineration ash of domestic waste in Tokyo, inorder to assess the potential for the resource
recycling from it.

In this study, the composition of the slag in
Sagamihara City, Kanagawa Prefecture, which
produces domestic waste slag as in Tokyo, wasstudied by using the photon activation analysis,
and its results were compared with those inTokyo.
2A08 Variability in Composition of Domestic
Waste Slag and Separation of Valuable Metal
Elements from them
SAITOU, R.1, AKIYAMA, K.1, ALI, A.S.A.1,
KHAN, I.1, KIKUNAGA, H.2, KUBUKI, S.1(1Grad. School Sci., Tokyo Metropolitan Univ.,
2
ELPH, Tohoku Univ.)
Domestic waste slag is a kind of artificial sandproduced by the melt/quenching method of theincineration ash from the combustible waste. It
has been considered that these slag containseveral kinds of valuable metal elements, such as
Cu and Au, and are important materials from theview point of resource recycling. In our previous
work, we reported the composition of monthly
provided slag from January 2018 to December
2018 by photon activation analysis (PAA). In thiswork, we will report the composition of monthly
provided slag in 2019 by PAA and XRF and also,
we discuss about the possibility of component
separation by magnets.
Monthly collected domestic waste slag (Slag1901-1912) at the Tamagawa Incineration Plant
in 2019 was pulverized and wrapped by high pure
Al foil. These slag samples were irradiated with
20 MeV bremsstrahlung for 6 hours in ELPH at
Tohoku University. After the irradiation, J rayemitted from slag samples were determined by ahigh purity Ge semiconductor detector.
As results, the averaged main composition of slag
in 2019 was found to be almost same as that in
2018.
2A09 Activation analysis of shells of Japanesebasket clams (shijimi)
REZA, Md.S., OURA, Y.
(Tokyo Metropolitan Univ.)
Shells of Japanese basket clams (shijimi) living
in brackish lakes were analyzed by instrumental

photon activation analysis (IPAA) andinstrumental neutron activation analysis (INAA).
A single comparator method was applied in IPAA.
About 10 elements were detected by INAA and
IPAA each. As, C, Rb, Y, and Zr were detected byonly IPAA. Elemental contents in 2 shells of anindividual were almost consistent. Among
different individuals most of elemental contents
also consistent, but especially, some individuals
have higher content for Mn. Shells from four
different locations were also analyzed. Major andminor elements were contained in similar
concentration even for different locations. But forsome trace elements, especially Mn, theconcentrations varied among production areas.
Nocorrelations
betweenelemental
concentrations and locations were observed.
2A10 Determination of elements in sedimentsof lakes in Gunma prefecture by neutron
activation analysis
OKADA, Y.1, KUMAGAI, N.1, WATANABE,
S.2, NOHARA, S.3(1Tokyo City Univ., 2Gunma Prefectural Fisheries
Experiment Station, 3National Institute forEnvironmental Studies)
In Akagi-Onuma, Gunma Prefecture, theconcentration of radioactive cesium in the lakewater continues to decline gradually. In order toinvestigate the sediment characteristics of Akagi
Onuma, the elements in the sediments of 11 lakes
in Gunma prefecture were analyzed by neutron
activation analysis. The sediment (0 mm to 40
mm depth) was irradiated with KUR for 30
seconds and 1 hour to quantify the elements. The
quantification was performed by the comparison
method using rock standard substance JLk1-1. As
a result, 25 elements were quantified. All lake
sediments contained more than 20% Si and a
few% Al and Fe. Stable Cs content is 1.4 µg / g in
Lake Haruna, 2.8 µg / g in Lake Narusawa andUsui, 2.9 µg / g in Lake Baraki, 3.5 µg / g in
Condonuma and 4.3 µg / g in Nyu. , 5.1 µg /Akagi Onuma / g, Lake Okutone 7.2 µg / g,
Kanako 8.0 µg / g, Lake Kusagi 10 µg / g, Lake
Umeda 15 µg / g. The elements having acorrelation coefficient with Cs of 0.8 or more
were Ba, Sm, Ce, Eu, and Ta.
2A11 Precise determination of Ir in highpurity reagent by neutron activation analysis
MIURA, T.1, IINUMA, Y.2, SEKIMOTO, S.2(1NMIJ/AIST., 2KURNS)
Instrumental neutron activation analysis withinternal standard correction was applied for
precise determine of mg quantities of Ir in
high-purity IrBr4. A known amount of Au
standard solution was used as an internal standard
to compensate for inhomogeneity of the neutron
flux through an irradiation capsule and forneutron self-shielding. The linearity of thecalibration curves of Ir was improved by using aninternal standard. The relative expanded
uncertainty (k = 2) associated with thedetermined value was 0.86%, which allowed themg quantities of iridium to be precisely
determined.
2B01 Dynamics of polaronic local structuresin a colossal-magnetoresistive manganite
La0.7Ca0.3MnO3SATO, W.1, KOMATSUDA, S.2, SHIMIZU, H.1,
MORIICHI, R.1, ABE, S.1, WATANABE, S.1,
KOMATSU, S.1, TERAI, T.3, KAWATA, S.4,
OHKUBO, Y.5(1Inst. Sci. Eng., Kanazawa Univ., 2Inst. Human
Soc. Sci., Kanazawa Univ., 3Grad. Sch. Eng.,
Osaka Univ., 4Dept. Chem. Fukuoka Univ., 5Inst.
Integ. Radiat. Nucl. Sci., Kyoto Univ.)
The magnetic hyperfine field and electric field
gradients at a radioactive impurity probe of111&G ĸ111mCd) occupying the La/Ca A site in acolossal-magnetoresistive perovskite manganaite
La0.7Ca0.3MnO3 (TC ~ 250 K) were measured bymeans of time–differential perturbed angularcorrelation (TDPAC) spectroscopy.
In theparamagnetic–insulator
phase
at
room
111
111m
temperature, the&G ĸ Cd) probes are
distributed in two different environments(distorted and less distorted sites) at the fractionof 7:3; whereas in the ferromagnetic–metal phase
below TC, the oscillatory structure of the distorted

component vanishes from the TDPAC function.
The vanishing of the oscillation is ascribable todynamic motion of polarons dragged byconduction electrons originating from eg
electrons of Mn3+. At liquid helium temperature,
the dynamic motion freezes, leaving averaged
quadrupole frequency reflecting local distortion.
The dynamic motion and freezing of local
structuresassociatedwiththecolossal-magnetoresistance phase transition to
the ferromagnetic phase is discussed on the basisof temperature-dependent electromagnetic fields
at the probe nuclei of the A site ions.
2B02 Observation of Dynamic Behavior andSite Occupation of 111&G ĸ111In) Probe Dopedin SrTiO3
KOMATSUDA, S.1, SATO, W.2, OHKUBO, Y.3(1Inst. Hum. Soc. Sci., Kanazawa Univ., 2Inst. Sci.
Eng., Kanazawa Univ., 3KURNS)
Strontium titanate (SrTiO3) is a cubic perovskite
oxide. SrTiO3 doped with metal ions as
impurities exhibits a wide variety of electronic
properties.
Especially, SrTiO3 doped withtrivalent metal ions at Ti4+ site has been attracted
much attention because of their excellent
photocatalytic activity. For a practical use of
SrTiO3, it is necessary to obtain more
microscopic information on the impurity site.
Therefore, we investigated the local structures at
the In3+ site in SrTiO3 by means of thetime-differential perturbed angular correlation(TDPAC) method using the 111&G ĸ111In) probe.
The
TDPAC
spectrumof 111&G ĸ111In)
embedded in SrTiO3 can be reproduced by a fit
with three unique quadrupole frequencies. As forone of these components, the quadrupole
frequency shows a zero. On the basis of the cubic
structureof
SrTiO3,
thissignifies
the 111&G ĸ111In) probes occupy defect-freesubstitutional Sr or Ti sites in SrTiO3. The
remaining two components shows two
well-defined EFG values. These non-zerofrequencies imply that defects were associatedwith 111In probes. In the session, based on thefurther investigation of TDPAC spectrafor 111&G ĸ111In) embedded in SrTiO3 measured
at various temperature (400~1100 K), we discuss
the defect structure of local surroundings of In
ions doped in SrTiO3.
2B03 Effect of thermal diffusion of In
impurities in ZnO on its electricalconductivity
TAKATA, M.1, SHIMIZU, H.1, KOMATSUDA,
S.2, OHKUBO, Y.3, SATO, W.1,4(1Grad. Sch. Nat. Sci. Tech., Kanazawa Univ.,
2Inst. Human Soc. Sci., Kanazawa Univ., 3Inst.
Integ. Radiat. Nucl. Sci., Kyoto Univ., 4Inst. Sci.
Eng., Kanazawa Univ.)
Zinc oxide (ZnO) is known as an intrinsic n-typesemiconductor, and its physical and chemical
properties are extensively studied aiming toenhance n-type conductivity by introducing
impurity donors. Thus, control of the state of
impurities is an urgent issue for its application tofunctional materials. In our previous study, we
succeeded in uniformly diffusing 0.5at.% In ionsin ZnO. In the next stage, we directed our interest
to thorough understanding of the effect ofassociation-dissociation behavior of impurity In
ions on electrical conductivity. In thispresentation, the effect of thermal diffusion of In
impurities was investigated by means of
perturbed angular correlation spectroscopy withthe 111&G ĸ111In) probe and the electricalconductivity measurements.
2B04 Change in gel fraction of polyethylene
after irradiation: Evaluation by positronannihilation lifetime spectroscopy
KITADA, N.1, OKA, T.2, OKUTSU, K.1,
YAMASHITA, T.3,1, KINO, Y.1, SEKINE, T.3,1(1Department of Chemistry, Tohoku Univ., 2Japan
Atomic Energy Agency, 3Institute for Excellencein Higher Education, Tohoku Univ.)
Polyethylene (PE) is widely used for insulators innuclear power plants and accelerators. Duringlong-term usage, since PE is subjected toradiation environments, and is degraded byoxidation. The examination of the degradation of
PE is important for the safety of these facilities.

In this work, we evaluated the degradation of the
gamma-ray irradiated PE with positronannihilation lifetime spectroscopy (PALS). In
order to show the effectiveness of the PALS, we
compared with gel fraction measurement. PALS
is known as a powerful tool to investigate
nanostructure without destroying the sample.
Ultra-high molecular weight PE (UHMWPE)
with a molecular weight of 1 million or more,high-density PE (HDPE) with a molecular weightof about 300,000, and low-density PE (LDPE)
having branched molecular chains, were
irradiated with gamma-ray. The samples were
irradiated under vacuum and room temperature
condition and then exposed to the air.
The results of PALS showed that the formation
probability of spin-triplet positron-electron
bound state, ortho-positronium (o-Ps), decreased
after the irradiation as the air exposure timeincreased. The gel fraction also decreased as the
air exposure time increased. We found acorrelation between the gel fraction (0-100% for
HDPE and LDPE, and 80-100% for UHMWPE),
and the formation probability of o-Ps. The
relation between the change of the gel fraction
and that of the formation probability of o-Ps was
explained by the oxidation of the sample. The
results suggest that PALS can be a nondestructive
method for analyzing radiation degradation ofpolymers as an alternative to gel fraction.
2B05 Observation of oxidation reaction of
metal iron by muonic X-ray measurement
KAJINO, M.1, NINOMIYA, K.1, KUDO, T.1,
TERADA, K.1, INAGAKI, M.2, SATO, A.1,
TOMONO, D.3, KAWASHIMA, Y.3, SAKAI, Y.4,
TAKAYAMA, T.4, SHINOHARA, A.1(1Osaka Univ., 2Kyoto Univ., 3RCNP, 4Daido
Univ.)
An atomic system having one negatively charged
muon instead of an electron is called a muonic
atom. After formation of a muonic atom,
high-energy muonic X-rays are emitted in thede-excitation process of the atomic muon.
Recently, non-destructive elemental analysis
method by muonic X-ray measurement has been

developed. In the formation process of themuonic atom, chemical environmental effects on
muonic X-ray intensities have been known. For
example, intensity ratio of muonic KĮ X-ray to Kȕ
X-ray is different by chemical species of muon
capturing atom. In this work, we performed
feasibility study on observing oxidation reaction
tracking by muonic X-ray measurement.
Muon irradiation experiments were conducted at
RCNP-MuSIC. We prepared a packed ironpowder included in disposable heat pad for muon
irradiation sample. Muonic X-rays from thesample were continuously measured during its
oxidation by HPGe detectors. Muonic KĮ X-ray
intensity ratio from iron became large with time
passing. The time dependence on muonic KĮ
X-ray intensity ratio means progress of oxidation
process of the sample. Considering the sample as
the binary system of iron oxide and metal iron,
this time dependence of muonic X-ray intensity
was consistent with the chemical species change
revealed by Mossbauer spectroscopy. In
summary, we successfully demonstrated thechemical reaction tracking by muonic X-ray
measurement.
2B06 Development of non-destructive 3D
image method using muon beams with CdTe
Double-sided Strip Detector.
CHIU, I-H.1, KAJINO, M.1, SHINOHARA, A.1,
NINOMIYA,
K.1,
TAKEDA,
S.2,
2
2
KATSURAGAWA, M. , TOMARU, R. , YABU,
G.2, NAGASAWA, S.2, TAKAHASHI, T.2,
WATANABE, S.3(Osaka University1, Kavli IPMU2, JAXA3)
Analyzing the internal elements without
destroying the sample is an important target forvaluable materials such as the archaeologicalobjects, the meteorites. The non-destructive
analysis has been achieved using muon-induced
characteristic X-rays with the high-intensity
negative muon beam. Since the energy of muon
characteristic X-rays is 200 times higher than thatof electron characteristic X-rays, it provides a
new method to analyze the internal elements anddepth of substances by the non-destructive

elemental
analysis.
Furthermore,atwo-dimensional cadmium-telluride detector,
which is used for space observation experiments,
is possible to be used in the image reproduction
with excellent positional resolution. The
two-dimensional image has been developing
using muon characteristic X-rays so far. A new
method for the non-destructive three-dimensional
image with muon characteristic X-rays is
expected. Moreover, we use the Geant4 program
to evaluate the validity of the experimental data.
Geant4 program is commonly used in particle
physics and medicine and astronomy. In thispresentation, we will show the construction of a
two-dimensional cadmium telluride detector andthe analysis method of the image reproduction. In
addition, the non-destructive 3D imaging method
using muon characteristic X-rays will be
discussed, too.
2B07 Residential Site of Impurity In Atoms in
Fe3O4 Observed by Means of Positron
Annihilation Spectroscopies and Mössbauer
Spectroscopy
ISHIZAKI, R.1, SHIMIZU, H.1, SATO, W.1,2(1Grad. Sch. Nat. Sci. Tech., Kanazawa Univ.,
2Inst. Sci. Eng., Kanazawa Univ.),URQ ჟრ  R[LGH )H3O4) with an inverse spinel
structure has many vacancies at the sites where
Fe atoms can occupy; it is expected thatenhancement of magnetism and electricalconductivity is attained by introducing impurity
ions to the vacant sites. When a trace amount ofindium (In) was introduced as impurities in Fe3O4
in our previous work, it was found that In
occupies the tetrahedral site at room temperature.
Our next interest is in the directed to residentialsites of a macroscopic amount of impurity In
introduced. In this study, we investigated thedependence of In concentration introduced in
Fe3O4 on the local structure in Fe3O4 by means ofpositron annihilation lifetime spectroscopy(PALS), Doppler broadening spectroscopy(DBS) and 57Fe Mössbauer Spectroscopy. PALS
and DBS measurements show that In having alarge ionic radius substitutes for Fe, squeezing

nearby local structures to cause the reduction of
the vacancy volume. The results of Mössbauer
measurements revealed that hyperfine fields at
the Fe site and the residential fraction of Fe in A
and B sites change depending on the Inconcentration. These observations suggest that In
introduced in Fe3O4 replaces Fe ions at the A site.
2B08 Mössbauer spectroscopy of Fe-Ag type
Hofmann-type complex
KITASE, K., TAKAHASHI, M., KITAZAWA, T.
(Toho Univ.)
Hofmann-type complex is a coordination
polymer with a center metal ion such as Fe, Ni or
Cd, bridging ligand that is liner dicyanide
complex or square planer tetracyanide complex,
and pyridine-type ligands. The spin-crossover(SCO) phenomenon is a reversible transition
between high-spin and low-spin state. 57Fe
Mössbauer spectroscopy is a useful tool forinvestigations in Fe-based SCO phenomenon due
to dependence of valences, spin states, andenvironments of Fe site.
In this research, we synthesized a Hofmann-typecomplex Fe(4-methylpyrimidine)2[Ag(CN)2]2.
This complex is synthesized by direct method
using Mohr’s salt, K[Ag(CN)2] and ligand. The
magnetic measurement shows one-step spintransition between 140 and 130 K in this complex.
The single crystal data shows this complex
belongs to the Hofmann-type structure. weak Agʊ 1 LQWHUDFWLRQ H[LVWV 57Fe Mössbauer
spectroscopy of this complex reveals spintransition occurs 140 and 130 K. However, nohysteresis is observed in 57Fe Mössbauer data
while a relatively large hysteresis is observed in
SQUID data. The differences between
Mossbauer and SQUID data might be explainedby different scan rates. We are set to measuremagnetic susceptibility to make sure this
explanation.
2B09 Mössbauer spectroscopic studies ofNa2Ru1-xFexO3 of sodium-ion battery electrode
HAMANO, K.1, KOBAYASHI, Y.1,2, HABA, H.2,
UENO, H.2

(1Univ. Electo-Comm., 2Nishina Center, RIKEN)
Sodium-ion battery has attracted attention as thenext generation of battery after Li-ion one forlarge-scale applications owing to the abundance
and low cost of sodium. Among Na-excess metaloxides, Na2RuO3 is expected to be the leading
cathode material. Mössbauer spectroscopy is a
powerful tool to understand the oxidation statesof Ru ions. However, the measurements of 99Ru
Mössbauer spectra can only be performed at low
temperatures because the Mössbauer transitionenergy is relatively high (EJ= 89.8 keV). A
57
Fe-doped sample of Na2Ru1-xFexO3 was
prepared to estimate the temperature dependenceof the oxidation states of Ru sites by 57Fe
Mössbauer spectroscopy. In this study, wedemonstrate the oxidation states and coordination
environments of Ru ions in Na2RuO3 andNa2Ru1-xFexO3
after
repeatingthecharge/discharge processes by means of 99Ru and57
Fe Mössbauer spectroscopy, XRD, andelectrochemicalmeasurements.
The
Na2Ru0.99Fe0.01O3 sample was confirmed to be ina single phase by XRD. The 99Ru Mössbauer
spectrum of Na2Ru0.99Fe0.01O3 after charging
showed that Ru ions were oxidized from Ru4+
before charging to Ru5+. We will discuss that thevalence states and structural changes of Ru ionsdue to charging-induced Na+ deficiencies fromthe results of 57Fe Mössbauer spectroscopy.
2B10 In-beam Mössbauer spectra of 57Fe
after 57Mn implantation in alkali halides
KIJI, M.1, HAMANO, K.1, SATO, M.1,
TAKAHAMA, N.1, KOBAYASHI, Y.1,2, KUBO,
M.K.3, YAMADA, Y.4, MIHARA, M.5, SATO,
W.6, NAGATOMO, T.2, OKAZAWA, A.7, SATO,
S.8, KITAGAWA, A.8(1Univ. Electro-Commun., 2RIKEN Nishina
Center, 3Int. Christ. Univ., 4Tokyo Univ. Sci.,
5
Osaka Univ., 6Kanazawa Univ., 7Nihon Univ.,
8
National Institute of Radiological Science)
In-beam Mössbauer spectroscopy using ashort-lived 57Mn (T1/2 = 1.45 m) implantation is a
powerful tool to study the characterization of
localized 57Fe atoms in solids. Alkali halide ismainly used as an optical material. Since iron ismixed as an impurity in the optical material
during the manufacturing process, there is aproblem that the visible light transmittancebecomes lowered. In order to use an opticalmaterial with high efficiency, it is necessary tohave high purity. However, it is very difficult toquantify a trace amount of impurities, and it is notknown how it behaves. Therefore, we conducteda study for understanding the occupied positionand chemical state of 57Fe in alkali halides byusing in-beam Mössbauer spectroscopy and DFT
calculation. All the obtained Mössbauer spectra
could be analyzed with three components, one
singlet and two doublets, respectively. From theobtained Mössbauer parameters and DFT
calculations, the singlet and doublets wereassigned to the substituting positions of thecations without and with defects, respectively. In
addition, we will discuss the characteristic
behavior of Fe atoms in LiF, NaF, NaCl, and KCl,
which have NaCl-type crystal structures.
2B11 Identification of Co sites in spinel ferriteby means of 57Co emission Mössbauer
spectroscopy
SAKAGUCHI, M.1, TAKENAKA, S.1, SATO,
W.1,2(1Grad. Sch. Nat. Sci. Tech., Kanazawa Univ.,
2Inst. Sci. Eng., Kanazawa Univ.)
Cobalt ferrite (CoxFe3–xO4) is a magnetic material
that has been extensively studied for a wide
application in various fields of industry. In spiteof the expectation to application, however, evencation distribution is still unknown. Thus, weprepared 57Co-doped CoFe2O4 and appliedemissionandtransmission
Mössbauer
57
57
spectroscopy with the Fe( ˣ Co) probe toclarify how cations are distributed in thecompound with a spinel structure. It was foundthat the 57Fe transmission and 57Co emission
spectra of CoFe2O4 obtained at 7-295 K consistof three components: two components are
assigned to the B site and the other to the A site.
This result indicates that part of the A sites areoccupied by Co ions. On the basis of a modelof probability distribution, it was estimatedthat 7.5±0.5% of the A sites are occupied by
Co ions. In the session, temperature
variation of the spectra are discussed inrelation to the 57Co emission Mössbauer
spectra for Fe3O4 based on the Mössbauer
parameters obtained.
3A01 Production and chemical purification of
Ag-111 toward nuclear medical application
OOE, K.1,2, WATABE, T.1,2, SHIRAKAMI, Y.2,
MORI, D.3, YOKOKITA, T.3, KOMORI, Y.3,
HABA, H.3, HATAZAWA, J.2,4(1Osaka Univ. Grad. Med., 2IRS, Osaka Univ.,
3
RIKEN, 4RCNP, Osaka Univ.)
Toward domestic production of therapeutic
radionuclides using accelerators, production
cross sections and chemical purification methodof a ȕ-particle emitter, 111Ag, were investigated. A
stack of metallic natPd target foils was irradiatedwith a 24-MeV deuteron beam from the RIKEN
K70 AVF Cyclotron. The irradiated natPd targets
ZHUH VXEMHFWHG WR Ȗ-ray spectrometry with a Ge
detector. The 245-NH9ȖSHDNRI 111Ag was used
for determination of the cross section of thenatPd(d,x)111Ag reactions. In the chemical
separation of 111Ag from the natPd target, theirradiated natPd target was dissolved in mixed
HNO3 and HCl solution. After evaporation todryness, the residue was dissolved in 1 M HNO3
solution and then fed into an anion exchange
column. The 111Ag was eluted by 1 M HNO3
solution. The maximum cross section of 111Ag
was approximately 40 mb at the deuteron beamenergy of approximately 9 MeV. The elution of111
Ag from an anion exchange column using 1 M
HNO3 was completed before the start of elutionof natPd. The recovery of 111Ag was more than
99%. The production and separation methods of111
Ag from the metallic Pd were established.
These results lead to preclinical studies oftherapeutic effects with 111Ag.
3A02 Development of new diagnostic method
by ETCC imaging using Tc-95 and Tc-95

HATSUKAWA, Y.1, KABUKI, S.2, KUSHIDA,
J.3, IKUTA, A.3, KIMURA, H.4, ASAI, M.5,
TSUKADA, K.5(1QST, 2Tokai Univ., Medical school, 3Tokai
Univ., Physics, 4 Kyoto Pharmaceutical Univ.,
5
JAEA)
In this study, we produced Tc isotopes with highenergy gamma emitting for developing ofCompton camera imaging instead of SPECT
measurement with 99mTc. Technetium-99m isused in radioactive diagnostic tests, for example
as a radioactive tracer that a nuclear medical
gamma camera can detect in human body. There
are
at
least
31
commonlyused
99m
radiopharmaceuticals based on Tc for imaging
and functional studies of the brain, myocardium,thyroid, lungs, liver, gallbladder, kidneys,
skeleton, blood, and tumors. Two technetium
isotopes, 95mTc and 96Tc are candidates forCompton camera imaging. The feasibility studyof Compton camera imaging using gamma rays
emitted from 96Tc was carried out. Using the
ETCC (Electron Tracking Compton Camera), we
tried to obtained imaging pictures of the gamma
rays emitted from 96Tc. 96Tc was obtained fromproton irradiation. After chemical purification,
96
TcO4- ions were labeled with DTPA compound.
Then the 96Tc labelled DTPA compound were
injected into a mouse, and imaging picture of themouse was taken by the ETCC imaging method.
Detailed results will be discussed in theconference.
3A03 Imaging the arsenic translocation andaccumulation in arsenic hyperaccumulator
Pteris vittata using Positron Emitting Tracer
Imaging System(PETIS)KOHDA, T.1, QIAN, Z.J.1, CHIEN, M.F.1,
INOUE, C.1, IKEDA, H.2,3, WATABE, H.2,
KIKUNAGA, H.3, SUZUI, N.4, YIN, Y.G.4,
KAWACHI, N.4, KITAJIMA, N.5(1GSES, Tohoku Univ., 2CYRIC, Tohoku Univ.,
3
ELPH, Tohoku Univ., 4QST, 5TDD, Fujita
Corp.)
Arsenic (As) contamination of drinking waterand irrigation water became a serious issue tomillions of people in the world. As remediationin water employs granular metal oxide adsorption
method,ion
exchange,orcoagulation–microfiltration method. The main
disadvantage of these methods is high cost of thearsenic removal. Phytofiltration is an emerging
water treatment technology that uses the plants toremove contaminants from water. Pteris vittata,
the As-hyperaccumulator plant, which thecapability is accumulating large amount of As
into fronds and rhizomes. The mechanism of As
accumulation in this plant is still keeping
unknown. In the present work, we used PETIS(positron-emitting tracer imaging system) to get
the serial noninvasive images and quantitative
characterization of absorption, translocation, andaccumulation of arsenic (As) in Pteris vittata
with positron-emitting 74As-labeled arsenate
tracer. We first recorded the real-time Astranslocation from the medium to the roots andthen to the rhizomes and fronds in Pteris vittata.
We found that not like roots, rhizomes keep the
As level with fronds indicates that rhizomes
control the As translocation to fronds in Pteris
vittata. But non-accumulator Arabidopsis
thaliana hold most of As in roots.
3A04 Protective behavior of tea catechins on
DNA double strand breaks by radiation
WADA, T.1, YAMAZAKI, S.1, KOIKE, A.1,
ASHIZAWA, K.1, ZHAO, M.1, SUN, F.1, OYA,
Y.2
(1Graduate School of Integrated Science andTechnology, Shizuoka Univ., 2Faculty of Science,
Shizuoka Univ.)
The evaluation of radiation effects for humanbody is necessary. Regarding on a safety issue onradiation damages for human being, it isimportant to elucidate the protecting mechanism
for natural antioxidants including vitamin E,
caffeine and catechin from radiations. In thepresent study, DNA double strand breaks on
genome-sized DNA was evaluated quantitatively
under several types of radiation sources and thecharacteristics of radiation damages in different
LET was revealed, and the effect of radiation

protection by tea catechins was also studied as afunction of its concentration. The DNA ofbacteriophage (T4 GT7: 166 kbp) was soaked inasterilized
water
with
EGCg
((-)-epigallocatechin gallate) which is the main
ingredient of a tea catechin and exposed tovarious radiation sources (3H-ȕ UD\ 45Ca-ȕ UD\60
Co-Ȗ UD\  7KH OHQJWK RI '1$ PROHFXOHV ZDV
measured using fluorescence microscope, which
can estimate a number of DSBs quantitatively.
Based on experimental results, the DSBs werereduced by addition of EGCg and a saturation on
the protection in EGCg concentration of 1 µM
was found. As it was reported in previous study
that the concentration of EGCg in blood wasincreased to several µM after ingesting tea extract,
the result suggested that EGCg could protectorganisms from indirect radiation effect.
3A05 Search for an optimized condition of207
Po elimination for the 211Rn/211At generator
systemAOI, K.1, SHIN, Y.1, KAWASAKI, K.1,
MARUYAMA, S.1, WASHIYAMA, K.2,
NISHINAKA, I.3, HABA, H.4, WANG, Y.4,
YOKOYAMA, A.1(1Kanazawa Univ., 2Fukushima Medical Univ.,
3
QST, 4RIKEN)
The astatine-211 nuclide is a prospective
candidate to utilize in targeted alpha therapy. To
extend usable time of 211At of 7.2h half-life, the211
Rn / 211At generator system has been indeveloping. However, 207Po (t1 / 2 = 5.80 h) fromthe decay of 211Rn is also produced as aby-product. It is necessary to separate 211At from
207
Po, since 207Po may damage normal tissue ofhuman body. In this study, an optimal condition
for elimination of 207Po was studied by a cationexchange resin of 0.1, 0.3, 0.5, and 0.7 g, andascorbic acid of 0.1, 0.5, 1, 2, and 3wt%, in
0.01M HCl as eluent. The results demonstrate theabsorption rate of more than 90% of 207Po was
obtained for cation exchange resin. However, therecovery rate of about 94% of 211At from cationexchange resin of 0.5 g in 0.01M HCl was mosthigh for ascorbic acid of 1wt%. As the weight ofresin increased, the recovery rate of 211At
increased, and the absorption rate of 207Po
decreased. Separation factor was 35 for cationexchange resin of 0.5 g with 1wt% ascorbic acidin 0.01M HCl. Thus, this is a suitable condition
for the elimination method of 207Po from 211At.
3A06
Study on solvent extraction andspeciation of astatine species with a thin layer
chromatography
MARUYAMA, S.1, KAWASAKI, K.1, AOI, K.1,
HIGASHI,
M.2,
NISHINAKA,
I.2,
WASHIYAMA, K.3, HABA, H.4, YOKOYAMA,
A.5(1Kanazawa Univ., 2QST, 3Fukushima Med.
Univ., 4RIKEN),QUHFHQW\HDUVVWXGLHVRQĮ-ray internal therapy
XVLQJĮ-ray emitting nuclides have been actively
conducted, and astatine-211(211At) has been
attracting much attention from the viewpoints ofavailability of nuclides and outpatient treatment.
Astatine is a radioactive element that has only
short-lived radionuclides, and various chemical
species of At have been reported in relation to its
chemical behaviors that were not well clarified.
We obtained the nuclide from the 209%L ĮQ 211At
reaction to study the distribution behavior insolvent extraction in relation to At species. We
performed solvent extraction in HCl/DIPE
system and speciation of At species with a thinlayer chromatography (TLC) followed by Image
Plate (IP) measurement on its radioactivity toidentify the chemical species of At in a solution
and to determine its distribution.
3A07 Synthesis of astatin-211 labeled gold
nanoparticles and evaluation of anti-tumor
effectHUANG, X.1, KATO, H.2, KADONAGA, Y.3,
SHIMOYAMA, A.1, KABAYAMA, K.1, OOE,
K.2, TOYOSHIMA, A.3, SHINOHARA, A.1,
FUKASE, K.1(1Graduate School of Science, Osaka Univ.,
2
Graduate School of Medicine, Osaka Univ.,
3
Institute for Radiation Sciences, Osaka Univ.)

0XFKDWWHQWLRQKDVEHHQGUDZQWRWKHĮ-emission
radiotherapy with regard to its potential cancer
therapeutic efficacy. Astatin-211 (211At), with acomparatively short half-life of 7.2 h, is able toemit alpha particles within a few cell diameterswith high energy, which can damage cancer cells
in a relatively high biological effectiveness. 211At
has similar characteristics to the iodine, which
can rapidly diffuse throughout the body andaccumulate in thyroid gland. Since 211At has highaffinity to gold, we planned to develop a cancer
treatment by direct injection of 211At-labeled gold
nanoparticles (AuNP) to cancer cells. Here, we
synthesized different sizes of poly(ethylene
glycol) methyl ether thiol (mPEG-SH) modified
AuNP and performed astatination (211At) of
pegylated AuNP (AuNP-S-mPEG). Furthermore,anti-tumor effect of the 211At-AuNP-S-mPEG
were evaluated by using rat xenograft model (C6glioma). In the results, all 13 nm-120 nm of
AuNP-S-mPEG were quantitively assassinatedby simple mixing with 211At solution. In vivo
studiesrevealed
that
the
30
nm
211
At-AuNP-S-mPEG was diffused more
efficiently in tumor tissue without leaking toblood vessel and has significant anti-tumor effect,
whereas the effect of 120 nm size was weaker.
The results may help to optimize the design oftargeted alpha therapy drugs, which are suitablefor intratumorally injection.
3A08 Analytical method for radioactivity andchemical forms of 211AtSEGAWA, M.1, MAEDA, M.1, TOH, Y.1,
NISHINAKA, I.2, WATANABE, S.2, ISHIOKA,
N.2(1Japan Atomic Energy Agency, 2National
Institute for Quantum and Radiological Scienceand Technology)
211
At is artificially produced for medical purposes.
To prevent severe loss of short-lived 211At, a rapid
method analyzing both the radioactivity and all
chemical forms was required for related
researches. We propose a new method by means
RI DQ Į-scintillation-camera system comprisingofthin-layer
chromatographyandahigh-sensitive CCD camera. Our previous
research verified the performance of the system
for low-radioactivity 211At experimentally. In thisstudy, the performance of the system and its
capability for high radioactive 211At are reported.
3A09 Preparation of Pure Sodium Astatide,[211At]NaAt, for Nuclear Medicine Application
SHIRAKAMI, Y., OOE, K., KANEDA, K.,
TERAMOTO, T., WATABE, T., TOYOSHIMA,
A., SHINOHARA, A., HATAZAWA, J.
(Osaka Univ.)
Sodium astatide, [211At]NaAt, is expected to be agood agent for the treatment of patients withthyroid cancer, although it has not yet been usedin clinics. We tried to elucidated chemical
properties of the aqueous solution of 211At after
addition of ascorbic acid.
211
At was produced through the 209Bi(Į,2n)211At
reaction. Dry-distillated 211At was collected anddissolved in distillated water (211At bulk solution).
Into the bulk solution, ascorbic acid and sodiumhydrogen carbonate were added and stand for 1hr
at room temperature. The solutions wereanalyzed by thin layer chromatography (TLC)
and high performance liquid chromatography(HLPC).
TLC profiles suggested that the 211At bulk
solution composed of several 211At labeled
species which might be attributable tocompounds of At[I] and At[III] oxidation states.
After addition of ascorbic acid in the bulk
solution, the radioactive species were converged
on a single compound. The compound wasestimated to be [211At]-NaAt.
We demonstrated a method for the preparation ofpure sodium astatide, [211At]NaAt, for thetreatment of patients with thyroid cancer.
3A10 Investigation of drug for 211At-labeled
nuclear medicine targeting to cancer specificamino acid transporter
KANEDA-NAKASHIMA, K.1,2, SHIRAKAMI,
Y.1,3, OOE, K.1,4, TERAMOTO, T.1, WATABE,
T.1,4, SHIMOYAMA, A.1,2, MANABE, Y.1,2,

KABAYAMA, K.1,2, TOYOSHIMA, A.1,2,3,
FUKASE, K.1,2, SHINOHARA, A.1,2(1Osaka Univ., 2Toyonaka College)
Targeted alpha therapy (TAT) is receiving muchattention in the field of “theranostics” because of
its high cytotoxic effect to the targeting cancer.
However, physiological uptakes in non-targetedorgans are also observed in the TAT, which mightlead to the severe side effects. We should
consider about both maximizing the treatment
effect in the tumor and minimizing the side
effects in the organs at risk. From this viewpoint,
decision of targeting molecule was mostimportant.
We selected LAT1 as molecular target. LAT1 is
one of the amino acid transporters, which has
highly specificity to cancer tissues. We
developed next-generation internal radiotherapy
using chemicals targeting LAT1. First, we
synthesized large neutral amino acid derivative
labeled with 211At. 211At was produced by thecyclotron, and then quickly purified and labeled.
Next, we performed its cytotoxicity evaluation
using some cancer cell lines. As a result, cell
death and specificity were confirmed. We also
confirmed the specificity in vivo and found theanti-cancer effects in vivo study. In the immediate
future, we will examine that the effects of211
At-labeled amino acid derivative using several
kinds of tumor-bearing models.
3A11 Preparation and stability evaluation of
Į-emitter 211At-labeled iminobiotin
WASHIYAMA, K., AOKI, M., TATSUMI, T.,
YAMATSUGU,K.,
SUGIYAMA,A.,NISHIJIMA, K., JOHO, T., GAO, H., ZHAO, S.,
KANAI, M., KODAMA, T., TAKAHASHI, K.
(1Advanced Clin. Res Center, Fukushima Med.
Univ., 2Grad. Sch. Pharm. Sci., Univ. Tokyo, 3Isot.
Sci. Center, Univ. Tokyo, 4 Res. Center Advanced
Sci. Tech., Univ. Tokyo)
By separating the role of antibody andradioligand, pretargeting radioimmunotherapy
increases the absorbed dose to the tumor while
reducing the side effects on normal tissues. We
have developed a pretargeting system using amutated low immunogenic streptavidin called as
Cupid, which can be fused to four scFv of mAb,
and a bis-iminobiotin compound Psyche thatspecifically binds to Cupid. The alpha emitter,
211
At, is expected to be loaded into Psyche as it
irradiates tumors with high-energy radiation witha short-range. The purpose of this study was tooptimize the labeling of 211At to several Psyche
compounds (Psyche-B, -J, -N, and -P) andevaluate its stability in PBS and mouse plasma.
Organotin precursors of Psyches which modified
its structure on Cupid binding site, weresynthesized. 211At was produced using MP-30
cyclotron at Fukushima Medical University andseparated by dry distillation using a quartz tube
furnace. Psyche precursors were labeled with211
At using N-bromosuccinimide, and thestabilities in PBS and murine plasma werestudied.
211
At-Psychesobtainedwith
65-96%
radiochemical yields and >95% radiochemical
purities. All 211At-Psyches showed high stability
in PBS. While 211At-Psyche-N and -P are
relatively stable in plasma, 211At-Psyche-B and -J
dissociated in plasma within 1 hr.
3B01 Transport of Soil Particle in the
Reservoir-Catchment System Using Fallout
Radionuclides 7Be and 210Pb
TSURUOKA, M.1, OCHIAI, S.2, MATSUKI, A.2,
NAGAO, S.2(1Graduate School of Natural Science andTechnology, Kanazawa University., 2Institute of
NatureandEnvironmental
Technology,
Kanazawa University)
In this study, transport of surface soil particle in
the reservoir-catchment system located in Noto
Peninsula, was investigated by using fallout
radionuclides 7Be (half-life 53 days) and 210Pb(half-life 22 years). The amount of radionuclides
depositing from the atmosphere, sedimentation inreservoir, and the outflow from system were
measured using a collecting pan, sediment
trap, and water level meter installed in thereservoir. The amount of radionuclides
transported from the catchment area to thereservoir was estimated assuming that the total
amount of deposition from the atmosphere andtransport from the catchment corresponded to thetotal amount of sedimentation in reservoir andoutflow from the system. The amount of 210Pb
accumulated in the reservoir was mostly due tothe amount transported from the catchment area.
On the other hand, the amount of 7Be transported
from the catchment area was smaller than that of210
Pb. It suggests that time scale of soil particle
transportation is much longer than the half-life of
7
Be in this catchment. This result may be
attributed to the result that most of the 7Be is
trapped in the litter layer in catchment soils
implying the slow migration of 7Be from litter tosoil particles.
3B02 Uranium reduction by Fe(II) in smectite
TAKEDA, S. 1, SUN, J.1, HAMAMOTO, T. 2,
ISHIDA, K. 2, TANAKA, M.1, ITAI, T.1,
TAKAHASHI, Y.1(1The Univ. of Tokyo, 2NUMO)
Redox behavior in underground geosphere isimportant in terms of radioactive-waste
management and enrichment of uranium to form
uranium deposit. We conducted an experiment toVWXG\ LI XUDQLXP უ  LV UHGXFHG LQWR XUDQLXPს E\)H ჟ LQVPHFWLWH6RGLXPGLWKLRQLWHZDV
used to reduce Fe3+ in Kunipia F,(Na0.42K0.008Ca0.068)(Si3.91Al0.09)(Al1.56Mg0.31Fe3+0.
2+
09Fe 0.01)O10(OH)2. Uranyl solution was added tothe suspension of Fe(II)-bearing smectite as anadsorbent. All the procedures were conducted ina glove box to avoid oxidation. XANES analysis
VKRZHG WKDW 8 ს 8 უ  UDWLR LQFUHDVHG DV WKHLQFUHDVH RI )H ჟ )H რ  ZLWKLQ WKH RFWDKHGUDO
layer in the Kunipia F, whereas almost all
XUDQLXPDGVRUEHGWR.XQLSLD)ZDV8 უ DIWHU
its contact with Fe(III)-gearing Kunipia F without
the reduction treatment. In the presence ofcarbonate ions in the solution, U(IV) wasstabilized as carbonate complex, which is lesslikely to be reduced. Bond length of Fe(II)-O in
WKHVPHFWLWHZDVVPDOOHUWKDQWKDWRI)H ჟ -O inregular Fe octahedral compounds, which maylead to the tendency for Fe2+ to be oxidized toFe3+.
3B03 Fixation of radium by adsorption on
clay minerals in the environment
YAMAGUCHI, A.1,2, KURIHARA, Y.1,
OKUMURA, M.1, HIGAKI, S.2, TAKAHASHI,
Y.2(1JAEA, 2Univ. of Tokyo)
Radium (Ra), which is generated by radioactive
decay of uranium and thorium, is an importantelement from the standpoints of radiation
protection
andgroundwater
circulation.
Although some previous studies suggested the
fixation of Ra by clay minerals based onrelatively higher adsorption coefficients, its detailhas been unclear. Therefore, the purpose in thisstudy is to investigate the migration of Ra in theenvironment with clay minerals. In this study,
core samples collected around Ningyo-togeuranium mine were analyzed because they had
high concentrations of Ra and large amounts ofclay minerals in weathered granite layer. The
samples were analyzed by many methods,
including Ȗ-ray spectroscopy, sequential
extraction, and X-ray absorption fine structure(XAFS). The activity ratio of 226Ra/238U was
below and over 1 in the concentrated layer andthe weathered granite layer, respectively. Resultsof sequential extraction and XAFS showed that
more amount of Ra was distributed to clay
minerals. These results suggested that Ra isadsorbed on clay minerals and fixed in weathered
granite layers, which is important not only forclarification of the behavior, but for developmentof removal method of Ra.
3B04 Nationwide survey of atmospheric 85Kr
activity concentration in Japan
SATO, Y., NITTA, W., ISOGAI, K.
(Japan Chemical Analysis Center)85
Kr (half-life: 10.76 year) is a major radio
nuclide released from the spent nuclear fuelreprocessing plants into the atmosphere. In Japan,
a large-scale nuclear fuel reprocessing plant will
be operated in Rokkasho. Prior to the beginning

of full operation, a nationwide survey of
atmospheric 85Kr has been carried out since 2006.
Atmospheric 85Kr concentrations from 2006 to2019 were within the range of 1.30 to 1.60 Bq /m3 (Average: 1.46 Bq / m3) expect for the
temporary increases due to the pilot operation ofdomestic reprocessing plants and the accident ofFukushima Daiichi Nuclear Power Plant.
Considering the global inventory of 85Kr and theannual decreasing rate due to radioactive decay, It
can be presumed that about 340 PBq(P(peta)=1015) of 85Kr are removed from theatmosphere each year. From this presumption andthe annual release of 85Kr from reprocessing
plants (La Hague, Sellafield, Rokkasho), it is85
possible to estimate whether annualKrinventory increase or decrease. Comparing thechanges in 85Kr inventory with the 85Kr
concentrations in Chiba since 2006 obtained inthis survey, it was recognized that there was a
relationship with the operating status of
reprocessing plants around the world.
3B05
Spatial distributions of 234Th/238U
activity ratio in the Japan Sea and theimplications for scavenging effects
KAMEYAMA, H.1, INOUE, M.1, HANAKI, S.1,
MOROKADO,
T.1,
SHIROTANI,
Y.1,
TAKEHARA, R.1, MORITA, T.2, MIKI, S.2,
HONDA, N.3, NAGAO, S.1(1Kanazawa University, 2National ResearchInstitute of Fisheries Science, 3Japan Sea
National Fisheries Research Institute)
Reactive (particle-reactive) radionuclides in theseawater have been utilized to estimate thescavenging from seawater. The activities of thereactive 234Th (half-life, 24 d) and the extent of
disequilibrium with its soluble parent 238U
(234Th/238U activity ratio) in seawater clarified thescavenging processes. To study the circulation ofparticles in the Sea of Japan, water samples werecollected from 0-1000 m depths in the Tsushima
Warm Current area of the Japan Sea in
July-August of 2016-2019 and February of
2019-2020. By employing low-backgroundJ-spectrometry, the activities of 228Th (half-life,

1.91 y) and 234Th were determined along with226
Ra (half-life, 1600 y) and 228Ra (half-life, 5.75y). In the present study, we examined the verticaland seasonal profiles of 228Th/228Ra ratio (and228
Th/228Ra ratio) in the Japan Sea. Combining
with water circulations implied from 228Ra/226Ra
ratio, we clarify vertical behaviors of reactive
materials in the Sea of Japan.
3B06
Spatial distribution of 134Cs
concentration in the surface waters of thenorthwestern North Pacific Ocean
TAKEHARA, R.1, INOUE, M.1, HANAKI, S.1,
MATSUNAKA, T.1, MORITA, T.2, MIKI, S.2,
KURODA, H.2, TANIUCHI, Y.2, KASAI, H.2,
NAGAO, S.1(1Kanazawa University, 2National ResearchInstitute of Fisheries Science)
This study examined the spatial profiles ofradiosesium (134Cs and 137Cs) concentrations(activities) in the surface waters of thenorthwestern North Pacific Ocean in 2018-2019.
Because of its short half-life (2.06 y), the 134Cs
detected in seawater samples in the present study
is believed to be entirely derived from theDai-ichi Nuclear Power plant (FDNPP) accident.
Therefore, to investigate the migration patterns of
FDNPP-derived radiosecium after the accident,
we mainly focus on 134Cs concentrations on the
FDNPP accident date (March 11, 2011). To
measure low-level 134Cs concentrations,low-backgroundgamma-spectrometrywasperformed on all seawater samples using
Ge-detectors at the Ogoya Underground
Laboratory, Japan. In this study, we mainly focus
on the offshore of the eastern Hokkaido, where
the water masses (Oyashio Current, Soya Warm
Current, and surface water of the Sea of Okhotsk)
are complicatedly mixed. We classify the patternof the water mass mixing, using the data of 134Cs
combining with Radium isotope and salinity.
3B07 Adsorption behavior of cations inseawater on barium silicate-based adsorbent
for SrMINOWA, H. 1, OGATA, Y. 2, KATO, Y. 3,
KOJIMA, S.4(1Jikei Univ., 2Nagoya Univ., 3Hitachi Ltd.,
4
Aichi Med. Univ.)
Sr adsorbent (Pureceram MAq®, Nippon Kagaku
Kogyo) which based barium silicate (BaSi2O5) isuseful for analyzing radiostrontium in theenvironment because it specifically adsorbs Sr.
The purpose of this study is to explain the
behavior of elements such as Sr, Cs, Na, K, Mg,
Ca, Ra and Pb in the system of liquid phase:
artificial seawater and solid phase: Sr adsorbent.
We report the partition coefficients of thisadsorbent and seawater for these elements. The
liquid phase residual ratio of Cs, Na, K, Mg, Ca is
99% or more, and these elements are distributedin the liquid phase. Therefore, Sr can be easily
separated from these elements. The residual rateof Pb in the liquid phase is 14%, and Pb remains
in the liquid phase. On the other hand, Ra and Ac
adsorb quantitatively to the solid phase like Sr. It
has been suggested that SrSO4, which is insoluble,
is involved in the adsorption of Sr in thisadsorbent. Ra and Pb are also adsorbed in thestate of sulfates as RaSO4 and PbSO4. It wassuggested that this adsorbent could be used not
only for Sr but also for collecting Ra and Ac fromseawater.
3B08 Development of analytical method of
Cs/137Cs isotope ratio in environmental soil
samples
SHIMADA, A.1, KIM, M.2, TSUKAHARA, T.2,
NOMURA, M.2, SHIMADA, T.1, TAKEDA, S.1,
YAMAGUCHI, T.1(1Japan Atomic Energy Agency, 2Tokyo Instituteof Technology)
It is possible to deduce contribution of the
Fukushima Daiichi Nuclear Power Station (1F)
accident from the detected radioactivity of 137Cs
as background at the completion of
decommissioning of nuclear facilities. In order to
identify origin of 137Cs using 135Cs/137Cs isotope
ratio, radiocesium must be separated from major
elements of soil followed by measurement ofmass spectrometry. In this study, Cs separation
135

methodusing
Calix[4]arene-bis(tertoctylbenzo-crown-6)(BOBCalixC6) was developed.
First, reusability of the BOBCalixC6 in 1-octanol
solution was studied. The extraction, striping,and back-extraction properties for Na, Mg, Al, K,
Ca, Fe, Sr, Mo, Sn, Sb, Cs, and Ba were hardly
changed by 5 times usage and Cs was separated
from
the
other
elements.
Therefore,
approximately 150 ml of the dissolved solution ofsoil sample collected at Tokai-mura was treatedwith 2 sets of 15 ml of BOBCalixC6 solution 5times. The 135Cs/137Cs isotope ratio wasdetermined using thermal ionization mass
spectrometry. Although precise value of0.3634±0.0005 was obtained for 16900 Bq/g soil
collected near 1F, the precision was decreased for
low concentration of soil samples collected in
Tokai-mura.
3B09
Spectrum analysis of low energy
radiation using a plastic scintillator bottle
KATO, Y.1, OGATA, Y2, MINOWA, H3,
KOJIMA, S.4(1Hitachi, Ltd., 2Nagoya Univ., 3Jikei Univ.,
4
Aichi Med. Univ.)
We have researched and presented for the simple
and rapid analysis of radiostrontium in seawater.
In this work the plastic scintillator bottle (PSB)
method was developed. The PSB method uses aplastic scintillator to measure a filter sample witha low background liquid scintillation counter(LSC-LB7, Hitachi). One of the features of thismethod is to pouch the sample to prevent
contamination. We have succeeded in improving
the PSB method by examining the material forthe pouch processing, and it has become possible
WR PHDVXUH ȕ-ray emitting nuclides with highcounting efficiency. We thought that thismeasurement method could be applied to othernuclides. Therefore, typical low energy
ȕ-emitting nuclides, 3H, 63Ni and 14C, were
measured and spectrally analyzed. By using thefilm of plastic scintillator for the new pouchprocessing, it was possible to obtain counting

efficiencies of 14.4%, 37.0% and 83.7% for 3H,
63
Ni and 14C, respectively.
3B10 Educational use of Ge-68/Ga-68
generater under legally defined level asradioactive material (3): introduction toexperimental program on role of humics insoil environment
MINAI, Y.1,2, NIIZAWA, K.3, NAGATSU, K.4,
WASHIYAMA, K.5, NOZAKI, T.3,6(1Musashi Univ., 2Nedzu Chem. Lab., 3Kitasato
Univ., 4NIRS, 5Fukushima Med. Univ., 6RIKEN)Radionuclides under particular level ofradioactivity is not regarded as radioisotopes
under current regulations. We can apply very
trace radioactivity for educational purposes atclassrooms without special facility for handlingof radioactive substances. Our group supporting
Dr. T. Nozaki has focused on development of68
Ge/68Ga generator kit under its regulation level,
100kBq, for education.
This is the third report after publication of thesummary of achievements made at the initialstage of development in 2018. This report
proposes a use of the 68Ge/68Ga generator kit for
education. A laboratory research program inenvironmental science for high school students
was chosen as a trial case for developing a new
education program using the generator. The
program was focused on experimental works tounderstand roles of humics in soil environment.
The program composed of 9 modules ofexperiments includes 2 modules on metal-humate
interaction: adsorption of metal cations on humic
precipitatesandmetal-humatecomplexformation. Non-radioactive Cu2+ or Co2+ wasused in those modules. Color of each metal ion isan indicator of the presence of the ion in solution
contacting with humic precipitates or other solid
media. This report proposes that the 68Ga tracer
can replace those visible cations applied in alaboratory research program. Besides, it ispossible to improve quality of experiments, using
the tracer.

3B11 Radiocarbon
datingofBifukumon’in-Fujiwara-no-Nariko-hotsugankonshi-kinji-issaikyo sutra: Natural scientificevidence for the use of Zn in the Heian period,
Japan
ODA, H.1, NISHIYAMA, Y.2, IKEDA, K.3(1Nagoya Univ., 2Nara Univ., 3Chuo Univ.)
Bifukumon’in-Fujiwara-no-Nariko-hotsugan-ko
nshi-kinji-issaikyo sutra has been considered tohave been written on navy blue paper with gold
mud. Recent studies, however, indicated that thegold letters are by brass (Cu and Zn), not by Au.
To clarify whether the sutra was truly written in
the Heian period, and whether Zn was used inJapan at that time, we measured radiocarbon ageof the sutra. Paper sample weighting ca.10mg
were cut from the margin of the calligraphy. The
sample was soaked in H2O to peel away theoriginal sheet from the lining. The original sheet
and the lining were then washed in H2O, 1.2N
HCl and 1.2N NaOH. Graphite target was
prepared from each sample. Radiocarbon ages
were measured using the CAMS-500(NEC,U.S.A) at Paleo Labo Co., Ltd., Japan. The
calibrated radiocarbon age of the original sheet
indicated 1020-1151 cal AD. It shows that thesutra was indeed written in the Heian period andbrass was used during this period.
P01 Solvent extraction of Fr and Cs withcalix[4]arene-bis(benzocrown-6)
KOMORI, Y., HABA, H.
(RIKEN Nishina Center)
Francium (Fr) is the heaviest alkali metal. Fr has
been one of the least-studied elements among thenaturally occurring elements because it has nostable isotopes and all its isotopes are short-lived.
Due to the experimental difficulties, chemical
properties of Fr have not been studied in detail sofar. In this work, we investigated the solvent
extraction behavior of Fr and Cs using
calix[4]arene-bis(benzocrown-6). 700 µL of
10௅4௅3 M NaNO3 aqueous solutions containing
221
Fr milked from an 225Ac/221Fr generator and137
Cs were transferred into a polypropylene tube.

ȝ/
RI
1.5
×
10௅3
M

calix[4]arene-bis(benzocrown-6)
in
1,2-dichloroethane was added, and then the tube
was shaken for 5 min. After centrifugation, each
500 µL of the aqueous and organic phases was
subjHFWHGWRȖ-ray spectrometry with Ge detectors
to determine the distribution ratios (D) of Fr and
Cs. We also studied the extraction behavior of Fr
and
Cs
with
1.5
×
10௅3
M
calix[4]arene-bis(benzocrown-6)
in௅4
1,2-dichloroethane from 10 ௅3 M NaNO3/10௅4
M CsNO3 aqueous solutions. We found that the Dvalues of Fr and Cs change similarly as a functionof the NaNO3 concentration, though the D valuesof Cs are slightly higher than those of Fr in boththe 10௅4௅3 M NaNO3 and 10௅4௅3 M NaNO3/10௅4
M CsNO3 solutions. In the conference, we will
discuss these results by comparing with theliterature data and those obtained with crownethers.
P02 Production cross sections of 175Hf in thenatLu(p,xn) and natLu(d,xn) reactions
KOMORI, Y.1, HABA, H.1, AIKAWA, M.2,3,
SAITO, M.2, TAKÁCS, S.4, DITRÓI, F.4(1RIKEN Nishina Center, 2Grad. School of
Biomed. Sci. and Eng., Hokkaido Univ.,
3
Hokkaido Univ., 4ATOMKI)
A long-lived isotope of Hf, 175Hf (T1/2 = 70 d), is
useful for basic studies for rutherfordium (Rf, Z =104). This isotope is producible inno-carrier-added form in the proton- anddeuteron-induced reactions on natLu. However,excitation functions of these nuclear reactions
have been scarcely studied. In this work, wemeasured the excitation functions of thenatLu(p,xn)175Hf and natLu(d,xn)175Hf reactions up
to 18-MeV proton and 24-MeV deuteron energies
using a stack-IRLO WHFKQLTXH DQG D Ȗ-ray
spectrometry. We performed these experiments at
RIKEN and Institute for Nuclear Research(ATOMKI). The target stacks of Ta/Lu/Ti and
Lu/Ti foils were irradiated for 2 h with proton ordeuteron beams of approximately ௅ Q$.
After the irradiation, each foil was subjected toȖ-ray spectrometry with Ge detectors. We noticed
that the half-life of 173Hf is slightly longer thanthat adopted in the current nuclear database.
Therefore, we measured a precision half-life of173
Hf in a separate experiment. In this work, we
could measure the excitation functions of thenatnatLu(p,xn)173,175Hf
andLu(d,x)173,175Hf,
173,174m,174g,176m,177m,177g
Lu reactions. Thick-target
175
yields of
Hf were also deduced from themeasured excitation functions. The yields are
0.47 MBq/µA·h at 17.2-MeV proton and 2.0
MBq/µA·h at 24.0 MeV deuteron. We
determined the half-life of 173Hf to be 24.176 ±0.012 h which is 0.58 ± 0.10 h longer than that in
the database.
P03 Online anion-exchange experiment of89m
Zr in HNO3 for chemical study of Rf
WATANABE,
E.1,
KASAMATSU,
Y.1,
YOKOKITA, T.2, HAYAMI, S.1, TONAI, K.3,
SHIGEKAWA, Y.2, HABA, H.2, SHINOHARA,
A.1(1Grad. Sch. Sci., Osaka Univ., 2Nishina Center,
RIKEN, 3Sch. Sci., Osaka Univ.)
We are interested in the complexation of 104Rf
with nitrate ions and are planning to perform ananion exchange experiment of Rf using theextraction apparatus, AMBER. We havepreviously determined the experimental
condition for Rf using long-lived radiotracers ofhomologue elements, 88Zr, 175Hf, and 234Th. In
this study, online anion-exchange experimentswith the short-lived 89mZr (T1/2 = 4.18 min) in
nitric acid were performed using a gas-jet
transport system at the RIKEN AVF cyclotron.
89m
Zr was produced in the 89Y(d,2n)89mZr
reaction. The products were transported to
AMBER with the He/KCl gas-jet system. We
performed anion-exchange experiments of 89mZr
using Adogen 464 resin in 4.3 – 8.1 M HNO3.
The radioactivity of 89mZr was determined by
gamma-ray spectroscopy with a Ge detector.
Although a part of 89mZr was adsorbed on thereaction container of AMBER, the Kd values,
which were obtained by correcting the adsorptionof Zr, are consistent with those in the batch
experiment. In addition, we repeated theanion-exchange experiment 30 times byautomatic control, and constant Kd values wereobtained throughout the experiment. From thisstudy, it was confirmed that AMBER can beapplied to the anion-exchange experiment of Rf
in nitric acid.
P04 Coprecipitation experiment of 99Mo withsamarium hydroxide for chemical experimentof Sg
KASAMATSU, Y.1, TONAI, K.1, HAYAMI, S.1,
WATANABE,
E.1,
TAKAMIYA,
K.2,
1
SHINOHARA, A.
(1Grad. Sch. Osaka Univ., 2KURNS)
In our previous study, we developed thecoprecipitation method with samarium hydroxide
to investigate the chemical behavior for
superheavy elements. Indeed, we succeeded ininvestigating the coprecipitation behavior forelement 104, Rf. The purpose of this study is toestablish the coprecipitation experimental
method including development of a new
apparatus for the coprecipitation experiment ofelement 106, Sg.
We used carrier-free 99Mo sample produced fromfission of 235U and macro amount of Mo sample
including 99Mo produced by neutron activation of
Mo at KURNS. Coprecipitation behavior of Mo
with samarium hydroxide and precipitation
behavior of Mo were both investigated byconventional suction filtration method. In
addition, Coprecipitation behavior of 99Mo wasalso investigated using a fast and flow filtrationequipment developed for online experiment of Sg.
Consequently, the coprecipitation yield (~0%)
which is consistent with precipitation yield undereach condition was obtained for Mo, suggestingthat the hydroxide precipitation properties ofgroup 6 elements can be investigated throughtheir coprecipitation behavior with Sm. The
coprecipitation yields obtained with theapparatus were equivalent with those obtained byconventional filtration method. It was found thatthe developed equipment is applicable for Sg
experiment.

P05 Development of sample data library forradioactive particles
SATOU, Y.1, IGARASHI, Y.2, MARTIN, P.G.3,
ALHADDAD, O.3, SCOTT, P.G.3(1CLADS JAEA., 2 KURNS Kyoto Univ., 3Univ.
Bristol)Radioactive particles so called Cesium micro
particles is one of nuclear forensic material
emitted from Fukushima Taiichi nuclear power
plant accident, number of researchers in theworld approaching these analyses for discloseparticle generation process. However, key
researchers of these particle in Japan will beretired, and these samples will be lost their
whereabouts. We proposed sample archive
system to protect the particles for the future. The
system combined physical sample storage andthese data library. The library works collecting
basic sample information (when, where, whocollected), ownership, lending history, also
laboratory and system common sample IDs. The
library store non-destructive and destructive
analyses results such as DEJ-ray emitting
radionuclides, SEM, EDS, synchrotron X-ray
analyses results (XRT, XRD, XRF, XAFS) ,SIMS, ICP-MS and so on. Currently, the library
works completely independent from each other's
country due to export control and sample
ownership in unpublished data, but finally thelibrary will be open to public.
P06 The evaluation of 129I internal exposure of
infants due to intake of breast milk
OTA, T.1, MATSUZAKI, H.2, KODAMA, H.3,
TERADA, H.4, NOMURA, K.5, OTA, Y.1,
WANG, X.1, IIDA, M.1, HIBINO, Y.1,
OKAYAMA, K.6, TOYA, M.2., WATANABE,
M.1(1Japan chemical analysis center,2The Universityof Tokyo, 3Teikyo Heisei University, 4National
InstituteofPublicHealth,5Akita
University,6Hiroshima International University)
I-129 is a long-lived (Half-life: 15.7 million year)
iodine radioisotope which is mainly produced by
nuclear fission of Uranium. It has beendischarged to environment from nuclear facilities

including fuel reprocessing plants and nuclear
power stations. I-129 is concentrated in thyroid
when taken into human body, causing long-term
internal exposure which leads to a potential causeof thyroid cancer.
The purpose of this study is to assess the infant's
internal exposure to I-129. For this purpose, we
analyzed I-129 concentration in human milk
which is a main source of nutrition for infants. To
measure extremely low concentrations of I-129,
AMS (Accelerator Mass Spectrometer) was
adopted. In this study, we applied combustion
methods to retrieve iodine quantitatively fromhuman milk samples to overcome interference
caused by high fat content. We established a new
method to retrieve radioactive iodine in humanmilk samples quantitatively through combustion.
Analysis of iodine 129 in the collected humanmilk was carried out, and the internal exposure toiodine 129 due to human milk intake was
evaluated.
P07 Trends in Proficiency Tests Provided by
IAEA ALMERA
OTA, T.1, OTA, Y.1, SATO, S.1, SUZUKI, K.1,
NISHIMORI, C.1, WATANABE, M.1, ISOGAI,
K.1(1Japan Chemical Analysis Center)
The ALMERA network (Analytical Laboratories
for the Measurement of Environmental
Radioactivity) was established by IAEA in 1995
to share technologies for reliable and rapid
analysis in emergencies. ALMERA consists of
187 laboratories representing 89 countries as of
May 2020. We have been participating in the
network since 2008. ALMERA's main activities
are an implementation of proficiency tests,
development of analytical methods, developmentof reference samples for radioactivity analysis,
and implementation of workshops and training.
Annual meetings are held once a year to actively
exchange information. We use the ALMERA
proficiency test as a part of our external quality
control program. The proficiency test is held
every year, and the contents of the program are
updated every time. In this presentation, we will

present the results of recent IAEA ALMERA
proficiency tests.
P08 Consideration on the Concentration
Ratio of Strontium from Ambient Water to
Aquatic Biota
TAGAMI, K., UCHIDA, S.
(Natl. Inst. Quantum Radiol. Sci. Technol.)The amount of released 90Sr was much smaller
than those of radiocaesium from the Fukushima
Daiichi Nuclear Power Plant (FDNPP) accident;
yet, it is still necessary to assess the dose from theradionuclide because the radionuclide has long
biological half-life in human body. Concentration
ratio (CR) can be used to estimate radionuclide
concentrations in foods; unfortunately however,internationally available CR data of Sr for aquaticbiota were usually categorized in big groups,
such as fish, molluscus, and algae. More detailed
CR data for each species are helpful for reliable
dose assessment. In this study, therefore, we
carried out a data survey to enhance the Sr CR
data sets for aquatic biota in marine andfreshwater systems. In total, ca. 3700 CR data for
aquatic biota were collated with species names
and analyzed tissues (muscles, bones, whole etc.).
For freshwater fish collated mainly in Japan, notime dependence of CR in common carp were
found but for crucian carp, some increments wereobserved for the data obtained after the FDNPP
accident. We found that the difference wasmainly due to the co-present major elements inwater which affect the uptake of Sr by fish bodyas previously reported outside Japan.
P09 Evaluation of uncertainty in gamma-ray
spectrometry due to non-uniform distributionof radionuclides in sample container
SUZUKI, K., MIYATA, S., OHTA, Y., ISOGAI,K.
(Japan Chemical Analysis Center)
The measurement uncertainty in gamma-ray
spectrometry with Ge semiconductor detector
was evaluated due to non-uniform distribution ofradionuclides
inmeasurement
sample.

Calculation of uncertainty was performed basedon the framework of JCGM 101:2008 (ISO/IEC
Guide 98-3/Supplement 1:2008) by using EGS5
Monte Carlo simulation code.
Firstly, numerical models were constructed for a
coaxial p-type Ge semiconductor detector and arectangular parallelepiped sample container witha cross section of 4.2cm × 4.2cm square.
Secondly, the sample in the container was
virtually divided into small cubes with a side
length of 2 mm, then the 10% of the cubes wererandomly selected as “gamma-ray sources” andthe counting efficiencies (count/number ofphotons) for the collection of the selected sourceswere calculated. Finally, the uncertainty wasevaluated from the frequency distribution ofcounting efficiencies obtained by repeating thisprocess. The conditions for the simulation wereasfollows:(samplefillingheight:10,20,30,40,50mm, gamma-ray energy: 88.8keV,
661.7keV, 1836.2keV, number of repetitions:
10,000)The uncertainty due to the distribution ofradionuclides in the measurement container was
estimated within 2.5%.
P10 Isotopic ratios of plutonium in theradioactive particles released by the accidentof Fukushima Daiichi Nuclear Power Plant.
IGARASHI, J.1, ZHENG, J.2, ZHANG, Z.1,
NINOMIYA, K.1, SATOU, Y.3, FUKUDA, M.2,
NI, Y.2,4, AONO, T.2, SUEKI, K.5, SHINOHARA,
A.1(1Graduate School of Science, Osaka University,
2
QST, 3JAEA, 4School of Physics, Peking
University, 5Graduate School of Pure andApplied Sciences, Tsukuba University.)
Plutonium is one of the most notableradionuclides in the nuclear accident. The
amounts of Pu released by the Fukushima Daiichi
Nuclear Power Plant (FDNPP) accident were
investigated so far. However, because thereleased amounts of Pu isotopes is small compare
to global fallout, it is difficult to accurately
evaluate Pu contamination caused by the FDNPP
accident. On the other hand, Pu contamination

source can be investigated from Pu isotopic ratios
since Pu isotopic ratios are different by Pu
contamination sources of FDNPP accident,
Chernobyl accident and global fallout. In thiswork, we focused on the insoluble particles
having highly concentrated radioactive Cs(radioactive particles) released from the FDNPP
to determine accurate Pu isotopic ratios. Due totheir insolubility, the particles retained theoriginal property at the time of emission from thereactor, and have never contaminated by Pu fromglobal fallout. We identified Pu isotopes for 6
radioactive particles by radiochemical analysis
and ICP-MS measurement. The average values of240
Pu/239Pu and 241Pu/239Pu isotopic ratios in theradioactive particles were determined as 0.383±
0.019 and 0.171±0.012, respectively. These
values were slightly different from the calculated
value of the core inventory.
P11
Study on prevention effect ofradionuclides adsorbed on the surface ofmeasurement containers
KONNO, Y.1, MAEYAMA, T.1, SAEGUSA, J.2,
SHINOHARA, H.1, OTA, H.1, ISOGAI, K.1(1Japan Chemical Analysis Center, 2Japan
Atomic Energy Agency)
It is well known that radioactive cesium andradioactive iodine are adsorbed on themeasurement container’s surface. In this study,
we used some reagents in measurement vessel
trying to find an anti-adsorption method. The
study was conducted at the time of revising “Theseries of environmental radioactivity measuringmethods No.24 (Sample Pretreatment for
Gamma-ray Spectrometry in Emergencies)”, toconfirm
theprevention
effectofradionuclide-adsorption radionuclides adsorbedon the surface. In our study, we prepare four 2L
Marinelli beakers, and pour 2L tap water. Threebeakers were added to sodium chloride, sodium
thiosulfate and nitric acid, respectively. The otherone was nothing added as a comparative control.
After these preparatory works, we added I-131
and Cs-137 standard solutions in these beakers.
We measured these units by germaniumsemiconductors detector immediately after the
standard solution added. The concentrations of
the solutions were repeatedly measured toobserve their chronological changes. As a result,the adsorption of Cs-137 to the surface was notfound in any units, whereas that of, theadsorption of I-131 was found at each of three
beakers with sodium chloride, nitric acid, and thecontrol. We did not find the adsorption of I-131 tosurface in the sodium thiosulfate unit. Based on
the above, the sodium thiosulfate is designated as
an additive for measuring radioactive iodine in
the revised “The series of environmental
radioactivity measuring methods No.24”
P12 Quality assurance in environmental
radioactivity monitoring.
ABE, G., OHTA, H., KAWAMURA, T., KONNO,
Y., TOYOOKA, S., SUZUKI, K., SATO, S., OTA,
T.
(Japan Chemical Analysis Center)
After the accident at TEPCO's Fukushima
Daiichi Nuclear Power Plant, more severe
attention is being paid to the analytical data onradioactivity, and it is required to provide morereliable data. There is environmental
radioactivity monitoring by the Nuclear
Regulation Department conducting nationwide.
Japan Chemical Analysis Center (JCAC) is
outsourced from the Nuclear Regulation
Department, to ensure the reliability ofradioactivity monitoring in Japan, we areconducting interlaboratory comparisons based on
ISO/IEC 17043 for analysis institutions in all
prefectures of Japan. Here, we report theinterlaboratory comparison’s results using by
Ȗ-ray spectrometry analysis conducted in
FY2019.
JCAC prepares reference samples and distributes
them to the analysis organization. The analysis
organization analyzes and measures the reference
samples. JCAC compares and evaluates theanalysis and measurement results of analyticalinstitutions with the assigned values. The
evaluation method was calculated by the robust
method using Z-score.

According to evaluation results, a higher accurate
analysis was performed in the interlaboratorycomparisons. The causes of the unsatisfactory
results were investigated and through reanalysis
and reanalysis, and the improvements were also
observed.
P13
Ecological cesium resuspension
generated by precipitation-Coarse bioaerosol
IGARASHI, Y.1, KINASE, T.2, KITA, K.3,
HAYASHI, N.3, ISHIZUKA, M.4, ADACHI, K.2,
SEKIYAMA, T.-T.2, KOITABASHI, M.5, ONDA,
Y.6(1Kyoto Univ., 2Meteorolo. Res. Inst., 3Ibaraki
Univ., 4Kagawa Univ., 5Nat. Inst. Agro-Environ.
Sci. & 6Univ. Tsukuba)
Even though it has been nine years since the
Fukushima Dai-ichi Nuclear Power Plant(F1NPP) accident, detectable levels of F1NPP
radiocaesium (10–5 to 10–3 Bq m–3) are stillpresent in the air over evacuating zone of
Fukushima Pref., where was the mostcontaminated region. The continued detection ofradiocaesium is attributable to its resuspension,
but the mechanism of that resuspension is notwell understood. In the present study, we add
additional
evidencefor
thisrain-enhanced/induced aerosol emission in aforest environment, that is outbreak ofradiocesium-bearing aerosols in a Japanese forest
due to precipitation during warm season. We
confirmed that the fungal spore sources in therainy weather for the radiocesium resuspension
seem to be different from those in the fineweather, by applying the weather dependent
sample collection. Larger fungal particles(possibly conidia and ascospore) are probably
emitted during precipitation than during fineweather, suggesting that the rain-splash
mechanism for mold-like fungi could be themajor mechanism.
P14 Simulated generation experiment bylaser irradiation for radioactive particles
emitted from the Fukushima nuclear accident

SATO, R.1, INAGAKI, M.2, SEKIMOTO, S.2,
TAKAMIYA, K.2, OKI, Y.2, OHTSUKI, T.2(1Kyoto Univ., 2KURNS)
A large amount of radioactive materials was
released into the environment as a result of the
Fukushima nuclear accident. There are variety offorms of the radioactive materials. For instance,gas, aerosol, and fine particles. Because thephysical and chemical forms of the released
radioactive materials affect the deposition andmigration in the reactor and in the environment,
the elucidation of their dynamics requires
information on the initial state of them at the timeof formation and release. Therefore, we decided
to simulately generate the radioactive particles bylaser irradiation. Siliceous material wasprocessed by laser irradiation for generating
simulated particles. Irradiation produced thefume and it was captured by impactor. As a resultof SEM observation of the fume, a several
particles were discovered. The sizes of particles
wewe  WR  ȝm and the shape was spherical.
Accordingly, the experimental apparatus used inthis study is able to generate simulated particles
sufficiently. The examination for the simulated
generation experiment was also undertaken withother nominated materials and compared with theactual particles. The details result of them will bereported in the presentation.
P15 Distribution of 90Sr, 137Cs, and direction
dependency of 90Sr/137Cs around the FDNPP
KAJIWARA,
T.1,
NINOMIYA,
K.1,
SHINOHARA, A.1, YAMAGUCHI, Y.2(1Osaka Univ., 2Institute for Radiation Sciences,
Osaka Univ.)
In the nuclear accident, 137Cs and 90Sr are themost important nuclides because of their large
core inventories and long half-lives. However,
the researches on environmental behavior of 90Sr
released by the accident of FDNPP are limited
compare to these of 137Cs due to the difficulty on
quantification. Release process of 90Sr and 137Cs
were strongly influenced by their volatility
properties; 90Sr is low-volatile element, and 137Cs
is high-volatile element, as a result, 90Sr/137Cs

was changed by core temperatures. In previous
studies, when the core temperature reached
2000K, 90Sr/137Cs becomes 10-4. From deposited90
Sr/137Cs distribution, we can categorize release
events from the FDNPP and investigate releaseprocess and core temperature. In this work, we
analyzed 90Sr and 137Cs in 21 soil samples
collected around FDNPP. After extraction of 90Sr
from the soil sample by solid phase extraction
technique 90Sr activity was determined by liquid
scintillation counter. Chemical yield was
identified
by
ICP-MS
measurement.
137
Concentration of Cs was 4.8-294 Bq/g, andthat of 90Sr was 0.41-34 mBq/g. 90Sr/137Cs
changed by direction from FDNPP. In north tonorthwest and south direction, 90Sr/137Cs wasorder of 10-4, it indicated core temperaturereaches around 2000K. In west direction,
90
Sr/137Cs was order of 10-5.
P16 Effect of chemical characteristics offission products on generation process ofradioactive aerosols
TAKEUCHI, T.1, TAKEUCHI, Y.1, TAKAMIYA,
K.2, INAGAKI, M.2, SEKIMOTO, S.2, OKI, Y.2,
OHTSUKI, T.2(1Graduate School of Engineering, Kyoto Univ.,
2
Institute for Integrated Radiation and Nuclear
Science, Kyoto Univ., Osaka Japan)
The generation mechanism of the radioactive
aerosol has been studied by developing anapparatus that simulates the generation process ofradioactive aerosol containing fission products(FP) in our previous work. The apparatus consistsof four parts; generation of aerosol, supply of FPs,
mixing chamber and collecting filter. In order tosupply FPs, neutron irradiated uranium sample
had been used. In the present study, theirradiation condition was changed to observe thegeneration mechanism of different FPs because
chemical effect of FP in the generation process ofradioactive aerosols might become clear. As aresult, it was found that FPs of 87Kr, 92Sr, 94Y,
105
Ru, 128Sb, 131Te, 133mTe, 134Te, 132I, 134I, 135Xe,
138
Cs, 142La are available to observe their
behaviors by shortening irradiation and standing

times. Plural isotopes were observed forruthenium, tellurium and iodine that enables tocheck the reproductivity of experiments bycomparing the behavior of FPs among isotopes.
The attachment behavior of FPs to solution
aerosols will be discussed by observed
attachment ratio of these FPs.
P17 Strontium-90 measurement in trace
amount of hard tissues for distribution
analysis
KOARAI, K.1, MATSUEDA, M.1,2, AOKI, J.1,2,
YANAGISAWA,
K.2,
FUJIWARA,
K.1,
TERASHIMA, M.1, KINO, Y.3, OKA, T.1,
OKUTSU,
K.3,
YAMASHITA,
T.3,
3
3
TAKAHASHI, A. , SUZUKI, T. , SHIMIZU, Y.3,
CHIBA, M.3, OSAKA, K.3, SASAKI, K.3,
SEKINE, T.3, FUKUMOTO, M.3,4, SHINODA,
H.3, KITAMURA, A.1, ABE, H.1(1JAEA, 2Fukushima Univ., 3Tohoku Univ.,
4Tokyo Med. Univ.)
We demonstrated a method of 90Sr measurementin small pieces of hard tissues with radioactivity
measurement
or
ICP-MS
measurement.
Interference elements of the measurements were
removed by chemical separation. We could
determine 90Sr in 0.1 g of hard tissues byradioactivity measurement method and ICP-MS
method. Limit of detection of the ICP-MS
method was lower than that of the radioactivity
measurement. The ICP-MS method is adequate
method for distribution analysis of 90Sr in thehard tissues.
P18 Sample preparation procedure for ESR
dosimetry using teeth of wild animal
OKA, T.1, MITSUYASU, Y., TAKAHASHI, A.,
KOARAI, K., KINO, Y., SEKINE, T., OKUTSU,
K., YAMASHITA, T., SHIMIZU, Y., CHIBA, M.,
SUZUKI, T., OSAKA, K., SASAKI, K.,
FUJISHIMA, Y., URUSHIHARA, Y., GOH, V.,
ARIYOSHI, K., NAKATA, A., YAMASHIRO,
H., SUZUKI, M., FUKUMOTO, M., MIURA, T.,
SHINODA, H.

(1JAEA, 2Tohoku Univ., 3Hirosaki Univ.,
4
Fukushima Medical Univ., 5Hokkaido Univ. of
Science, 6 Niigaka Univ, 7RIKEN)
Releases of the radioactive materials from the
Fukushima Daiichi Nuclear Power Plant accident
result in a low dose exposure to wild animals.
The external dose of wild animals is commonly
estimated by the external dose rate of thecaptured point, but the estimated exposure dose
has huge uncertainties because the size of thehabitat and/or the movement of the wild animals
are not included in the estimation. To estimate theexternal dose precisely, we utilize electron spinresonance (ESR) dosimetry. In this work, weinvestigated the sample preparation procedure ofwild animals. The ESR spectrum of enamel ofracoon captured in Namie-town, Fukushima has abroad ESR signal due to metal components. We
attempted to remove metal components bychemical treatments. After the chemicaltreatment, the irradiation of 60Co gamma-ray and
ESR measurements were repeated to obtain therelationship between the CO2 radical intensity
and the absorbed dose. The linear relationshipbetween them suggests that we can apply ESR
dosimetry for racoon teeth. Using thisrelationship, the external exposure dose wasestimated to be 68.8 mGy.
P19
Surface water circulations in thesouthwestern Sea of Japan: Implications fromthe Ra-228/Ra-226 ratio and Cs-134
concentration
HANAKI, S.1, INOUE, M.1, TAKEHARA, R.1,
MOROKADO,
T.1,
SHIROTANI,
Y.1,
2
3
TAKIKAWA, T. , YOSHIDA, M. , OKINO, A.4,
MIKI, S.5, NAGAO, S.1(1Kanazawa Univ., 2Nagasaki Univ., 3Shimane
Univ. Oki Marine Biological Station, 4Shimane
Prefecture, 5Fisheries Resources Institute)
The concentration (activity) ratios of radiumisotopes (228Ra/226Ra ratio) at the surface of thesouthwestern Sea of Japan showed high values(1.5–2.5) in July–December (2015–2019),
indicating a seasonal variation. This was due tothe high mixing ratio of 228Ra-rich continental

shelf water from the western East China Sea(ECS). Furthermore, the 228Ra/226Ra ratios of thewaters exhibited a wide lateral variation withhigher values relative to those in coastal areas(1.5–2.0). The total fractions of waters from the
ECS continental shelf and Yangtze River (fS+Y) in
the southwestern Sea of Japan (0.2–0.5), basedon 228Ra concentration and salinity, were 1–1.5
times higher than those of the coastal waters(0.2–0.3), in contrast to a small variation withlower fS+Y values in January–June (particularly inMarch–June). This indicated the irregularpatterns of the lateral intrusion of the 228Ra-richbranch of the Tsushima Warm Current inJuly–December, passing through of the Tsushima
Strait.
P20 Method development for simultaneous
determination of 237Np and Pu isotopes inseawater by SF-ICP-MS with a single column
chromatographic separation
ZHANG, S.1,2, YANG, G.1, ZHENG, J1., PAN, S.2,
AONO, T.1
(1 National Institutes for Quantum andRadiological Science and Technology, 2 Nanjing
Univ.)
Plutonium in seawater is a well-known tracer inbiogeochemical
processes
withitsparticle-reactive properties. Recent studies
evidenced that another transuranic isotope, 237Np(t1/2=2.14×106y) has a similar behavior of 137Cs,
thus shows great potential to act as a tracer forwater mass circulation for decadal and longer
time scales. However, information on 237Np
presented in seawater, especially in open ocean isvery scarce, the distribution and inventory of237
Np in the ocean remains largely unknown due
to its low concentration in seawater and great
analytical challenge for its measurement. Most
methods for analysis of 237Np need a large
volume seawater, tedious chemical separations,and long counting times in the radiometricmethods of alpha spectrometry, and theexpensive AMS devices. In this study, we present
a new method for simultaneous determination of237
Np and Pu isotopes in seawater by SF-ICP-MS.

242

Pu was employed as a non-isotopes yield tracer
for 237Np and Pu isotopes. A single column
anion-exchange (AG MP-1M) chromatography
was used for chemical separation of 237Np and Pu
isotopes from seawater matrix. This method wasapplied to determine the seawater samples
collected from the Pacific Ocean for the firsttime.
P21 Re-suspension of insoluble Cs radioactive
particles to the atmosphere
TANG, P.1, HATANAKA, K.1, KITA, K.1,
SATOU, Y.2, NINOMIYA, K.3, SHINOHARA,
A.3, KINASE, T.4, ADACHI, K.4, IGARASHI,
Y.5(1Ibaraki Univ., 2CLADS/JAEA, 3Osaka Univ.,
4
MRI, 5Kyoto Univ.)
Due to the Fukushima Daiichi Nuclear Power
Plant accident (FDNPP), insoluble radioactive Csparticles were generated and released into theenvironment. Resuspension of such particles,
which may be derived from FDNPP
decommissioning work, are recognized as along-term potential risk factor. In this study, weinvestigated the reemission-possibility and thephysicochemical characteristics of these
insoluble radioactive Cs particles. Twenty
radioactive Cs particles were detected in 186
aerosol samples collected from 2015 to 2019 in adifficult-to-return-zone about 25 km far from
FDNPP. SEM-EDS analysis was performed on
the successfully isolated 15 Cs bearing particles,
and all were type-A particles with the diametersof 1-ȝP$OWKRXJKWKHUHVXVSHQVLRQ-frequency
was low, it can be clarified that such radioactive
Cs particles could be re-emitted to theatmosphere.
P22 Speciation of uranium particles using
P-X-ray absorption near edge structure
spectraYOMOGIDA, T.1,2, OUCHI, K.2, KITATSUJI,
Y.2, TAKAHASHI, Y.1(1Tokyo Univ., 2JAEA)
Micro X-ray absorption near edge structure(XANES) spectroscopy was applied to thecharacterization of uranium particles with adiameter of a few micro-meter. Uranium
dioxide(UO2), Uranium peroxide(UO4 ʀnH2O),
Uranyl nitrate (UO2(NO3)2 ʀ 6H2O) were
employed. Uranium samples were diluted inboron nitride for XANES measurement
performed at BL01B1 of SPring-8. Uranium
particles on carbon tape were used for
micro-XANES measurement at BL37XU ofSPring-8.
The XANES spectrum of the UO2 particle with adiameter of 3 Pm was consistent with thestandard UO2 spectra. The result is showing theapplicability of the proposed methods toanalyzing micron sized uranium particle.
However, a large spectral distortion was observedin the XANES spectrum of the small uranium
particles with a diameter less than 3 Pm. X-ray
beam shift in the measurement or backgroundfrom Br in the carbon tape would be interferingwithmicro-XANES
measurement.
Improvements of sample preparation andmicro-XANES
measurement
methodis
indispensable for speciation of small uranium
particles.
P23 Feasibility study on the on-line
monitoring of tiny particles containingalpha-emitters generated in the fuel-debris
retrieval from the reactors of Fukushima
Daiichi Nuclear Power Plant
TOYOSHIMA,A.,
FURUTANI,H.,TERAMOTO, T., MUTA, H., TOKOI, K.,
YOSHIMURA,T.,
TOYODA,M.,
SHINOHARA, A.
(Osaka Univ.)
The retrieval of the fuel debris from the reactors
in Fukushima Daiichi Nuclear Power Plant isplanned to start at FY2021. It is concerned thatradioactive
tiny
particles
containing238
alpha-emitters such as
U and 239Pu are
generated in the cutting process of the debris andare dispersed to outside of the reactors. We,
therefore, suggest on-line monitoring of the tiny
particles using an Aerosol Time-Of-Flight
Mass-Spectrometer (ATOFMS) to prevent theparticles from leaking out of the reactors in thedebris retrieval. At present, we are preparing thegeneration apparatuses of tiny particles frommodeled solid and liquid samples and the on-line
detection system using ATOFMS. In this study,
we present the present status of the sample
preparation, developments of the generation
apparatuses, and results of preparatory
experiments.
P24 Non-destructive image experiment using
Muonic X-ray with Si Double-sided Strip
Detector
CHIU, I-H.1, KAJINO, M.1, SHINOHARA, A.1,
NINOMIYA,
K.1,
TAKEDA,
S.2,
2
2
KATSURAGAWA, M. , TOMARU, R. , YABU,
G.2, NAGASAWA, S. 2, TAKAHASHI, T.2,
WATANABE, S.3(Osaka University1, Kavli IPMU2, JAXA3)This study presents an element analysis method
using a muon beam. Muon stopped in the matterand they are captured by element. When muontransitions to a low energy level in atom, muonscharacteristic X-rays are radiated. This makes it
possible to non-destructively analyze theelements of matter with an excellent energy
resolution detector. Furthermore, we will develop
a two-dimensional silicon detector with highposition resolution. It is possible to reconstruct
the image by muon characteristic X-rays with thistwo-dimensional detector. When the muon
characteristic X-rays come into a silicon
semiconductor, lots of electron and hole areproduced. The amount of electric charge iscalculated for the energy of the input muon
characteristic X-rays. Then the energy spectrumwith high resolution can be obtained. At the sametime, the double-sided strip detector provides
position information of detector with highposition resolution. Combing the energy
spectrum and position information, an image ofthe matter is reconstructed. This talk will
introduce the development and details of thesilicon double-sided strip detector. Then, thedeveloped silicon detector was subjected to amuon X-ray experiment at the J-PARC.

P25 Mössbauer Characterization of Iron
Oxidation State during Carbonization ofIron-Loaded Woody Biomass
YAMAUCHI,
S.1,
YAMAGISHI,
T.2,
KURIMOTO, Y.1, SUZUKI, H.1, TAKAYAMA,
T.3, SAKAI, Y.3(1Akita Prefectural Univ., 2Seikei Univ., 3Daido
Univ.)
Recently, woody biomass has attracted attention
as the resources of functional carbon materials.
Conductive filler made from iron-loaded
charcoal is expected to be put into practical use interms of high electric conductivity and low cost.
The iron-loaded woody charcoal is graphitizedfrom considerably low temperatures; however,
the whole mechanisms of this carbonization
reaction has not been completely explained. In
particular, many of details of iron-role incarbonization are not elucidated. We investigatedthe effects of carbonization temperature andcooling rate on the chemical states of iron andcarbonusing
MössbauerandRaman
spectroscopy in order to discuss the mechanismof the changes in iron-oxidation states.
P26 Hyperfine field measurements for theinvestigation of nuclear spin relaxation of the
A site probes in CdFe2O4 E\ PHDQV RI ၫၭ)H
Mössbauer spectroscopy
ITO, T.1, KONAKA, M.2, SATO, W.1,2(1Grad. Sch. Nat. Sci. Tech., Kanazawa Univ.,
2Inst. Sci. Eng., Kanazawa Univ.)
Spinel oxides exhibit various physical properties
depending on the constituent metal elements andon their residence positions: the tetrahedral A siteand octahedral B site. Especially, electric
conductivity and magnetic property of spineloxides have been extensively studied for practicalapplication. In our recent study, hyperfine fields
in CdFe2O4 were measured by means of
perturbed angular correlation spectroscopy withthe 111Cd(ˣ111mCd) probes and obtained spectra
implying nuclear spin relaxation of the probe
occupying the A site at two different
temperatures (room temperature and 77 K).

However, the cause of this phenomenon is still
unknown. In order to provide insight into theunexpected phenomenon, we measured hyperfine
fields in CdxFe3-xO4 (x=0.25, 0.5, 0.75, 1.0) bymeans of 57Fe Mössbauer spectroscopy toinvestigate the local environment of Fe nuclei.
Magnetic interactions appearing in the spectra
gradually disappear as the Cd concentration
increased, and the fitting results revealed that Cd
occupies the A site for all the samples
investigated. The results are consistent with thoseof the previous studies, suggesting that thenuclear spin relaxation phenomenon is acharacteristic of Cd at the A site.
P27 57Fe Mössbauer spectra of sand samplesof Inamuragasaki in Kamakura
YOSHIDA, M.1, ENDO, K.2, KOBAYASHI, Y1(1UniversityofElectro-Communications,2
Showa Pharmaceutical University)
Iron is contained in iron oxides, iron sulfides, andthe substituted positions of metal-ions in silicatesin the crust. It is important to study the chemical
forms of Fe atoms in environmental samples
from the view point of earth science andenvironmental science. There are many beaches
in Shonan area near Kamakura. Only the
Inamuragasaki beach has a color of black. 57Fe
Mössbauer spectroscopy was applied to the sandof Inamuragasaki beach in order to characterize
the chemical form of Fe atoms. 57Fe Mössbauer
spectra of the sand samples were measured at RT,
77 K and 15 K, respectively. X-ray diffraction
patterns of them were also observed.
The Mössbauer spectra of sand samples obtainedat RT could be analyzed by two components of adoublet and a singlet. One of the results wasdemonstrated to be a doublet with I.S. į =1.31(1) mm/s and Q.S. = 2.35(2) mm/s and a
VLQJOHW 6 ZLWKį   PPV,WLVFRQVLGHUHG
that a doublet and a singlet is assigned to be inFe2+ (H.S.) and Fe3+ (H.S.), respectively. Since
there is clearly no magnetic splitting, it wasdetermined to be in paramagnetic states. Basedon 57Fe Mössbauer spectroscopy and XRD, thechemical forms of Fe atoms in sand samples ofInamuragasaki will be discussed.
P28 Antimony-121 Mössbauer spectra ofsquarepyramidalorganoantimony
compounds with catechol ligands
TAKAHASHI, M., IITSUKA, T.
(Toho Univ.)
Mössbauer spectra for the square pyramidal (SP)organoantimony R3SbL (R = Ph, p-FC6H5, p-Tol,o-Tol, o-Xyl, Mes) with catechol (H2cat) and
2,3,4,5-tetrachlorocatechol (H2Cl4-cat) were
measured at 20 K and the electron distribution
was compared with those of the TBP complexes.
7KHLVRPHUVKLIWį UHODWLYHWR,Q6E ZDVWR
4.32, the quadrupole coupling constant e2qQ was–8.56 to –12.2 mm s–1, and the asymmetry
SDUDPHWHUȘWR7KHYDlue of e2qQ was
smaller than the value of –20.6 mm s–1 of
Ph3Sb(OTf)2 with TBP structure, which was
about half. This strongly reflects the difference instructure. We calculated the Muettertues and*XJJHQEHUJHU V GLKHGUDO GLDJRQDO į24, which
evaluatestheSPcharacterofthefive-coordination complex, to examine therelation with the Mössbauer parameters. The
e2qQ WHQGV WR GHFUHDVH DFFRUGLQJ WR į24.
Consequently, the SP structure was found to givedifferent parameters than TBP, and the electron
distribution was, however, also strongly
influenced by the substituents.
P29 VRFB membrane permeability tests
using radiotracer 48V
SHIRASAKI, K.
(IMR, Tohoku Univ.)
Vanadium redox-flow battery (VRFB) draws
attention for the energy storage system, which isparticularly useful for conjunction withrenewable energy sources. The VRFB consists ofelectrodes, membranes, electrolytes and only
vanadium ions as active substance in both
positive (VO2+/VO2+) and negative (V3+/V2+)
electrolytes [1]. This constitution makes it
convenient to recover battery capacity to initialstate by adjusting the concentration and valenceof vanadium ions between positive and negativeelectrolytes, and makes it difficult to directly
evaluate vanadium ions crossover of themembrane, simultaneously.
In the last year, we developed an evaluation
method of the crossover of vanadium ionsthrough the membrane using radiotracer 48V [2].
The method has a potential for understanding
nature of the membrane both in a self-discharge
andcoulombic
efficiency
duringcharge-discharge processes of the VRFB.
In this study, we investigate the behavior ofcrossover of vanadium ions in the different typesof the membranes.
[1] E. Sum, M. Skyllas-Kazacos, J. Power
Sources, 15 (1985) 179-190.
[2] K. Shirasaki, T. Yamamura, J. Membr. Sci.,
592 (2019) 117367.
P30 Development of 211At labeling method byelectrolysis.
NAKAGAWA,S.,
KADONAGA,Y.,TOYOSHIMA, A., OOE, K., KANDA, A.,
NAGATA, K., TERAMOTO, T., TOKOI, K.,
YOSHIMURA, T., SHINOHARA, A.
(Osaka Univ.)
211
At (half-life = 7.2 h) is expected to be used for
WDUJHWHGĮ-therapy. There are various methods forlabeling 211At on molecular targeting agents. The
substitution reaction of 211At using a harmful
metal such as tin or mercury is common.
However, it is concerned to be problematic forhuman health in clinical uses. Therefore, in thisstudy, we aim at labeling 211At by a clean method
by applying electrolysis that does not contain any
oxidants and metals. As a labelled compound,astato-Į-methyl-L-tyrosine(211At-AAMT),
which is currently labeled by substitution using
mercury, was selected. Because it is important togenerate 211At cations for the electrolytic labelingreaction, we first aimed to change the chemical
species of astatine. In the experiment, theelectrolytic oxidation of 211At was carried out
under various conditions of pH and applied
potentials. Formed 211At species were assayed byThin Layer Chromatography (TLC) before andafter the electrolysis. Spot positions of 211At wereobserved using Imaging Plate. After confirming
change of oxidation states of 211At before andafter the electrolysis, an electrolytic labelingreaction was performed. As a result, oxidation
states of astatine species were changed after
electrolysis. The electrolytic labeling reaction
will be reported in the symposium.
P31 Development of identification method forchemical form of astatine using mass
spectrometry
TOKOI, K., TOYOSHIMA, A., KADONAGA,
Y., TERAMOTO, T., SHINOHARA, A.
(Osaka Univ.)
211
At is considered as one of the most promisingradionuclides for targeted alpha therapy becauseof its suitable half-life of t1/2 = 7.2 h andD-particle emission probability of 100%
including that of its short-lived daughter nucleus
211
Po. However, due to the lack of long-lived
radioisotopes of At, its chemical properties havebeen still incompletely understood. In particular,
for medical application, it is important tounderstand chemical forms of At under various
conditions. Mass spectrometry is promising forthe determination of chemical forms of At. In the
At case, however, sample condensation isrealistically important because of the limitationof its available amount. Therefore, we started atstudying gold nanoparticles which are known toadsorb astatine quantitatively, as a condensation
absorbent (matrix) for At. In this study, we report
the development plan of the mass spectrometer
for astatine and a sample concentration method
for a lighter homolog of At, iodine. Details of
results will be presented in the symposium.
P32 Production of 47Sc for cancer therapy
with accelerator neutrons by deuterons
HASHIMOTO, K.1, TSUKADA, K.1,2, SAEKI,
H.1,3, KAWABATA, M.1,3, OHTA, A.1,3(National Institutes for Quantum andRadiological Science and Technology1, Japan
Atomic Energy Agency2, Chiyoda Technol
Corporation3)

Scandium-47 is an attractive radionuclide forcancer therapy, because of emissions of medium
energy beta particle (a mean energy of 162 keV)and gamma rays (159 keV) suitable for imaging,and its appropriate half-life (3.35 days). In thisstudy, we have investigated the production of47
Sc by the 47Ti(n,p)47Sc reaction using fastneutrons from natBe(d,n) reaction at the CYRIC
of Tohoku university. The irradiated natural Ti
metal sheets were dissolved in HCl/HF (400/l)
and 47Sc as well as 44m, 46, 48Sc and 47Ca weredetected in the solution. The purified 47Sc was
obtained by the DGA normal resin separation
method with high recovery yield.
P33 Chemical separation of As-74 using
solvent
extraction
andcolumnchromatography
IKEDA, H.1,2, KIKUNAGA, H.2, KOHDA, T.3,
QIAN, Z.J.3, CHIEN, M.F.3, INOUE, C.3, SUZUI,
N.4, KAWACHI, N.4, RAMDHANI, D.1,
WATABE, H.1(1CYRIC, Tohoku University, 2ELPH, Tohoku
University, 3GSES, Tohoku University, 4QST)We produced As-74 (T1/2 = 17.77 d), which is oneof the positron-emitting nuclides of As, andinvestigated the chemical separation method. We
produced As-74 by irradiating Ga2O3 pellet with
30 MeV alpha particles using the AVF cyclotronof Cyclotron and Radioisotope Center (CYRIC),
Tohoku University. The irradiated Ga2O3 pellet
was dissolved into 1 mL of 12 M NaOH solution
while heating. After neutralization with about 2
mL of 6 M HCl, solvent extraction was
performed with 5 mL of organic solvents
containing bis(2-ethylhexyl)phosphate (HDEHP).
The concentration of HDEHP was 1 M, andorganic solvents were benzene, toluene, ethyl
acetate, and hexane. From the ratios of As-74 inaqueous and organic phases, we selected hexane
as the organic phase. Ethanol was added to theaqueous phase to 50 mL, and solid NaCl was
precipitated. The supernatant was charged into ananion exchange column, and As-74 was eluted by
0.1 M HCl. The results of column
chromatography suggested that almost all ofAs-74 was eluted by 8 mL of 0.1 M HCl. Fromthese results, we determined the chemical
separation method of As-74 from irradiatedGa2O3.
P34 Development of a synthetic method foran aromatic hypervalent astatine compound
KANDA, A.1, NAGATA, K.2, TOYOSHIMA,
A.3, SHINOHARA, A.1,3, YOSHIMURA, T.2(1Grad.
SchoolofSci.,Osaka
Univ.,
2
Radioisotope Res. Ctr., Inst. of Rad. Sci., Osaka
Univ, 3Inst. of Rad. Sci. Osaka Univ.)
Astatine-211 is one of the promising nuclides forapplication to targeted alpha therapy. However,
medical application of astatine-211 has been
restricted by a lack of stability of astatine-labeled
compounds. Astatine-211 is currently labeled to amolecule as an aromatic monovalent astatine, andtrivalent (hypervalent) astatine is potentiallysuitable as an astatine-labeled compound because
trivalent astatine ion can be incorporated in acyclic planar three-coordinated structure.
Surprisingly, chemical property of hypervalentastatine compound has not been studied. The
study on influence electric and/or steric effects ofa ligand to the hypervalent astatine compound is
expected to lead to a novel stable astatine-labeled
compound or elucidation of the chemical
property of an aromatic astatine compound. In
thepresent
study,
synthesisof(diacetoxyastato)benzene in which astatine istrivalent was attempted. Astatobenzene wasoxidized with sodium hypochlorite in thepresence of acetic acid. After the reaction, theastatine species in the reaction solution was
analyzed with radio-HPLC. As the result, aheavy-tailed peak was observed at retention time(Rt) = 8.5 min which was different from 4.2 minof (diacetoxyiodo)benzene. The peak positionchanged to Rt = 12.5 min by addition of sodium
sulfite to the solution after oxidation of astatine.
The result suggests that the oxidized At
compound was reduced by sodium sulfite toreproduce astatobenzene. It is now projected theexperiments using radioiodine and astatine tochange in electronic property of ligand to find out

the difference of Rt between astatine and iodine
compounds.
P35 Synthesis of Radiometal Complexes
Coordinated with New Macrocyclic Ligand
Bearing Phosphonate Pyridine Arms
BABA, K.1, NAGATA, K.2, YAJIMA, T.3,
YOSHIMURA, T. 2
(1Osaka Univ., 2Osaka Univ. RI center, 3Kansai
Univ.)In recent years, targeted alpha therapy (TAT) has
attracted much interest. 225Ac is one of suitable
nuclides for TAT. The reaction of the metal ion
with a ligand is prefered to proceed in a mild
condition to give a highly stable metal complex.
In this study, we newly designed and synthesized
the new ligands, macropp and macroppEt in
which two arms with phosphonic acid or
phosphonic acid ester groups are attached to the
18-memberedmacrocycle,
4,13-diaza-18-crown-6.
Inaddition,thelanthanum complexes using stable isotopes weresynthesized. The Rf values of the ligands and the
mixtures of La(III) and ligands were different one
another in thin layer chromatography withadsorbent of alumina and cellulose. This
indicates that the reactions of Ln(III) with one
molar equivalent of the ligands gave the La(III)complexes in high yields at room temperature.
The results of the reaction of Ac(III) with theligands will be reported in the JNRS annual
meeting.
P36 Production of Sc-46 and Sc-47 tracers byphotonuclear reactions
KIKUNAGA, H.
(ELPH, Tohoku Univ.)
Scandium-46 and scandium-47 are nuclei that are
useful or expected to be useful in various fields
such as radiotherapy and basic research. It is
important to produce separately between these
nuclides depending on the application. In thiswork, the radioactivity ratios of 46Sc and 47Sc
produced by photonuclear reactions from natTi
and 48Ti targets have been determined. natTiO2 and48
TiO2 were enclosed in a quartz tube forbremsstrahlung radiation. The irradiations werecarried out using the Electron Linear Accelerator
at Tohoku University. The accelerator was
operated at an electron energy of 20-50 MeV. The
TiO2 targets were placed in close contact with theback of a Ta converter and cooled with running
tap water during the 10-30 minutes irradiation.
After the irradiation, the targets were examinedby gamma-spectrometry with a high purity Ge
detector. As a result, the Sc-46/Sc-47
radioactivity ratios for natTi and 48Ti targets were
determined as a function of irradiation energy.
P37 Effect of Sodium Nitrate Concentrationand pH on Adsorption Behavior of Trivalent
Actinides and Lanthanides on Pyridine Resinin Aqueous Solution
FAUZIA, H.I.1, ABE, C.2, KONASHI, K.2,
SUZUKI, T.1(1Nagaoka Univ. Technol., 2Tohoku Univ.)
Trivalent actinides (An (III)) and lanthanides(Ln) have similar ionic radii in aqueous solution.
Thus, the separation of these elements is not soeasy. We have been studying the adsorption
behaviors of these elemental groups on pyridine
resin. In our previous studies, we found that thegroup separation is available in HCl system,
whereas in HNO3 system, the group separation
phenomenon does not occur as the adsorption isdue to the ionic radii. The reason why thisdifference appears is that the adsorption
mechanism of An(III) in HCl system is complex
formation with pyridine group and the adsorptionof An(III) and Ln in HNO3 system is ion
exchange. In the present study, we investigated
the absorption behavior of An(III) and Ln on
pyridine resin in NaNO3 aqueous solution withdifferent concentration of NaNO3 and pH of theaqueous solution. As a result, we found that thepossibility of group separation of An(III) and Ln
in HNO3 system by suppressing the protonationof pyridine group.
P38 DFT calculation for elucidation of MA
separation mechanism using C2-POPhen

NAKASHIMA,
T.1,
FUKASAWA,
Y.2,
NAKASHIMA, S.2,3(1Grad. School of Sci., Hiroshima Univ., 2Grad.
School of Sci. and Eng., Hiroshima Univ.,
3
N-BARD, Hiroshima Univ.)
Selective separation of minor actinides (MA) andlanthanides (Ln) is important in the treatment
process of high-level radioactive liquid waste.
The solvent extraction method is useful for the
separation of MA and Ln and the elucidation of
the separation mechanism using experiments andcalculations is in progress. Recently, C2-POPhen(tetraethyl(1,10-phenanthroline-2,9-diyl)phosphonate) has
been studied as an extractant with highdistribution ratio and MA selectivity[1]. In thisstudy, we tried to clarify the extraction
mechanism of C2-POPhen by using DFT (density
functional theory) calculation. ML(NO3)3 andML23+ (M=Eu3+, Am3+, L=C2-POPhen) models
were created based on the similar complexes
Y(CyMe4-BTPhen)(NO3)(CN)3andCu(C2-POPhen)2PF6Cl6. Structural optimizationand energy calculation were performed, and thebond order, molecular orbital, and MOOP
(Molecular Orbital Overlap Population) wereanalyzed based on the energy results.
The magnitude of orbital interaction was
evaluated using molecular orbital diagram and
MOOP analysis. These results show that theoverlap of Am's f orbital and coordinating N
atom's orbital is larger than that of Eu's f orbital.
From these results, it was clarified that the MA
selectivity of C2-POPhen was affected by thedifference in the metal f orbital and N atom
orbital interactions.
[1] L. Xu et al., Inorg. Chem. 2019, 58,
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P39 An investigation on the laboratory
management from the viewpoint of the
management theory
TANIGUCHI, E.1, ODA, H.2(1Chukyo Univ., 2Nagoya Univ.)Most of the principal investigators (PI) of
University are not well educated to be alaboratory manager; therefore, most laboratories
have many management problems (Kwok, 2018).
The purpose of this study is to clarify the typicalproblems on the management of chemicallaboratory in Japanese graduate school and toindicate their countermeasures.
We, first, conducted unstructured interviews withprincipal investigators, other staffs and students
about the problems of laboratory management.
The interviews revealed the following threeproblems. The first is the phenomenon thatstudents save their efforts to their researches
while watching each other’s progress. The
second is that students do not voluntarily conduct
the researches without their supervisor’s
guidance. The third is that students lose
motivation for the current researches after
obtaining a tentative job decision.
Next, we indicated their countermeasures fromthe viewpoint of the management theory. The
first phenomenon is called “systematic
soldiering”. As the countermeasure, PI need tograsp the situation of students in detail. The
second problem is called “flounder’s paradox”.
The countermeasure is for PI to take leadershipcorresponding to student’s maturity levels. The
third is caused by a student’s recognition that the
purpose of their research is to obtain a master’s
degree. For this problem, PI should makestudents realize that current research will be
useful for their future work.
P40 Tetrahedral Mesh Structure Modeling of
New Generation Helical Fusion Reactor
FFHR at NIFS for The Neutron Transport
Simulation using a Monte-Carlo Based PHITS
code
SAKAMA, M.1, KOBAYASHI, M.2, SAZE, T.2,
GOTO, T.2, MIYAZAWA, J.2, HAMABE, D.1,
KAMIYA, K.1, YOKOTA, K.1, OTANI, R.1,
MATSUMOTO-KAWAGUCHI, E.1(1Tokushima Univ., 2NIFS)
Today, the National Institute for Fusion Science(NIFS) is energetically working on studies

relative to ultra high-temperature plasma andcorresponding scientific phenomena on the stateof matter for achieving a stable and permanentenergy in future. Miyazawa's laboratory team
(Fusion Engineering Research Project Team) inwhich we have collaborated from FY2019 iscarrying out researches on New Generation
Helical Fusion Reactor FFHR as the steady-state
reactorreplacedcurrently
operatingexperimental-state reactor of LHD. In the
research role of this team, we would like todevelop the tetrahedral mesh structure modelingof FFHR and to simulate the neutron transport on
the modeling calculation space when the FFHR
will operate using PHITS code. In thispresentation, we have investigated the tetrahedralmesh structure modeling associated with twopaths toward the input code on PHITS what wasdone via .ele and .node files generated by TetGen
program and the other was done via .bdf file
generated by ANSYS Fluent.