FY2019 (2019.4‐2020.3) NSEC
Annual Report

Nuclear Science and Engineering Center
Nuclear Science Research Institute, Sector of Nuclear Science Research
Japan Atomic Energy Agency

September 2020

This report is issued by Japan Atomic Energy Agency.
Inquiries about availability and/or copyright of this report should be addressedto the Research Coordination and Promotion Office of the Nuclear Science andEngineering Center, Japan Atomic Energy Agency.
2‐4 Shirakata, Tokai‐mura, Naka‐gun, Ibaraki‐ken 319‐1195 Japan.
E‐mail: nsed‐web@jaea.go.jp© Japan Atomic Energy Agency, 2020

FY2019 NSEC Annual Report

Table of Contents

Preface........................................................................................... 1

R&D Highlights............................................................................... 2Group Activities.............................................................................. 9

Organization of NSEC··············································································································· 10

Nuclear Data and Reactor Engineering Division ······························································· 11
Nuclear Data Center
Research Group for Reactor Physics and Standard Nuclear Code System
Research Group for Nuclear Sensing
Fuels and Materials Engineering Division ·········································································· 14
Research Group for Corrosion Resistant Materials
Research Group for Radiation Materials Engineering
Research Group for High Temperature Science on Fuel Materials
Nuclear Chemistry Division ···································································································· 17
Research Group for Radiochemistry
Research Group for Analytical Chemistry
Environment and Radiation Sciences Division ·································································· 19
Research Group for Environmental Science
Research Group for Radiation Transport Analysis
LWR Key Technology Development Division ····································································· 21
Development Group for Thermal-Hydraulics Technology
Development Group for LWR Advanced Technology
Partitioning and Transmutation Technology Division ····················································· 23
Research Group for Partitioning
Research Group for Nuclear Transmutation System
Research Group for MA Transmutation Fuel Cycle

Publication List............................................................................. 26

FY2019 NSEC Annual Report

Preface

ENDO Akira
Director General, Nuclear Science and Engineering Center

The Nuclear Science and Engineering Center (NSEC) of the Japan Atomic Energy Agency (JAEA)
aims to conduct research and development to advance the science and technology that supports
the use of nuclear energy and radiation. This annual report provides research highlights and an
overview of the research groups’ activities in the NSEC for Fiscal Year 2019. We hope this annual
report will increase your understanding of the NSEC.
The use of nuclear energy and radiation is supported by the underlying basic science and various
technologies that link science and engineering. As such, we conduct fundamental research toelucidate various phenomena involving atomic nuclei, radiation, and radioactive materials using
our innovative techniques for measurement and analysis. Based on modeling of the observed
phenomena, we develop computer simulation codes and databases for predicting the behavior
of energetic particles, heat and fluid in a reactor core, performance of nuclear fuel and reactor
structural materials, properties and functions of radioactive materials related to their physicaland chemical states, migration behavior of radionuclides in the environment, and the effects ofradiation on the human body.
Through such knowledge and technologies, the NSEC contributes to solving various issues. Since
the accident at the TEPCO Fukushima Daiichi Nuclear Power Plant, we have focused on researchand development that contributes to (1) the accident response (promoting facility
decommissioning and environmental restoration), (2) improvement of light water reactors’safety performance, and (3) steady implementation of the treatment and disposal of radioactive
waste. Additionally, we disseminate our innovative technologies to resolve challenges in various
fields, such as industry, environment and medicine.
In 2019, JAEA formulated a vision for the future, JAEA2050+, in order to identify our direction
moving forward. To realize JAEA2050+, the NSEC will serve as a leading center for researchcollaboration and use our research and development capabilities to contribute to advances inscience and technology. We seek your understanding, support, and encouragement in our
research and development activities.

September 2020
1

FY2019 NSEC R&D Highlight

FY2019 NSEC R&D Highlights
The following 6 highlights are selected among various outcomes of the R&D
activities accomplished by the NSEC’s 6 divisions in FY2019.
 Nuclear Data and Reactor Engineering Division:“Development of Photonuclear Data Library for International
Contribution”
 Fuels and Materials Engineering Division:“Analysis for the Mechanism of Accelerated Corrosion on Low Alloy Steelin Air/solution Alternating Condition”
 Nuclear Chemistry Division:“External Exposure Dose Estimation by Electron Spin ResonanceTechnique for Wild Japanese Macaque Captured in Fukushima
Prefecture”
 Environment and Radiation Sciences Division:“Warning System for Aviation Exposure to Solar Energetic Particles(WASAVIES)” LWR Key Technology Development Division:“Fission Product Chemistry Database ECUME for LWR Severe Accidents”
 Partitioning and Transmutation Technology Division:“New Experimental Data Obtained to Validate Nuclear Data for ADS”

2

FY2019 NSEC R&D Highlight

Development of Photonuclear Data Library for International Contribution
IWAMOTO Nobuyuki
Nuclear Data Center
Photonuclear reaction is the phenomenon whichhappens when a nucleus is irradiated with highenergy gamma-rays. Photonuclear data are basic
ones not only for scientific researches but also forapplication fields. However, a large discrepancy ispresent between experimental data measured by thegroups of the Lawrence Livermore National
Laboratory in USA and the Saclay Nuclear ResearchCenter in France, both of which led photonuclear
researches in the 1960s to 80s. The discrepancy
makes a big disadvantage on practical aspects suchas the increase in the amount of radioactive waste
due to a large uncertainty of inventory estimation.
Therefore, the improvement of reliability ofphotonuclear data has been an overriding priority.
The International Atomic Energy Agency (IAEA)
started a coordinated research project (CRP) todevelop a photonuclear data library in 2016, and theresearchers of 15 countries participated. The present
work was done within the framework of CRP.
From
extensive
application
viewpoints,
photonuclear data are required to cover wide
gamma-ray energy and nuclide ranges. These
requirements cannot be satisfied only by
experiments. A nuclear reaction model is helpful for
fixing the matter. We used up-to-date knowledge oftheoretical reaction models and nuclear structure
data. In the evaluation of photonuclear data, the key
physical quantity is photon strength function, which
represents the absorption and emission strengths ofgamma-rays from nuclei. By analyzing experimental
data in various gamma-ray energies and nuclides, wefound out an optimum form of the photon strength
function. This made photonuclear data calculated by
the theoretical reaction models more reliable.
For the evaluation, we adopted the data measured
by a research group of Romania, Norway, Russia andJapan in the CRP at the NewSUBARU facility in Japan,
together with existing ones. The NewSUBARU
experiments were devised to obtain accurate crosssections with a laser Compton scattering gamma-ray
beam and a neutron detector with a flat detection
efficiency. The use of these apparatuses gets rid of
the primary factors of the discrepancy seen in thedata of the above two groups.
Evaluations of 140 nuclides (e.g., structural andmedium-heavy nuclides, and actinides) were
performed in the gamma-ray energy range of 1 to200 MeV. We obtained the photonuclear data which
well reproduce the experimental data. In particular,
the neutron emission cross sections were carefully

improved in the giant dipole resonance region (10 to
20 MeV), where the cross sections are large. This
improvement leads to the increase of practicality to
many fields. The IAEA photonuclear data library 2019
includes the nuclear data of 219 nuclides fromdeuterium to Plutonium-241. Here, new 140 nuclides
and existing 7 nuclides were provided from JAEA1).
This library will be available from the website of IAEA
Nuclear Data Services: https://www-nds.iaea.org/.
Figure 1 shows the comparisons of one- andtwo-neutron emission cross sections evaluated forLanthanum-139 (139La) with the data of NewSUBARU(circles), together with those of Saclay center(squares and triangles). The present results are ingood agreement with the data of NewSUBARU. It isfound that the data of Saclay center are lower thanthe present cross sections. It is inferred that theamount of undetected neutrons is large and thediscrimination accuracy of neutron multiplicity is low.
It is expected that the photonuclear data with an
improved reliability largely contribute to the
reduction in the amount of radioactive waste inelectron accelerator facilities, and optimization of
gamma-ray irradiation to human body on radiation
therapy, in addition to contributing to the scientificresearches.
Reference
1) T. Kawano et al., Nuclear Data Sheets, 163, 109-162(2020).

Fig.1 Comparisons of (a) one-neutron and (b)two-neutron emission cross sections evaluated for139
La with the data of NewSUBARU and Saclay
center3

FY2019 NSEC R&D Highlight

Analysis for the Mechanism of Accelerated Corrosion on Low Alloy Steel in
Air/solution Alternating Condition
OTANI Kyohei, TSUKADA Takashi, UENO Fumiyoshi and KATO Chiaki
Research Group for Corrosion Resistant Materials

steel in the interface condition would be caused by
the thin water film on the steel during the tests.

In the TEPCO Fukushima Daiichi Nuclear Power
Plant, it was observed that steel, the internalmaterial of the reactor, was exposed to air/solution
interface. It has been reported1) that steel at the
air/solution interface is exposed to a thin water film,
and the corrosion rate is accelerated by the water
film. In the present study, corrosion tests of carbon
steel simulating the air/solution interface wascarried out to clarify the mechanism of theaccelerated corrosion2).

The accelerated corrosion of carbon steel in theinterface condition would be caused by the thinwater film increasing mass transfer of dissolved
oxygen to the carbon steel surface during the tests.
Reference
1) T. Nishimura et al., Tetsu-to-Hagane, 81, 10791084, (1995). (in Japanese)2) K. Otani et al., Zairyo-to-Kankyo, 68, 205-211,(2019). (in Japanese)
3) A. Nishikata et al., J. Electrochem. Soc., 144,
1244-1252, (1997).

For the corrosion tests simulating the
air/solution interface, the carbon steel was rotatedand exposed to air and solution alternately(interface condition) using a rotating corrosion test
apparatus shown in Figure 1. The broken lines in
Figure 1 mean the water level of the test solution.
It was observed that a thin water film formed on
the surface of the carbon steel during the test while
it was exposed in the air. For comparison, corrosion
tests were also carried out under the condition thatthe specimens were always immersed in thesolution and rotated (immersion condition). 200
times diluted artificial seawater was used as thetest solution. The cross-section of the rust layer andthe mass change of the specimen were investigatedafter the tests.

Fig.1 Schematic representation of therotating corrosion test apparatus.

The cross-sectional SEM images show that therust layer formed on the steel after the tests in theinterface condition was thicker than that of theimmersion condition (Figure 2). The corrosion rateof carbon steel in the interface condition was morethan three times larger than that of the immersion
condition. It has been reported that the masstransfer of dissolved oxygen to the carbon steel
surface is accelerated in case of the carbon steel
covered by a thin water film and corrosion ofcarbon steel is accelerated by the acceleration ofoxygen reduction reaction (cathodic reaction)3).
This suggests that the accelerated corrosion of theFig.2 Cross-sectional SEM images of thespecimens tested in the interface condition
and in the immersion condition.

4

FY2019 NSEC R&D Highlight

External Exposure Dose Estimation by Electron Spin Resonance Technique forWild Japanese Macaque Captured in Fukushima Prefecture
OKA Toshitaka
Research Group for Analytical Chemistry
The release of the radioactive materials from theTEPCO Fukushima Daiichi Nuclear Power Plant (1F) tothe environment resulted in long-term low dose
(below 100 mGy) exposure to humans/animals. Fromthe viewpoint of biological effects and radiation safety
for individuals, the precise exposure dose estimation
is important.
Electron spin resonance (ESR) dosimetry is one ofthe powerful tools for exposure dose estimation. The
principle of it is to measure the CO2 radical, which was
induced in tooth enamel by the radiation and retainedwith a lifetime more than 107 years (Figure 1). The
relationship between exposure dose and CO2 radical
intensity, i.e., the dose response curve, enables us toestimate external exposure dose of the individuals.
This technique was commonly applied for the highdose exposure estimation (from a few hundred mGy
to a few Gy) for human, for example, exposure byatomic bomb, the nuclear plant accident in Chernobyl,
the nuclear industry workers, and so on. The
detection limit of the ESR dosimetry using humanteeth was reported to be 100 mGy-200 mGy. To apply
ESR dosimetry for the dose estimation due to 1F
accident, improvement of the detection limit of ESR
dosimetry is required. In the present study, we
attempted to improve the detection limit using teethof the Japanese macaque.
As reported in the previous study, organic materials
in dentine will interfere with ESR measurement of CO2
radical; it has been necessary to remove dentine andprepare dentine-free enamel samples1). However,
because of the small size of macaque teeth, it isdifficult to grind away with a dental bur. We
attempted to remove dentine based on the differencein the density between enamel and dentine. Molar
teeth of Japanese macaque were crushed into grainsusing a cryo-press, and enamel (density of 2.0-2.1
g/cm3) was separated from dentine (density of 2.8 3.0 g/cm3) by centrifugation.
To obtain the dose response curve, enamel samples
were irradiated by 60Co γ-ray up to 200 mGy (50, 100,
150, and 200 mGy) by cumulative irradiation. Before
the first irradiation and after each irradiation, samples
were measured by ESR to obtain a precise dose
response curve (Figure 2). From this dose response
curve, the detection limit is estimated to be less than
40 mGy.1) Wild Japanese macaques captured at Namie
town, Fukushima prefecture, about 15 km away from
1F were subjected to external dose estimation. We
found out that some of them show the estimatedexposure dose below 100 mGy.
The improved detection limit will enable us to
examine the relationship between external radiation
doses (at least 40 mGy) and their biological effects not
only on wild Japanese macaques but also on Japanesefield mice and raccoons in Fukushima prefecture. Oneof our goals is to assess the exposure radiation dosefor children in Fukushima prefecture.
Reference
1)

T. Oka et al., Radiation Measurements, 134, 106315-1-4 (2020).

Fig.1 CO2 radicals induced by radiation.
Measure the CO2 radical intensity byspectrometer.

ESR

Fig.2 Dose response curve for tooth enamel.
Purple and red bands represent the 90 % prediction
bands of each curve. This work can estimate thelower exposure dose than the previous work.

5

FY2019 NSEC R&D Highlight

Warning System for Aviation Exposure to Solar Energetic Particles (WASAVIES)
SATO Tatsuhiko1, KATAOKA Ryuho2, SHIOTA Daiko3, KUBO Yuki3, ISHII Mamoru3, YASUDA Hiroshi4,
MIYAKE Shoko5, PARK Inchun6, MIYOSHI Yoshizumi6
1 Research Group for Radiation Transport Analysis, 2 National Institute of Polar Research, 3 National
Institute of Information and Communications Technology, 4 Hiroshima University, 5 National Instituteof Technology, Ibaraki College, 6 Nagoya University

When a large solar flare occurs, the radiation doses
due to solar energetic particles (SEP) are occasionally
increased especially at flight altitudes, and they canbe a potential hazard to aircrews and passengers.
Thus, development of a system for nowcasting and/or
forecasting radiation doses due to SEP exposure is oneof the most important challenges in space weather
research. Collaboration with other research fields
such as nuclear physics and radiological protection is
the key issue in such development.
We therefore developed a physics-based model for
SEP dose estimation anywhere in the atmosphere anddesignated it WASAVIES: WArning System for AVIation
Exposure to Solar energetic particles1), under thecollaboration between several institutes in Japan. Thissystem is based on the combination of SEP transport
simulation models from the Sun to the ground level ofthe Earth. JAEA was responsible for developing the
SEP transport simulation model in the atmospherebased on PHITS and the automatic analysis program
by integrating all of the models.
The performance of WASAVIES is examined byanalyzing the four major solar particle events of the
21st century. The accuracy of the nowcast dataobtained by the model is well validated by the
reproducibility of the ground and satellite
observations. Figures 1 and 2 show the worldwide
dose rate map at 12 km and route-dose rate map
between Tokyo and New York, respectively, during thepeak of the solar particle event occurred on Jan. 20,
2005 drawn using WASAVIES. The complicatedlatitude, longitude, and altitude dependences of thedose rates such as the southern asymmetry can beseen in these figures, owing to the sophisticatedphysics models implemented in WASAVIES.
A web-interface of WASAVIES was also developed
and opened via public server of National Institute ofInformation and Communications Technology (NICT)(https://wasavies.nict.go.jp/) since Nov. 7th, 2019. The
radiation dose during a large solar flare calculated by
WASAVIES will be used as mandatory information foraviation operation management by International Civil
Aviation Organization (ICAO). This study is a successful
example of interdisciplinary research that has beenachieved through collaboration among researchers invarious fields such as space weather, solar physics,
upper atmosphere physics, nuclear physics, andradiation protection. This work was partially
supported by JSPS grant KAKENHI 15H05813.

Fig.1 Worldwide dose rate map at 12 km at the peak of thelargest solar particle event occurred on Jan 20, 2005 drawn
using WASAVIES

Fig.2 Route-dose rate map between Tokyo (NRT) and New

York (JFK) at the peak of the largest solar particle event
occurred on Jan 20, 2005 drawn using WASAVIES

Reference
1) T. Sato et al., Real-Time and Automatic Analysis Program
for WASAVIES: Warning System for Aviation Exposure to
Solar Energetic Particles, Space Weather, 16, 924-936(2018).

6

FY2019 NSEC R&D Highlight

Fission Product Chemistry Database ECUME for LWR Severe Accidents
MIWA Shuhei, NAKAJIMA Kunihisa, SUZUKI Chikashi, SUZUKI Eriko, LIU Jiazhan, Imoto Junpei,
KARASAWA Hidetoshi and OSAKA Masahiko
Development Group for LWR Advanced technology
Improvement of source term under LWR severe
accidents (SAs) is of crucial importance both for theenhancement of LWR safety and thedecommissioning and dismantling of the TEPCO
Fukushima Daiichi Nuclear Power Plant (1F). One of
the main tools for the evaluation of source term is
an SA analysis code. Implementation of fission
product (FP) chemistry treatment to the SA analysis
code has been the effective and promising way forthe improvement of source term. This is because
the FP chemistry significantly influences all the FP
behaviors.
Thus, we have been conducting a fundamental
study for constructing the FP chemistry databasenamed “ECUME” (Effective Chemistry database offission products Under Multiphase rEaction)1).
ECUME consists of three kinds of datasets: CRK(dataset for Chemical Reaction Kinetics), EM(Elemental Model set) and TD (ThermoDynamic
dataset). ECUME version 1.1 has been developed inorder to contribute mainly to the evaluation of Cs
distribution in 1F. Namely, the following datasets
were developed for evaluation of the effects ofboron (BWR control material) on Cs chemistry andCs chemisorption onto stainless steel (SS) at upper
part of the reactor pressure vessel: CRK for thereaction of Cs-I-B-Mo-O-H system in gas phase, EM
for Cs chemisorption onto SS caused by the hightemperature reaction between Cs and Fe, Si, andTD for CsBO2 vapor and solid Cs2Si4O9 and CsFeSiO4.
ECUME is the first database for Cs-I-B-Mo-Fe-Si-OH system in the world applicable to the evaluationof FP chemical reaction kinetics.
The constants in CRK have been prepared by a
combination of an ab-initio calculation andliterature review. A simulation calculation of Cs-I-BMo-O-H system with the presently prepared CRK ina simple thermal-hydraulic condition has revealed
the necessity of application of chemical reaction
kinetics instead of the chemical equilibria that has
been used so far (Figure 1)2).
The improved model for Cs chemisorption onto SS
in EM has successfully reproduced the effects ofvarious chemical conditions such as CsOH vapor
concentration in gas phase and Si content in SS,
which were not able to be evaluated by the existingmodel. The improved model shows that theexisting model may significantly over/underestimate Cs chemisorption rate according tovarious chemical conditions that should haveappeared reactors in Unit 1-3 at 1F2).
Thermodynamic data for CsBO2 vapor with highaccuracy were derived from the experiments,
which were also conducted by ourselves.
Thermodynamic data for solid Cs2Si4O9 and
CsFeSiO4 were prepared for the first time in theworld by the experiment and the DFT based
calculation, respectively.
ECUME version 1.1 was successfully constructed
for the evaluation of Cs distribution in 1F. In
addition, ECUME version 1.1 includes the datasets
for the evaluation of source term in PWR SA suchas CRK for the reaction of Ru-N-O-H system in gas
phase. In the future, ECUME will be expanded formore accurate evaluation of FP behaviors under
the LWR SA. Thus, it can be expected to provide thefundamental solution for the issues towards theenhancement of LWR safety and the 1F
decommissioning and dismantling work.
Reference
1) Development Group for LWR Advanced technology, JAEAData/code 2019-017 (2020).
2) S. Miwa et al., Mech. Eng. J., 7(3), 19-00537, (2020).

Fig.1 Effect of application of chemical reaction
kinetics on amount of Cs and I species (nEq/nCRK).

7

FY2019 NSEC R&D Highlight

New Experimental Data Obtained to Validate Nuclear Data for ADS
OIZUMI Akito, FUKUSHIMA Masahiro and NISHIHARA Kenji
Research Group for Nuclear Transmutation System
A fast neutron system dedicated to transmutation(accelerator-driven system: ADS) has been
investigated to reduce the environmental burden ofhigh-level radioactive waste (HLW). ADS is capable ofconverting partitioned long-lived nuclides with strong
radiotoxicity into stable or short-lived nuclides byfission reaction with neutrons. The top candidate for
ADS coolant is lead bismuth, which is chemicallystable and highly safe. However, Japan has noexperience with the use of lead bismuth as a nuclear
reactor coolant, and the characteristics of the nuclear
reaction (nuclear-reaction cross section) of lead havenot been sufficiently verified. Hence, in this study, the
new experimental data were obtained to validate thenuclear-reaction cross section of lead in fast neutron
cores using a critical assembly in the United States.
In ADS, fast neutrons generated by the spallation
reaction of lead-bismuth target are gradually
moderated by nuclear reaction with lead-bismuth
coolant, leading to fission after being absorbed tolong-lived nuclides. Fast neutrons generated by thefission are also used for the next fission reaction
through a similar moderation process (fission chain
reaction). Thus, to correctly predict the neutronmediated fission chain reaction in ADS, it is importantto accurately evaluate the nuclear-reaction crosssection of lead that affects neutron moderation in the
coolant. Because moderation of fast neutrons exhibits
different tendencies for different types of fuel,verification in several kinds of fuel is effective andreliable.
To verify the cross section of lead, influence ofremoving (voiding) the lead from an experimental
core on fission chain reaction is measured. The
influence is called “lead-void-reactivity worth”. By
voiding lead, neutrons are less moderated and keep
at high speeds. Such neutrons tend to cause more
fission in a core with particular fuel, or to escape fromone core into another one. This different tendency
among the fuel characteristics results in accurately
measurable value, i.e., criticality (reactivity) of thecore and is worth to verify the cross section of lead.
The two experimental cores with different uranium(U) isotope ratios, a highly-enriched uranium(HEU)/lead-experimental core rich in 235U and a lowenriched uranium (LEU)/lead-experimental core richin 238U, had been constructed in this experimental
series so far. Recently, a new measurement was
conducted by using a plutonium (Pu) /leadexperimental core in the same way as theexperiments using U1).

In the Pu fuel, neutrons moderated by leadgenerally have a higher probability of fission thanunmoderated fast neutrons. Therefore, the removing
lead from the Pu/lead experimental core decreases
the amounts of moderated neutrons by escaping fromthe core and then the fission chain reaction becomesless likely to occur. This resulted in a negative leadvoid-reactivity worth (Figure 1). These measurements
were compared with the calculation values using
nuclear-reaction cross section data (nuclear data)
developed in Japan (JENDL-4.0) and the United States(ENDF/B-VIII.0). As a result, the calculation results
using ENDF/B-VIII.0 well reproduced the experimental
ones, whereas that using JENDL-4.0 overestimatedthem by almost 6 cents in absolute value. Further
analysis of the gap between both calculations using
JENDL-4.0 and ENDF/B-VIII.0 indicated that thefundamental cause was due to the difference in the
nuclear data of one of Pu isotope, 239Pu, and not thatof lead.
By this study, the experimental data using Pu wereadded to a series of experiments for reliable
validation of the nuclear-reaction cross sections oflead. The research group of Japan and the UnitedStates will continue the cooperation to advance theresearch and development on transmutation
technology by expanding experimental data forvalidating the nuclear-reaction cross section.
This research was conducted as part of acollaboration with the Los Alamos National
Laboratory in the United States.
Reference
1) M. Fukushima, J. Goda, A. Oizumi et al., Nuclear Scienceand Engineering, 194(2), pp.138-153 (2020).
Lead void
reactivity worth (cents)

20
10
0

Experiment
JENDL-4.0
ENDF/B-VIII.0

-10
-20
-30
-40

Pu/Lead(New)HEU/Lead

LEU/Lead

Fig.1 Comparison of experimental and calculated
lead-void-reactivity worth

8

FY2019 NSEC Group Activity

FY2019 NSEC Group Activities
The NSEC of JAEA consists of 15 Groups.

9

FY2019 NSEC Annual Report

Organization of NSEC in FY 2019（as of March 2020）

URL of Organization of NSEC from April, 2020 (FY2020) : https://nsec.jaea.go.jp/organization/en_index.html
10

FY2019 NSEC Group Activity

Nuclear Data Center
Measurements of 237Np and243
Am Cross Sections**

The mission of Nuclear Data Center is to provide
reliable nuclear data which are required invarious applications such as nuclear reactors,
accelerators, medical use of radiations, and so on.
To achieve that, we engage in research works on
nuclear data measurement, nuclear theories,
and nuclear data evaluation related to nuclear
reaction and structure, collaborating with
nuclear data researchers and organizations inJapan as well as in the world. The evaluatednuclear data have been compiled into databases
called JENDL and are available from our website
http://wwwndc.jaea.go.jp.

Neutron cross sections of 237Np and 243Am havebeen measured by activation and time of flight(TOF) methods, respectively. These nuclides aresome of the main components of nuclear wastes
in spent fuels and accurate nuclear data havebeen required.
Regarding 237Np, the thermal capture crosssection and the resonance integral have beenobtained from the irradiated samples using Gd
filers instead of usual Cd ones, which enable us
to remove effects of low-energy resonanceexisted in 237Np leading to reliable estimation3).
The capture and total cross sections of 243Am
have been measured using ANNRI facility at
J-PARC4). The intensive pulsed neutron source of
MLF of J-PARC enables measurement of crosssections with small amounts of samples which is
crucial in use of minor actinide targets such as
Np and Am. The final results were obtained forneutron energies from 10 meV to 100 eV andfrom 4 meV to 100 eV for capture and total crosssections, respectively.

JENDL/ImPACT-2018*

To provide reliable data for the conceptual
design of transmutation system of long-lived
fission products (LLFPs) using accelerators thatwas carried out under a project of the ImPACT
Program in Japan, a JENDL special purpose file
JENDL/ImPACT-20181) was developed andreleased in August of 2019. With refining thetheoretical models based on the newly obtained
experimental data in the project, the nuclear
data evaluations for JENDL/ImPACT-2018 were
performed by applying the state-of-the-art
theoretical model codes taking account of thecurrently available experimental data. The filecontains cross sections of neutron and proton
induced reactions up to 200 MeV on 163
nuclides: LLFPs and their surrounding nuclei
which are expected to be produced duringtransmutations. These data were contributed to
the reliable estimation of amount of various
reaction products as well as neutron and protontransportation in the transmutation systems.

* The present study was sponsored by the
ImPACT Program of the Council for Science,
Technology and Innovation (Cabinet Office,
Government of Japan).
** A part of the present study was sponsored by
the Ministry of Education, Culture, Sports,
Science and Technology of Japan (MEXT).
Reference

1) S. Kunieda et al., J. Nucl. Sci. Technol, 56, 1073-1091(2019).
2) N. Furutachi et al., J. Nucl. Sci. Technol, 56, 412-424(2019).
3) S. Nakamura et al., J. Nucl. Sci. Technol, 56, 493-502(2019).
4) A. Kimura et al., J. Nucl. Sci. Technol, 56, 479-492(2019).

Hybrid Level Density Model*

Level density represents the average number oflevels of nuclei at certain excitation energies,
which play a crucial role on theoretical estimationof nuclear reaction cross sections. A new
phenomenological model, which shows good
agreements with experimental data for various
type of nuclei having from spherical shapes todeformed ones, has been proposed2). The model
consists of hybrid parametrizations of sphericaland deformed formulations and they are
optimized with existing experimental informationon the spherical and deformed nuclei incooperation
withmicroscopic
theoreticalpredictions of nuclear deformation depending on
excitation energies. This model was applied to theevaluations for JENDL/ImPACT-2018.

Contact (Group Leader):IWAMOTO Osamu
iwamoto.osamu@jaea.go.jp

11

FY2019 NSEC Group Activity

Research Group for Reactor Physics and Standard Nuclear Code System
Development of Inventory
Calculation Modules

The role of nuclear codes is increasing becauseof rapid advancement of computer technology. It
enables to evaluate in detail the energy andspatial distribution of neutrons and photons
emitted after fission reactions in a nuclear
reactor. Important key properties such as
criticality and radioisotope production rate etc.
can be deduced from these neutronics
calculations by these nuclear codes.
We are developing standard nuclear codes tosupport and advance nuclear energy andtechnology. The main codes are MVP and
FRENDY. We are also collaborating tightly with
the JENDL project and preparing many crosssection libraries. We prepared a multi-groupneutronactivation
cross-section
library(MAXS/AD-2017) and developed inventory
calculation modules for decommissioning of
nuclear power plants in 2019 JFY.

Radiological characterization is required as oneof the preparatory tasks for decommissioning of
nuclear power plants. We developed inventory
calculation modules7) using ORIGEN-S for reliableevaluationsofradioactivity
inventorycollaborated with the Japan Atomic Power
Company and the Institute of Applied Energy. As
shown in Figure 1, an activation cross-section
data library for ORIGEN-S is updated easily andeffectively based on a facility-specific neutron
spectrum and MAXS files by using these modules.
We can mitigate mistakes in data handlingaround ORIGEN-S calculations.
Reference

1) Y. Nagaya et.al., JAEA-Data/Code, 2016-018 (2017).
2) https://rpg.jaea.go.jp/main/en/program/(accessed 2020-05-22).
3) K. Tada et al., JAEA-Data/Code, 2018-014 (2019).
4) https://wwwndc.jaea.go.jp/ftpnd/jendl/jendl-ad-2017.
html (accessed 2020-05-22).
5) K. Okumura et al., JAEA-Conf 2015-003, p. 43 (2016).
6) I.C. Gauld et al., ORNL/TM-2005/39 (2006).
7) N. Matsuda et al., JAEA-Data/Code 2020-003 (2020).

MVP

MVP realizes fast and accurate Monte Carlosimulation of neutron and photon transport
processes. The version 3 of MVP1) was releasedin August 2018 and available from RIST in Japanand OECD/NEA data bank as NEA-1673
MVP/GMVP V.3. The cross section libraries forMVP3 can be downloaded from our group’s
home page.2)

FRENDY

Transport
calculation

code3).

FRENDY is a nuclear data processingItenables processing of nuclear data such as JENDL.
The first version of FRENDY treats the ENDF-6
format and generates the ACE files which are used
for Monte Carlo codes such as PHITS and MCNP.
FRENDY-1 was released in March 2019 as an open
source code from our group’s home page2).

MAXS2015

Cross-section
library

Library update toolTransport
calculation code

Activation crosssection library

Neutron spectrum

MAXS/AD-2017

Decay datalibrary

ORIGEN-S
Elements

JENDL Activation Cross Section File for Nuclear
Decommissioning 2017 (JENDL/AD-2017)4) was
released in 2018. MAXS/AD-2017 with the sameformat as MAXS-20155), which was produced
based on the nuclear data libraries JENDL-4.0
and
JEFF-3.0/A,
wasdevelopedfrom
JENDL/AD-2017 for activation calculations in
nuclear facility decommissioning. A simple code
to generate an ORIGEN-S library from
MAXS/AD-2017 was also produced. JPDR
activation analyses with ORIGEN-S6) and a librarygenerated from MAXS/AD-2017 demonstrated
that MAXS/AD-2017 has a performanceequivalent to the ORIGEN-S library in SCALE6.0.

Activity
calculation

History

Radioactivity

Fig. 1 Example of inventory calculation modules

Contact (Group Leader):KAWANISHI Tomohiro
kawanishi.tomohiro@jaea.go.jp
12

FY2019 NSEC Group Activity

Research Group for Nuclear Sensing
Neutron Resonance Transmission
Analysis

We are dedicated to the research and developmentof radiation measurement techniques and systems
and those applications. In particular, nondestructive analysis (NDA) that requires advanced
neutron measurement techniques has beendeveloped and could be an indispensable tool for
nuclear safeguards, nuclear security, nuclear waste
management and decommissioning. Developmentsof low-cost, accurate and practical NDA systems arealso needed for effective implementation. The
following are a part of our group activities in 2019.

Neutron cross sections show resonance structuresthat can be used in the identification andquantification of nuclides. Neutron ResonanceTransmission Analysis (NRTA) is based on theanalysis of the resonance structures and is one of
the most promising NDA techniques. In particular,
NRTA can be applied for highly radioactive
materials because the detector of NRTA is located
far away from the radioactive materials.
The specially designed large-volume LaBr3 detector
system for NRTA was developed and evaluated3).
The neutron energy spectra obtained by the LaBr3
detector system showed that prompt γ ray peaks
emitted from standard samples can be used toaccurately identify the nuclei. Moreover, the signalto-noise ratios of resonance peaks in the spectrum
were enhanced 1.5–2.5 times by using the LaBr3
detector system.
We also established the analytical techniques for
NRTA to handle complex nuclear material samples
such as spent nuclear fuel pellets4). It was
implemented in the resonance shape analysis code
and was validated by experiments at the time-offlight facility GELINA using a set of metallic natural
copper samples and pellets made of silver mixed
with uranium-oxide powder. The results of theexperiments reveal that sample properties can bederived even when ideal geometry conditions are
not fulfilled. The analytical techniques open
perspectives to apply NRTA as an absoluteanalytical NDA technique to determine theelemental and isotopic compositions of complex
nuclear materials.
This research was implemented under the subsidy
for nuclear security promotion of MEXT.

Fast Neutron Direct Interrogation

We have developed the Fast Neutron Direct
Interrogation (FNDI) that is an NDA technique fornuclear materials. FNDI is a kind of Differential DieAway Analysis (DDA). The conventional DDA uses
thermal neutrons for sample interrogation. By
contrast, FNDI utilizes fast neutrons forinterrogation to reduce the inﬂuence of sample
matrices. As a result, FNDI can measure a variety of
nuclear materials nondestructively and enable us
to rapidly and accurately measure a small amountof fissile materials in a nuclear waste drum. We
applied it in the accountancy of 1802 actual waste
drums generated in decommissioning of a nuclear
facility. A low-cost and transportable neutron
source has also been developed to improve thecapability of an NDA system1) (Figure 1). M. Kureta,
A. Ohzu and M. Komeda were awarded the MEXT
Minister Prizes for Science and Technology for theirwork on the implementation of the novel NDA
system by using the FNDI2).

NeutronsourceReference

1) M. Komeda and Y. Toh, J. Nucl. Sci. Technol., 56, 617-628(2019).
2) M. Kureta, A. Ohzu and M. Komeda, The Commendationfor Science and Technology by MEXT, April 9 (2019).
3) H. Tsuchiya et al., Nucl. Instr. Meth. A 932, 16-26 (2019).
4) F. Ma et al., J. Anal. At. Spectrom., 35, 478-488 (2020).

62cm

40cm

Fig. 1 Low-cost neutron apparatus. We havesuccessfully demonstrated the detection of
nuclear materials with the low-cost neutron
apparatus.

Contact (Group Leader):TOH Yosuke
toh.yosuke@jaea.go.jp
13

FY2019 NSEC Group Activity

Research Group for Corrosion Resistant Materials
and distance between Fe and cation, respectively.
As shown in these figures, for Zn, which had alarge adsorption potential, obvious increase inelectron density between adsorbed atom and Fe
at surface were observed. On the other hand, no
significant increase in electron density wasobserved for Na. For Mg, increase in the electron
density was shown in Figure 1, but there was large
negative electron density difference near Mg atom,that is, weak binding force. That was obviously
different from Zn, and seems to be anti-chemicalbonding. It was suggested that the dissolution
reaction of iron was suppressed by the formationof the Zn layer, and that lead suppression ofhydrogen permeation into iron. These results werein good agreement with experimental data. This
study is expected to contribute to clarifying thehydrogen embrittlement mechanism of structural
materials of nuclear facilities.
Fe
M(Adsorbed atom)

Our group studies the corrosion of materials
used in light water reactors, spent fuelreprocessing plants, ADS (Accelerator Driven
System). We mainly conduct corrosion tests in
non-radioactive environments and in radioactive
environments to elucidate the mechanisms ofcorrosion phenomena and prediction models forcorrosion. We also use computer science tounderstand and predict corrosion mechanisms inareas that are difficult to see due to theexperimental limitations.

Hydrogen Permeation
Mechanism into Iron simulated
by First-principles Calculation
Analyses1)

Hydrogen embrittlement is a phenomenon inwhich the strength of steel is reduced by thehydrogen absorbed in the steel. There aremicroscopic defects in structural materials in
nuclear reactors due to irradiation. These defects
have a possibility of capturing hydrogen and thencause hydrogen embrittlement. In order toobtain the basic mechanism of hydrogen
permeation
into
metal,
first-principles
calculations were conducted to acquire theadsorption potential of the metal cations (Na+,Mg2+, and Zn2+) in solution, Ead, and the electron
density difference between before and after
metal cation adsorption at the point ofzero-charge, ∆ρ, which were derived from theelectronic state around the iron surface. Ead wasderived using follow equation,
𝐸𝐸𝑎𝑎𝑎𝑎 = −Δ𝐺𝐺/𝑛𝑛𝑛𝑛
where G, n and F represent Gibbs free energy,
the number of reacted electrons, and Faraday
constant, respectively. ∆G represents thedifference in free energy before and after thereaction,
Δ𝐺𝐺 = 𝐺𝐺(Feslab + Mad )−{𝐺𝐺(Feslab ) + 𝐺𝐺(M n+ )}where M represents the investigated metal
species (= Na, Mg, Zn). ∆ρ was derived using
follow equation,Δ𝜌𝜌 = 𝜌𝜌FeSlab+M − (𝜌𝜌FeSlab + 𝜌𝜌M )where ρFeSlab+M, ρFeSlab, and ρM represent electron
density of the iron slab with metal cation
adsorption, that of the iron slab, and that of themetal cation, respectively. Fig. 1 shows a contour
plot of electron density difference aroundadsorbed atom at point of zero charge. Fig. 2
shows the electron density difference of eachcation as a function of relative position between
nearest Fe atom and cation; rFe-M / LFe-M, whererFe-M and LFe-M represent position from Fe atom

Bohr-30.01-0.01(1Bohr=5.3x10-11m)

Electron density difference / Bohr-3

Fig.1 Contour maps of electron density difference
around each adsorbed atom of (a) Na, (b) Mg and(c) Zn.
1

0

x10-2

0

Relative position of electron from the Fe atomrFe-M/LFe-M

1

Fig.2 Distribution of electron density difference
between the adsorbed atom and the nearest Fe
atom.
Reference
1) T. Igarashi et.al., ISIJ International, accepted.

Contact (Group Leader):KATO Chiaki
Kato.chiaki16@jaea.go.jp

14

FY2019 NSEC Group Activity

Research Group for Radiation Materials Engineering
We are conducting several researches related to
not only the material degradation mechanism
under radiation environment but also thedevelopment of novel analytical methods
expected to be applied to nuclear materials. As
one of the studies developing the novel
analytical methods, we just started to apply
Positron Annihilation Spectroscopy (PAS) for the
study of Room Temperature Ionic Liquids (RTILs),
which are expected to be applied for the
reprocessing of spent nuclear fuel. In addition,
we are also investigating the effects of theirradiation- defect motion on the microstructural
evolution by combining the experimental andmodeling techniques to improve the prediction
accuracy of the property changes in irradiatedmaterials for ensuring the integrity of nuclear
reactors.

properties in crystalline materials. By in situ
observation using electron microscopy, we
revealedafundamental
defect-motion
mechanism, i.e. trapping/detrapping by impurity
atoms, in pure iron. Based on the revealed
mechanism, we derived the analytical modelusing a random walk theory, and incorporated it
into a reaction rate theory. Figure 2 shows how
the evolution behavior of the irradiation-defectdensity depends on the impurity concentrationin pure iron. The decreasing behavior was in acloser accordance with the experimental datawith the impurity concentration CM = 10-5-10-4, as
experimentally deduced. This result suggeststhat the revealed motion mechanism is afundamental physical process under irradiation2).
Reference

1) T. Hirade, et al., ACTA PHYSICA POLONICA A, 137
109-112 (2020).
2) Y. Abe, et al., Philosophical Magazine, Vol. 100, pp.
110-125 (2020).

Application of the PAS for the
Study of RTILs.

Although RTILs are widely used, indirect methods
are often used for physical property evaluation in
the nano or sub-nano scale. Positronium (Ps),
which is a combination of positron and electron,can be a nano or sub-nano probe. Ps can form a
sub-nano bubble and localize there because of
its negative work function and the triplet Ps(ortho-Ps) lives longer in a larger Ps bubble. In
the usual molecular liquids, the expansion of Ps
bubbles at higher temperatures were observed
because of the smaller surface tension. In theprevious studies, the Ps bubble in RTIL’s showedsome new phenomena like GHz oscillation thatwas not observed in the usual molecular liquids
and it was suggested that the Ps bubble size canshow the size of the nano or sub-nano structurecomposed of the Coulomb force in RTIL’s. Hence,no increase of ortho-Ps lifetime at higher
temperatures was predicted. The temperaturedependence of the positron lifetime at thenear-surface and in the bulk of the RTIL wasmeasured by the beam that can inject positrons
from above the liquid surface at AIST(*) and theprediction was confirmed (Figure 1). It was also
found that the structure due to the Coulomb
force existing at the near-surface can remain
even at high temperatures 1).

Fig.1 Temperature dependence of ortho-Ps
lifetimes measured with positron energies of 2
keV (filled circles) and 12 keV (open circles).

Fig.2 Dependence of the defect-density evolution
on the impurity concentration CM as a function ofirradiation dose. Each symbol in the experimental
data corresponds to an individual run.

(*) AIST: National Institute of Advanced Industrial Scienceand Technology

Contact (Group Leader):YAMASHITA Shinichiro
yamashita.shinichiro@jaea.go.jp

In situ Observation of IrradiationDefect Motion and its Modeling

Motion behavior of irradiation defects is known
to affect the radiation-induced microstructural
evolution and the degradation of material

15

FY2019 NSEC Group Activity

Research Group for High Temperature Science on Fuel Materials
We treat issues on nuclear fuel materials forboth light water reactors (LWR) and advanced
reactors in the future. Experimental works on
uranium and non-radioactive materials arecarried out in the Research building No. 4, withvarious heating devices and analytical apparatus.
Those on transuranium elements (TRU: Pu andminor actinides) are performed at TRU-HITEC,
consisting of specially designed hot cells and a
glove box with a highly purified argon
atmosphere. We also take advantage ofcomputer science to understand or predict
phenomena concerning the fuel materials at hightemperatures and under the irradiation
conditions.

apposite modelling. We also demonstrated thesintering of (Np,Zr)N pellets with applying pore
former (organic polymer micro particles) tocontrol the porosity (Figure 2). These hot
experiments were carried out under the research
project “R&D on nitride fuel cycle for MA
transmutation to enhance safety and economy”
funded by the MEXT.
Reference

1) H. Shibata et.al., Development of Module for ADS
Nitride Fuel Performance Analysis, JAEA-Data/Code2019-023, March 2020.
2) Press release, https://www.jaea.go.jp/english/news/
press/2019/101801/ (accessed 2020-08-07)

FEMAXI Code and Nitride Fuel
Property Database

Our tool to predict behavior of the transmutation
fuels is the module for ADS (Accelerator Driven
System) nitride fuel performance analysis,
running on the computer code called FEMAXI.
We have continuously improved the module formore reliability. Details of the current models
and fuel materials properties in the module aredescribed in the JAEA-Data/Code report1).
For the practical analysis of the fuel behavior, thematerial property database developed with dataon the actual fuel materials containing TRU isessential. The web version of our “Nitride Fuel
Property Database” was opened in Oct. 2019with a press release2), and now any researchers
can access it. Figure 1 shows the databaseinterface. Users can see a graph as well as thedata source and the function formula bychoosing a composition of nitride.

Fig.1 Example of the web database interface.

Hot Experiments on TRU

Fig.2 Appearance of the sintered (Np,Zr)N pellet
and the cross sectional image.

To expand the database and the analysis module,
we performed a series of annealing experiments
on a (Pu,Cm,Zr)N nitride fuel pellet, in which
Frenkel defects and He atoms accumulated due
to alpha decay of 244Cm for two years. Data on
the dimensional recovery and the gas swellingcaused by gaseous He release were successfully
obtained as a function of temperature. These
data will be reflected to the module with

Contact (Group Leader):TAKANO Masahide
takano.masahide@jaea.go.jp
16

FY2019 NSEC Group Activity

Research Group for Radiochemistry
adsorbed on the silica gel plate were separately
measuredusing
photoluminescencemicrospectroscopy.
Thephotoluminescence
images of uranium and europium (Figure 2) clearlyshow different distributions from each other, anduranium is distributed near the center whereas
europium is distributed around the uranium
distribution. The larger-area distribution of
europium is caused because the uranyl ion ispreferentially adsorbed to silica gel over the
europium ion and the uranyl adsorption disturbs
the adsorption of europium ion.

Radiochemistry provides fundamental information
about the essential materials in developing nuclear
technology by identification of the chemical
reaction of radioactive materials by measurement
and chemical separation. We chemically resolve
various issues arisen from the nuclear industry by
developing new technique of measurement andcomputational method.

Chemical Reactivity of Nuclear Fuel

Estimating the long-term degradation of fuel debris
or the soundness of spent nuclear fuel in thegeological repository requires basic understandingof redox reactions taking place at the surface ofuranium (U) materials. Radiation-induced oxidative
dissolution of uranium dioxide (UO2) is one of themost important chemical processes of U driven by
the redox reactions. Thus, we have investigated theeffect of UO2 stoichiometry on the oxidative
dissolution of UO2 induced by hydrogen peroxide(H2O2) and γ-ray irradiation, in order to understandthe evolution of the reaction kinetics during thecourse of the surface oxidation1).
By comparing the reaction kinetics of H2O2 between
stoichiometric UO2.0 and hyper-stoichiometric
UO2.3, we observed a significant difference inreaction rate and U dissolution kinetics. The
stoichiometric UO2.0 reacted with H2O2 much fasterthan the hyper-stoichiometric UO2.3. The U
dissolution from UO2.0 was initially much lower
than that from UO2.3, but gradually increased as thesurface oxidation by H2O2 proceeded (Figure 1). The
γ-ray irradiation induced the U dissolution that is
analogous to the kinetics by the exposure to a low
concentration (0.2 mM) of H2O2. The exposure tohigher H2O2 concentrations caused lower U
dissolution and resulted in deviation from the U
dissolution behavior driven by the water radiolysis.

Reference

1) Y. Kumagai et al., Journal of Physical Chemistry C, 123,
9919-9925 (2019).
2) R. Kusaka et al., Journal of Nuclear Science andTechnology, 57, 1046-1050 (2020).

Fig.1 Change in the U dissolution kinetics due to the
H2O2 oxidation of UO2 (left) and schematic
representation of the surface oxidation process(right).

Adsorption and Transfer ofRadioactive Species on Solid
SurfaceRadioactive species in the environment transfer
while repeating sorption and desorption on thesurface of solid materials. Recently we havedeveloped an optical microscopic technique tostudy the transfer of radioactive species on a solid
surface, which requires a very small amount of aradioactive sample solution for the experiment2). In
this study, an aqueous solution (0.5 μL) dissolving
uranyl and europium ions was dropped on a dry
silica gel plate to spread the two ions on the platethrough the water flow caused by the capillaryeffect, and the distributions of the two ionsFig.2 Photoluminescence images of uranium andeuropium distributions formed on a silica gel plate.
This figure is adapted by permission of Informa UK Limited, trading as Taylor & Francis
Group, www.tandfonline.com on behalf of Atomic Energy Society of Japan. Application ofphotoluminescence microspectroscopy: a study on transfer of uranyl and europium ionson dry silica gel plate (Ref 2). Copyright 2020 © Atomic Energy Society of Japan.

Contact (Group Leader):WATANABE Masayuki
watanabe.masayuki@jaea.go.jp

17

FY2019 NSEC Group Activity

Research Group for Analytical Chemistry
ray Absorption Fine Structure (XAFS). It was foundthat U deposits initially form low electricalresistance amorphous compound as intermediate,
and they transfer to high electrical resistancecrystalline compound while reaction rate depends
on pH of the solution.

Accurate analyses of radioactive substances arefundamental technologies supporting the nuclear
technology. Control of the chemical state of theanalyte and removal of interference elements prior
to instrumental analysis are key techniques for thehigh precision chemical quantitative analysis.
Speciation analysis is necessary to understand the
behavior of radioactive elements such as actinides
whose chemical properties differ depending on thespecies. Our group is developing practical analyticalmethods for actinide and fission products based onstudies of elucidation of chemical reaction, ion
separation phenomena such as adsorption,
precipitation, aggregation, etc. It is engaged on
instrumental analyses such as electrochemical
method, microscopic analysis technology, etc.

Speciation of α Radioactive
Particles

Local speciation analysis for U in an alpharadioactive particle was tried based on micro
Raman spectroscopy. To confirm its applicability toheterogeneous samples, Raman measurement of
aged UO2 particles was performed (Figure 1a).
Mapping images with 1 µm width of Raman
measurement were analyzed. Strong Raman shift of
UO2 at 1148 cm-1 was obtained in the whole particle(Figure 1b). Raman shift of uranium peroxide at 828
cm-1 was strongly observed locally (Figure 1c). By
comparing the Raman spectrum measured at Spots
A and B, it is possible to clearly identify UO2 anduranium peroxide. Micro Raman mapping enables
local speciation analysis with spatial resolution of 1µm.

In the decommissioning of the TEPCO Fukushima
Daiichi Nuclear Power Plant (1F), there is concern
about internal exposure due to ingestion ofparticulate matter containing alpha radionuclide
into the body. Understanding their chemical
properties is important for predicting thoseparticulate formation and spreading behavior incontaminated workplaces.

Direct Quantitation Method Using
Laser Ablation-ICP-MS

Reference

1) S. Asai et al., Anal. Chem., 92, 3276 (2020).

To reduce exposure during analysis of highradiation dose samples, simplified quantitation
method for 135Cs in the spent Cs adsorbent at 1F
was developed1). It was examined that adsorbed Cs
was directly measured by ICP-MS without elution
and preparation of the solution sample. Crushingand subsequent coating with a nitrocellulose-based
curing agent provided a thin flat surface and thus
allowed for stable solid sampling during laser
ablation. The use of the 135Cs/137Cs ratio measured
by ICP-MS and 137Cs radioactivity obtained by
gamma spectrometry achieved simple and precise
quantitation of 135Cs, requiring only very small (<10mg) samples.

Fig.1 Local speciation by Raman spectroscopy ofaged UO2 particle. (a) Optical microscope image,(b, c) Raman mapping images, (d) Raman shift atspots A and B.

Electrochemical Study ofFormation of Actinide Colloidal
Particles

Redox of actinide ions in weakly acidic solution is acomplex reaction due to the formation of a
precipitate. We tried to elucidate their reaction
mechanism by electrochemical method andspectroscopy. Electric resistance of the electrodesurface covered with uranium deposit exhibit achange in chemical form was studied byelectrochemical impedance measurement and X-

Contact (Group Leader):KITATSUJI Yoshihiro

kitatsuji.yoshihiro@jaea.go.jp

18

FY2019 NSEC Group Activity

Research Group for Environmental Science(total 131I, 131I chemical species (I2, CH3I, andparticulate iodine), 134Cs, 137Cs, and 132Te) in the airand on the surface by using the simulation results.
This database was used for comprehensive dose
assessment coupled with behavioral patterns ofevacuees from the 1F accident by collaborating
research groups in the Japanese dose assessment
project2). The reproducibility of air concentration in
our simulation became higher especially for theregion of north of 1F. This area is important fordose estimation regarding the behavioral patternsof evacuees, and these improvements led to therefinement of dose estimation.

We are conducting research and development inorder to upgrade the assessment technology ofenvironmental radioactive materials, required forenvironmental impact assessment of various
radionuclide releases and environmental pollution
events. Computer models for simulations on the
behavior of radioactive materials in theatmospheric, terrestrial, and oceanic environments
are developed, and model validation andimprovement are carried out using measured dataaround nuclear facilities. Environmental samples
for model validation are obtained to evaluate
temporal and spatial distributions of radionuclides,
and the migration processes of radionuclides in theenvironment are elucidated by analysis of these
data. Our technology has been applied to analyze
the environmental behavior and impact ofradioactive materials discharged due to the TEPCO
Fukushima Daiichi Nuclear Power Plant (1F)
accident.

This work was supported by Research on the Health
Effects of Radiation (2017–2019) organized by
Ministry of the Environment, Japan.

Atmospheric Dispersion Simulation
Regarding the 1F Accident
We carried out source term estimations andatmospheric dispersion simulations to evaluate theenvironmental impact caused by the 1F accident
using the Worldwide version of System for
Prediction of Environmental Emergency Dose
Information (WSPEEDI). In the recent study, we
further refined the source term estimated in ourprevious study and improved the atmosphericdispersion simulation with an optimization method
using various measurements1). To apply thisanalysis to the local-scale atmospheric dispersion
simulations, the new optimization method withcombinationofensemble
meteorologicalcalculations and the Bayesian inference method
was developed (Figure 1). This optimization
improved not only the source term but also thewind field in meteorological calculations byselecting the optimum case from ensemble
members of meteorological calculations based oncomparison results between the dispersion
calculations and measurements of radionuclides.
As a result, the atmospheric dispersion simulation
successfully
reproduced
both
the
air
concentrations of 137Cs and 131I at monitoring
points and their surface depositions measured byairborne monitoring (Figure 2). The deposition
amount on the land decreased from 3.7 × 1015 Bq
by the previous study to 2.1 × 1015 Bq, which wasclose to the measured amount of 2.4 × 1015 Bq.

Fig.1 New optimization method

Fig.2 Deposition pattern of 137Cs
Reference

1) H. Terada et.al., Journal of Environmental Radioactivity,
213, 106104, (2020).
2) T. Ohba et al., Scientific Reports, 10, 3639, (2020).

Contact (Group Leader):NAGAI Haruyasu

We also constructed the database forspatiotemporal distribution of major radionuclides

nagai.haruyasu@jaea.go.jp

19

FY2019 NSEC Group Activity

Research Group for Radiation Transport Analysis
International Commission on RadiologicalProtection (ICRP) suggests new human models thatare constructed with a format of tetrahedral
structure. The new models can precisely depict skinand surface of small organs. So, we have developed
new Japanese adult models with the new format.
The posture can be easily changed in the newJapanese adult models (Figure 1). Thus, a user is toperform dosimetry study by taking account for an
exposure condition. These models are to bereleased in the near future.

Nowadays, a computer simulation technique that
can analyze radiation transport in a material is an
essential tool for research and development in thefield of nuclear and radiation sciences. We havedeveloped a radiation transport simulation code,
the Particle and Heavy Ion Transport code System(PHITS), and apply it to industrial, scientific, andmedical studies. PHITS has been upgraded to
improve its reliability and to expand areas to be
applied. In addition, we also conduct studies onradiological protection and radiation effects. Here,computational human models have beendeveloped for dosimetry studies and an experimenthas been carried out to study DNA damage fromlocalized exposure to an insoluble cesium (Cs)particle.

Upgrade of PHITSIn FY2019, we released PHITS versions 3.17 and3.20. The major upgraded features are as follows
for these versions.
/ Proton (E < 300 MeV) and carbon ion (E < 10
MeV/n) track structure mode has been
implemented in the recent versions of PHITS. A
user can analyze points where ionization andexcitation events might occur. This function isuseful for studies on DNA damage, medical
physics and so on.
/ A function has been implemented to read thestopping power of each material from the usersupplied table.
/ A function to read electro-magnetic field maps
written in xyz or r-z grid has been implemented.
This tool is useful for design of a beam line in an
accelerator and so on.
/ We have improved DCHAIN that is used to
calculate induced radioactivity. Several neutron
activation libraries and decay-data libraries havebeen developed based on the latest evaluatednuclear data for DCHAIN. In addition, statisticaluncertainties of the induced activities can beevaluated by DCHAIN. The new version of DCHAIN
is called as DCHAIN-PHITS and included in the
package of PHITS.

Fig.1 Japanese adult male computational modelwith the tetrahedral format in various
postures

Experiment for DNA Damage
during Exposure to an Insoluble Cs
Particle

Insoluble Cs microparticles with radioactivity havebeen detected around the TEPCO Fukushima
Daiichi Nuclear Power Plant after the accident in2011. While a soluble Cs particle is distributed overa whole body, an insoluble Cs particle can remain in
the respiratory system after inhalation. We haveconducted experimental studies to investigate DNA
damage in cultured cells from localized exposure by
an insoluble Cs particle2). In addition,
computational studies using PHITS were also
performed to obtain dose distribution around cells
where a Cs particle adheres. The results show that
localized exposure to a Cs particle would giveadvantageous (repair) to proximal cells as well as
disadvantageous (more damage) to distal cells.
Reference

1) PHITS home page, https://phits.jaea.go.jp/(accessed 2020-08-04).
2) Y. Matsuya et al, Sci. Rep. 9-9483, (2019).

Please access PHITS home page1), if you have aninterest in further information on the code.

New Japanese Computational
Models for Dosimetric Study

JAEA developed and has released Japanese adultcomputational models, JF-103 (female) and JM-103(male). These models are constructed with thevoxel (volume-pixel) format that consists of large
number of cuboids with the size in mm-order. The

Contact (Group Leader):
TAKAHASHI Fumiaki
takahashi.fumiaki@jaea.go.jp20

FY2019 NSEC Group Activity

Development Group for Thermal-Hydraulics Technology(so-called two-phase flow pattern) depends onsuperficial liquid and gas velocity1), and numericalresults reproduced this two-phase flow pattern.
TPFIT and JUPITER were released at PRODAS2). We
are continuously improving TPFIT and JUPITER toenhance the safety of the LWRs.

For the establishment of thermal-hydraulics
numerical simulation methods for multi-phase flow,
we are developing multi-phase CFD (computational
fluid dynamics) numerical simulation codes formassive computers, TPFIT and JUPITER,
measurement techniques to obtain detailed
thermal-hydraulics data and performing thermalhydraulics experiments to construct validation
databases. These advanced techniques are applied
to the research works for improving the safety of
the LWRs and considering the decommissioning
process of the TEPCO Fukushima Daiichi Nuclear
Power Plant.

Experimental Studies

We perform various experiments to validate thosesimulations and construct basic physical models. As
one of the experiments, we performed opticalmeasurement of aerosol particle capturing
behavior near the gas-liquid interface (Figure 2)3).
Aerosol particle capturing at the gas-liquid interface isutilized in water filtering industrially. The capturing is
also used in the filtered venting systems and pool

Multi-phase CFD codes

TPFIT is developed for two-phase flow in the
nuclear reactor. TPFIT uses compressible fluid
equations and can be applied to the numericalsimulation of two-phase flow in any system.
JUPITER can simulate melting and relocation
behavior without assumptions or simplification. A
chemical reaction such as a eutectic reaction andoxidation model can also be taken into account.
Besides, JUPITER can perform the massively parallel
simulation of multi-phase flow with more than two
hundred thousand cores, by adapting high-efficientparallel computing techniques.
As one of the examples of CFD codes, we performed
a numerical simulation of two-phase flow in a 4×4
bundle of fuel rods by JUPITER (Figure 1)1). The
diameter of the rods is 10 mm, and the pitch
between the rods is 13 mm. In this simulation,
superficial liquid velocity was 0.100 m/s, andsuperficial gas velocity was 0.034 (Case 1), 0.157(Case 2), and 0.781 (Case 3) m/s. Based on existingknowledge, the interface shape of two-phase flow

scrubbing in the nuclear reactor. We performed thisexperiment to understand the capturing
mechanism and validate the numerical simulation
results of TPFIT. By this experiment, we could
visualize aerosol particle behavior. Based on the
results, we concluded that an inertial impact ofaerosol particles to a droplet occurs as one of thephysical mechanisms of the aerosol particle
capturing.
0s
10 µs
20 µs
30 µs
40 µs
50 µs
60 µs
70 µs
90 µs

10 µm

1670 µs
Droplet286 µm

Fig.2 Composite image of continuous images
particles near upper part of the droplet
References

1) A. Ono et al., Mechanical Eng. J. 7(3), 19-00583 (2019).
2) PRODAS (PROgram and DAtabase retrieval System),https://prodas.jaea.go.jp/ (accessed 2020-09-10)
3) S. Uesawa and H. Yoshida, et al., Proceedings of the 27th
International Conference on Nuclear Engineering (ICONE27), ICONE27-1972 (2019).

Contact (Group Leader):YOSHIDA Hiroyuki
yoshida.hiroyuki@jaea.go.jp(a) Case 1 (b) Case 2 (c) Case 3
Fig.1 Numerical simulation of two-phase flow in
4×4 bundle

21

FY2019 NSEC Group Activity

Development Group for LWR Advanced Technology
This group was founded to conduct a research
program to improve light water reactor (LWR)
safety from a scientific point of view. Through this,the group wants to contribute to the advance of thesafety technology in LWR, and also accelerates thedecommissioning and dismantling of the TEPCO
Fukushima Daiichi Nuclear Power Plant (1F).
This group mainly conducts studies on fission
product (FP) behaviors under normal and accident
conditions and development of accident tolerant
fuel (ATF) cladding.

insert. The upper end of the test rod was connected
to a load cell. The lower end was connected to an
argon pressurizer to control internal pressure of thetest rod. The connected parts were sealed withepoxy. The test rod was pressurized with argon gas
up to 7 MPa. The test chamber was filled withsteam, and the test rod was heated up to the peaktemperature of 1200°C by 5°C/sec. The test rod was
kept at the peak temperature for the holding timeof 100 sec. The equivalent cladding reacted (ECR) to
the peak temperature of 1200°C and the holding
time of 100 sec was 15%. The heater was turned off
and simultaneously the water was fed from thewater feeder at the bottom of the test chamber.
When the test rod was quenched, the axial force of
540 N was applied to the test rod. The test rod did
not fail beyond the conditions corresponding to thecurrent LOCA criteria. It was demonstrated that
SiC/SiC cladding could keep fuel pellet inside thecladding even in beyond design-basis-accident
condition. After the above integral LOCA test, thetest rod was subjected to the axial tensile test atroom temperature. There was no difference inmaximum load between before and after the
integral LOCA tests. This indicates that themechanical strength of the SiC cladding was notdegraded by severe thermal and mechanical load
under the LOCA condition4).

Fission Product Behavior

We are constructing a database of FP chemistrynamed ECUME (Effective Chemistry database offission products Under Multiphase rEaction)1).
ECUME covers important phenomena revealed
after the 1F severe accident (SA). According to
TEPCO’s report of the investigation in the internal ofprimary containment vessel (PCV) of 1F unit 22), themeasured dose rate was 10 Gy/h at the pedestalarea, where most debris should exist, while it was
70-80 Gy/h in the vicinity. It was reported that
deposits were found in this vicinity, and these canbe believed as the source of higher dose rate. Fromthe information of condition and location, we
assumed that the suspected materials for thedeposits were the thermal insulation (i.e. calsil)
which covers the main steam piping. We presumed
that steam containing FPs such as Cs was leaked
from safety relief valves and blew off the calsil
which was adsorbing Cs. Therefore, as an initial step,
we investigated interaction temperature between
the calsil and Cs with effect of atmospheres. As theresults, it was suggested that some chemicalinteraction between calsil and Cs (i.e. CsOH)
occurred in the temperature range of 575-730°C,
regardless of Ar-5%H2 and Ar-20%H2O atmospheres.
Furthermore, the X-ray diffraction (XRD) analyses
have indicated that cesium aluminum silicate,
CsAlSiO4 was formed in the test (Figure 1)3).
Aluminum was present as an impurity or adduct in
the calsil.

Accident Tolerant Fuel (ATF)* This study was funded by Ministry of Economy, Trade and Industry(METI) of Japan.

Fig.1 XRD patterns of calsil mixed with CsOH•H2O in
Ar-5%H2*

References

For further improvement of safety of the existing
LWRs, ATFs are being developed. In Japanesedevelopment program, FeCrAl-ODS steel for boilingwater reactor (BWR) and SiC fiber reinforced SiC
matrix composite (SiC/SiC) for BWR and pressurizedwater reactor (PWR) were selected as major ATF
cladding concepts. Out of pile tests with the SiC/SiC
composite tubes were performed to investigate thebehavior in loss of coolant accident (LOCA). The test
rod consisted of the SiC/SiC cladding and alumina

1)

2)
3)
4)

Development Group for LWR Advanced technology,
JAEA-Data/code 2019-017 (2020).
Tokyo Electric Power Company, The 5th Progress Report
on 1F Accident, Attachment 4 (2017).
M. Rizaal et al., J. Nucl. Sci. Technol., to be in press.
K.Furumoto et al., Proc of TOPFUEL2019, (2019) 830-835.

Contact (Group Leader):NEMOTO Yoshiyuki
nemoto.yoshiyuki@jaea.go.jp

22

FY2019 NSEC Group Activity

Research Group for Partitioning
gases by incineration. This contributes to reducing
the volume of secondary solid waste.
We carried out continuous counter-current
experiments for steps (i) and (ii), and demonstrated
the validity of each step. For further development
of SELECT process, a continuous counter-current
experiment for step (iii) was performed using
HONTA as an extractant with mixer-settler
extractors installed in a hot-cell (Figure 2) at NUCEF(NUclear fuel Cycle safety Engineering research
Facility). A nitric acid containing Am, Cm, and REs
obtained by an experiment for step (ii) was used as
the feed. The experiment was conducted over a
cumulative operation time of 14 h. HONTA diluted
with n-dodecane extracted Am and Cm in the feed.
The recoveries of Am and Cm were 94.9% and78.9%, respectively, and these values were similar
to the predicted ones obtained by a simulation
code called PARC2,3). PARC indicated that therecoveries could be ≥99% by optimizing separation
conditions such as nitric acid concentration andflow rate. These results support the applicability of
HONTA as an extractant to separate Am and Cmfrom REs.
In addition to developing separation process withnovel extractants, other studies, such as to evaluate
radiolysis of the extractants and to improve the
PARC code, have been carried out.

Partitioning and transmutation has been proposed
as a strategy for managing high-level radioactive
waste (HLW) generated by reprocessing of spent
nuclear fuels via a hydrometallurgical method. HLW
consists of many elements of different
radiotoxicities and chemical properties. Thus, it isreasonable to separate the elements into groups
instead of treating them together from theviewpoint of increasing transmutation efficiency
and reducing disposal area.
To this end, our research group has beendeveloping several extractants and has investigatedtheir extraction properties. Recently, we proposeda novel hydrometallurgical process called SELECT(Solvent Extraction from Liquid waste using
Extractants of CHON-type for Transmutation) torecycle nuclear materials and separate actinides fortransmutation1).

A Demonstration Test of SELECT ina Hot-Cell

A conceptual flow sheet of SELECT process is shownin Figure 1. This process consists of the following
four steps: (i) recovery of U and Pu from dissolution
solution of spent nuclear fuels, (ii) recovery of Am,
Cm, and rare earth elements (REs) from HLW, (iii)
separation of Am and Cm from REs, and (iv)separation of Am and Cm. The extractants used inthis process consist of carbon, hydrogen, oxygen,and nitrogen, and thus can be decomposed into
Dissolution solution of spent nuclear fuelStep (i): U and Pu recovery
DEHBA

N

DEHDMPA

N
O

O

U, Pu

Step (ii): Recovery of Am, Cm, and REs
C12H25
C12H25NNO
C12H25
C12H25 TDdDGAOO

Fig. 2 Mixer-settler extractors used in thecontinuous counter-current experimentFPs otherthan REs

Reference

1) Y. Ban et al., Solvent Extra. Ion Exch., 37, 27-37, (2019).
2) Y. Ban et al., Solvent Extra. Ion Exch., 37, 489-499, (2019).
3) Y. Tsubata et al., JAEA-Data/Code, 2008-010, (2008).

Step (iii): Separation of Am and Cm from REs
C8H17

C8H17
N
C8H17
O

N
N

C8H17

O
O

C8H17
HONTA
N
C8H17

Step (iv): Separation of Am and Cm
N
O

N

N
O

ADAAM(EH)

REs

Am

Contact (Group Leader):BAN Yasutoshi

Cmban.yasutoshi@jaea.go.jp

Fig. 1 A conceptual flow sheet of SELECT process
and proposed extractants in each step23

FY2019 NSEC Group Activity

Research Group for Nuclear Transmutation System
by ignoring some of the neutron counts right after
the proton injection, but the error due to spatial
dependence still remains.
To overcome this problem, a new method, thelinear combination method (LCM), has been
proposed, which aims to mitigate the spatial
dependence by linear combination of neutron
counts obtained at multiple detectors 1) andprovides one unique estimation of sub-criticality. It
essentially reduces the error by the detector
position. Figure 1 shows an experimental result
conducted at Kyoto University Critical Assembly(KUCA). Figure 2 shows the core configuration of
the experiment. The result of the decay constant by
LCM has less dependence on the masking time
(range of ignored counts) while the results by theconventional method depend on both detector
position and the masking time.

Research Group for Nuclear Transmutation System
is developing Accelerator Driven System (ADS)
devoted to transmutation of Minor Actinide (MA)
into short-lived or stable nuclide. Present R&D level
on ADS is at maturing of conceptual design andtesting by small-scale equipment for eachcomponent and material. To improve ADS design,
we are developing analysis systems consisting ofparticle transport, thermal-hydraulics, material,and plant behavior. Moreover, we are developing
sub-critical monitoring techniques for safe andeffective operation of ADS.

New Method for Sub-Criticality
Measurement

Accurate sub-criticality measurement is a key issue
for operation of ADS whose core must be at a subcritical state. The pulsed neutron source (PNS)
method is one of the promising sub-criticality
measurement techniques. In this method, the subcriticality is estimated by measuring decay
constants of neutron counts after each pulse
injection of proton beam which generates
spallation neutrons at the center of the core. The
problem of this method is that the decay constants
are affected by detector positions and it can impose
an error on the sub-criticality measurement. For
example, neutron counts of a detector near thegeneration point of spallation neutrons seemingly
decay more rapidly than that in the peripheral
position because neutrons produced by proton
beam directly enter the detector without fissions.
The conventional PNS method mitigates this error

103
1.E+3
10
1.E+2

2
1

0.0

1.E+1
101

Neutron counts[-]

Combined neutron counts[-]

10
1.E+1

2.0
4.0
6.0
Time after pulse injection[msec]

1.E+0
100

Contact (Group Leader):NISHIHARA Kenjinishihara.kenji@jaea.go.jp
Polyethylene

1200

FC#3

1000
BF-3 #3
FC #1
FC #3

800
600

1400

0.0

HEU fuelwith lead plate

BF-3 #4
FC #2

1.0
2.0
3.0
Masiking time [msec]

FC#2

FC#1

4.0

HEU fuel

BF-3 #3

1200

1.E-1
10-1

1000

1.E-2
10-2

10-3
1.E-3
0.0

LCM

1) R. Katano, Nuclear Science and Engineering 193 (4), p.
431-439, (2019).
2) R. Katano et al., Nuclear Science and Engineering 193 (12),p. 1394-1402, (2019).

1400

Decay constant [s-1]

104
1.E+4

BF-3 #3
BF-3 #4
Conventional
FC #1
FC #2
FC #3

Decay constant [s-1]

Neutron counts[-]

Neutron counts[-]

105
1.E+5

Reference

2.0
4.0
6.0
Time
afterafter
pulse injection[msec]
Time
pulse [ms]D-T source

800
600

BF-3 #4

All detector

0.0

1.0

2.0

3.0

Masking time
time [msec]
Masking[ms]

Fig. 1 Results of the PNS experiment at KUCA 2)

4.0

Fig. 2 Core configuration of KUCA

Neutron counts from 5 detectors decay after proton pulse injection (top left). By the conventional method,
neutron counts are converted to decay constant unique to the ADS, but it problematically depends on detector
position and masking time (top right). In the new LCM method, 5 neutron counts are combined to one neutron
counts (bottom left) and a unique decay constant with less effect of masking time is obtained (bottom right)

24

FY2019 NSEC Group Activity

Research Group for MA Transmutation Fuel Cycle
sodalite waste. The results show that multistage
reductive extraction treatment is necessary to meet
the targets, and the amount of the salt transferredto the recycling process per day is only 2-3 % of themolten salt bath. On the other hand, the stage
number of the zeolite treatment is recommended
to be more than three from the aspect of quantityof glass-bonded sodalite wastes 1).

Feasibility study on transmutation system showsthat only 20 % of minor actinides (MAs) in the fuels
can be transmuted in one burning cycle of about 2
years. Reprocessing of the spent fuels is necessary
to transmute MAs remaining in the spent fuels.
Repeating fuel fabrication, transmutation, andreprocessing can transmute most of MAs coming to
the dedicated MA transmutation fuel cycle in the
double-strata fuel cycle concept. We have been
carrying out research and development of thetechnology on reprocessing of spent MA
transmutation fuels. One of our concerns is on
pyroprocessing technology, in which molten salts
and liquid metals are used as solvents; thistechnique is suitable for reprocessing spent MA
nitride fuels.

Table 1 Conditions of the electrorefining process.
Number of ADS
Spent MA nitride fuel/ ADS・cycle
Actinides in spent fuel/ ADS・cycle
Number of electrorefiner
Molten salt in electrorefiner
Actinides content in molten salt
Liquid Cd cathode in electrorefiner
Operating days

Material Balance Calculation on
the Electrorefining Process

We have proposed a flowsheet for theelectrorefining process of spent MA nitride fuels,
based on that designed for metal fuel treatment.
The flowsheet contains the salt recycling process tocontrol the contamination of fission products (FPs)in the MAs recovered by electrorefining. FPs areconstantly removed from the molten salt bath via
this process, which includes multistage reductive
extraction of actinides using molten salt/liquid Cdphases and zeolite treatment to absorb FP by ion
exchange or occlusion of FP chlorides. The saltloaded zeolite is to be immobilized in glass-bonded
sodalite for disposal in a geological repository.
Material balance calculation is useful to quantify
the scale of equipment needed to achieve thedesired outputs of the process and to examine theimpact of processing conditions. Such attempts
were made on the electrorefining process of spent
MA transmutation nitride fuels for the acceleratordriven system (ADS). The conditions of the process
are needed to meet the target recovery yield of MA(99.9 %) and the acceptable impurity level of rareearths (REs) fission products in the recoveredmaterial (RE/MA < 5 wt.%).
We examined the impact of the conditions in thesalt recycling process such as stage numbers of thecountercurrent reductive extraction and the zeolite
treatment on material balance including quantity ofthe secondary wastes. Table 1 shows the conditionsof the calculations. The composition of the spent
MA nitride fuel was determined by the latest burnup calculation for the initial fuel containing 5 wt.%
RE against MA. Distribution of the elements in eachstep was calculated based on the experimental datain literature. Table 2 shows the conditions of theprocess and the amounts of the glass-bonded

17789 kg
4217 kg
11000 kg
6 wt.%
200 kg200

Table 2 The effect of the stage numbers for eachstep on quantity of the glass-bonded sodalite
waste.
Salt
Glass
Stage number
transferred -bonded
to thesodalite
reductive
zeoliterecycling
waste
extraction treatment(kg/fuelprocess(kg/day)
cycle)
1
3
2
3
32
6680
3
3
22
5790
4
3
20
5660
5
3
19
5610
3
2
22
8040
3
4
22
5480
2
2
32
10020
2
4
32
5870
Reference

1) H. Tateno, T. Sato, Y. Tsubata, H. Hayashi, J. Nucl. Sci.
Technol., 57(3) 224-235 (2020).

Contact (Group Leader):
HAYASHI Hirokazu
hayashi.hirokazu55@jaea.go.jp25

FY2019 NSEC Publications

Publication list
* Works with underlined numbers were published before
FY2019 (not included in the list of FY2018 NSEC report).

Nuclear Data and Reactor Engineering Division
Nuclear Data Center
Papers1) Consistent description of light composite particle
emission in deuteron-induced reactions, S.
Nakayama, O. Iwamoto & Y. Watanabe, Phys. Rev.
C 100(4), 044603 (2019).
2) Spin-isospin properties of N = Z odd-odd nuclei
from a core+pn three-body model including core
excitations, F. Minato & Y. Tanimura, Eur. Phys. J.
A 56, 45 (2020).
3) Measurements of the Am-243 neutron capture
and total cross sections with ANNRI at J-PARC, A.
Kimura, S. Nakamura, K. Terada, T. Nakao, K.
Mizuyama, N. Iwamoto, O. Iwamoto, H. Harada,
T. Katabuchi, M. Igashira, T. Sano, Y. Takahashi,
C.H. Pyeon, S. Fukutani, T. Fujii, T. Yagi, K.
Takamiya & J.-I. Hori, J. Nucl. Sci. Tech. 56(6), 479(2019).
4) Measurements of thermal-neutron capture cross-section and resonance integral of neptunium237, S. Nakamura, F. Kitatani, A. Kimura, A.
Uehara & T. Fujii, J. Nucl. Sci. Tech. 56(6), 493(2019).
5) Measurements of thermal-neutron capture cross-section of Cesium-135 by applying mass
spectrometry, S. Nakamura, Y. Shibahara, A.
Kimura, O. Iwamoto, A. Uehara & T. Fujii, J. Nucl.
Sci. Tech. 57(4), 388 (2020).
6) Phenomenological level density model withhybrid parameterization of deformed andspherical state densities, N. Furutachi, F. Minato& O. Iwamoto, J. Nucl. Sci. Tech. 56(5), 412 (2019).
7) Statistical properties of thermal neutron capture
cross sections calculated with randomly
generated resonance parameters, N. Furutachi, F.
Minato & O. Iwamoto, Phys. Rev. C 100(1),014610 (2019).
8) JENDL/ImPACT-2018: a new nuclear data libraryfor innovative studies on transmutation of longlived fission products, S. Kunieda, N. Furutachi, F.
Minato, N. Iwamoto, O. Iwamoto, S. Nakayama,
S. Ebata, T. Yoshida, K. Nishihara, Y. Watanabe &K. Niita, J. Nucl. Sci. Tech. 56(12), 1073 (2019).

9) Reference database for photon strength
functions, S. Goriely, P. Dimitriou, M. Wiedeking,T. Belgya, R. Firestone, J. Kopecky, M. Krtička, V.
Plujko, R. Schwengner, S. Siem, H. Utsunomiya, S.
Hilaire, S. Péru, Y.S. Cho, D.M. Filipescu, N.
Iwamoto, T. Kawano, V. Varlamov & R. Xu, Eur.
Phys. J. A 55, 172 (2019).
10) Neutron capture cross-section measurement
and resolved resonance analysis of Np-237, G.
Rovira, T. Katabuchi, K. Tosaka, S. Matsuura, K.
Terada, O. Iwamoto, A. Kimura, S. Nakamura, N.
Iwamoto, M. Segawa & M. Maeda, J. Nucl. Sci.
Tech. 57(1), 24 (2020).
11) IAEA photonuclear data library 2019, T. Kawano,
Y.S. Cho, P. Dimitriou, D. Filipescu, N. Iwamoto, V.
Plujko, X. Tao, H. Utsunomiya, V. Varlamov, R. Xu,
R. Capote, I. Gheorghe, O. Gorbachenko, Y.L. Jin,
T. Renstrøm, M. Sin, K. Stopani, Y. Tian, G.M.
Tveten, J.M. Wang, T. Belgya, R. Firestone, S.
Goriely, J. Kopecky, M.Krtička, R. Schwengner, S.
Siem & M. Wiedeking, Nucl. Data Sheets 163,109 (2020).
12) Enhancement of element production by
incomplete fusion reaction with weakly bounddeuteron, H. Wang, H. Otsu, N. Chiga, S. Kawase,
S. Takeuchi, T. Sumikama, S. Koyama, H. Sakurai,
Y. Watanabe, S. Nakayama, D.S. Ahn, H. Baba, S.D.
Chen, K. Chikaato, M.L. Cortés, N. Fukuda, A.
Hirayama, R. Hosoda, T. Isobe, S. Kawakami, Y.
Kondo, S. Kubono, Y. Maeda, S. Masuoka, S.
Michimasa, I. Murray, R. Nakajima, T. Nakamura,
K. Nakano, M. Nishimura, T. Ozaki, A. Saito, T.
Saito, H. Sato, Y. Shimizu, S. Shimoura, P.-A.
Söderström, Y. Soudo, X.H. Sun, J. Suwa, D. Suzuki,
H. Suzuki, H. Takeda, M. Takechi, Y. Togano, T.
Tomai, H. Yamada, M. Yasuda & K. Yoshida,
Communications Phys. 2, 78 (2019).
13) Conceptual study on parasitic low-energy RI
beam production with in-flight separator BigRIPS
and the first stopping examination for highenergy RI beams in the parasitic gas cell, T.

26

FY2019 NSEC Publications
Sonoda, I. Katayama, M. Wada, H. Iimura, V.
Sonnenschein, S. Iimura, A. Takamine, M.
Rosenbusch, T.M. Kojima, D.S. Ahn, N. Fukuda, T.
Kubo, S. Nishimura, Y. Shimizu, H. Suzuki, H.
Takeda, M. Tanigaki, H. Tomita, K. Yoshida & H.
Ishiyama, Prog. Theor. Exp. Phys. 2019(11),
113D02 (2019).
14) Anomalous radioisotope production for 68ZnO
using polyethylene by accelerator neutrons, K.
Tsukada, Y. Nagai, S. Hashimoto, F. Minato, M.
Kawabata, Y. Hatsukawa, K. Hashimoto, S.
Watanabe, H. Saeki & S. Motoishi, J. the Phys. Soc.
Jpn 89(3), 034201 (2020).
15) Measurement of the 235U(n,f) cross section
relative to the 6Li(n,t) and 10B(n,α) standards
from thermal to 170 keV neutron energy range
at n_TOF, S. Amaducci, et al. (The n_TOF
Collaboration (H. Harada & A. Kimura)), Eur. Phys.
J. A 55, 120 (2019).

16) Measurement of the 70Ge(n,γ) cross section up
to 300 keV at the CERN n_TOF facility, A. Gawlik,
et al. (The n_TOF Collaboration (H. Harada & A.
Kimura)), Phys. Rev. C 100(4), 045804 (2019).
17) Fission program at n_TOF, L. Tassan-Got, et al.
(The n_TOF Collaboration (A. Kimura)), EPJ Web
of Conf. 211, 03006 (2019).
18) PR10-7 activation measurement for thermalneutron capture cross-section of Cesium-135, S.
Nakamura, A. Kimura, O. Iwamoto, Y. Shibahara,
A. Uehara & T. Fujii, KURNS PROGRESS REPORT
2018, 106 (2019).
19) Diagnostic (99Mo/99mTc) and therapeutic (67Cu)
radioisotopes produced by neutrons from
C,Be(d,n), Y. Nagai, K. Hashimoto, M. Kawabata,K. Tsukada, Y. Hatsukawa, F. Minato, Y. Sugo, H.
Saeki, Si. Motoishi, CERN Proc. 1 (Proc. the 15th
Int. Conf. on Nucl. Reaction Mechanism), 333(2019).

JAEA Reports
Symposium on Nuclear Data November 29-30,
2018, Tokyo Institute of Technology, Ookayama
Campus, Tokyo, Japan), 83 (2019).
4) Neutron capture reaction data measurement ofminor actinides in fast neutron energy region forstudy on nuclear transmutation system, T.
Katabuchi, O. Iwamoto, J. Hori, N. Iwamoto, A.
Kimura, S. Nakamura, Y. Shibahara & K. Terada,
JAEA-Conf 2019-001 (Proc. the 2018 Symposium
on Nuclear Data November 29-30, 2018, Tokyo
Institute of Technology, Ookayama Campus,
Tokyo, Japan), 193 (2019).
5) Survey of computational methods of crosssections for thermal neutron scattering byliquids, A. Ichihara, JAEA-Review 2019-046(2020).

1) Status and future plan of JENDL, O. Iwamoto,
JAEA-Conf 2019-001 (Proc. the 2018 Symposium
on Nuclear Data November 29-30, 2018, Tokyo
Institute of Technology, Ookayama Campus,
Tokyo, Japan), 7 (2019).
2) Gamow-teller strength distribution of nickel
isotopes with odd number of neutron, F. Minato,
JAEA-Conf 2019-001 (Proc. the 2018 Symposium
on Nuclear Data November 29-30, 2018, Tokyo
Institute of Technology, Ookayama Campus,
Tokyo, Japan), 173 (2019).
3) Measurement of the neutron capture crosssection of 237Np using ANNRI at MLF/J-PARC, G.
Rovira, T. Katabuchi, K. Tosaka, S. Matsuura, K.
Terada, O. Iwamoto, A. Kimura, S. Nakamura & N.
Iwamoto, JAEA-Conf 2019-001 (Proc. the 2018

Research Group for Reactor Physics and Standard Nuclear Code System
Papers1) Development of a handy criticality analysis tool
for fuel debris, K. Tada, Proc. ICONE27, 1151
(2019).
2) Investigation of the impact of the prediction
error of the burn-up code system SWAT4.0 on
neutronics calculation, K. Tada & T. Sakino, Proc.
ICNC 2019 (11th International Conference on
Nuclear Criticality safety) (2019).
3) Treatment of R-matrix limited formula in FRENDY,
K. Tada & S. Kunieda, Proc. RPHA19 (Reactor
PHysics Asia 2019), 229 (2019).
4) Implementation of random sampling for ACE

format cross sections using FRENDY andapplication to uncertainty reduction, R. Kondo, T.
Endo, A. Yamamoto & K. Tada, Proc. M&C 2019(2019).
5) TENDL-2017 benchmark test with iron shielding
experiment at QST/TIARA, S. Kwon, C. Konno, M.
Ohta, K. Ochiai, S. Sato & A. Kasugai, Fusion Eng.
Design 144, 209 (2019).
6) Problems of DPA cross-sections above 20 MeV in
FENDL-3.1d found in A-FNS neutronics analysis,
S. Kwon, C. Konno, M. Ohta & A. Kasugai, J. Nucl.
Sci. Tech. 57(3), 344 (2020).

27

FY2019 NSEC Publications
7) IRDFF-II: A new neutron metrology library, A.
Trkov, P.J. Griffin, S.P.Simakov, L.R.Greenwood,
K.I. Zolotarev, R. Capote, D.L. Aldama, V. Chechev,
C. Destouches, A.C. Kahler, C. Konno, M. Koštál,M. Majerle, E. Malambu, M. Ohta, V.G. Pronyaev,

V. Radulović, S. Sato, M. Schulc, E. Šimečková, I.
Vavtar, J. Wagemans, M. White & H. Yashima,
Nucl. Data Sheets 163, 1 (2020).
8) FRENDY Nuclear data processing system, K. Tada,
Nuclear Data Newsletter 67, 2 (2019).

JAEA Reports
30, 2018, Tokyo Institute of Technology,
Ookayama Campus, Tokyo, Japan), 167 (2019).
3) Development of Inventory Calculation Modules
using ORIGEN-S for Decommissioning, N.
Matsuda, C. Konno, T. Ikehara, K. Okumura & K.
Suyama, JAEA-Data/Code 2020-003 (2020) (inJapanese).

1) Nuclear data processing code FRENDY, K. Tada,
JAEA-Conf 2019-001 (Proc. the 2018 Symposium
on Nuclear Data November 29-30, 2018, Tokyo
Institute of Technology, Ookayama Campus,
Tokyo, Japan), 29 (2019).
2) Problems of TENDL-2015 official ACE files, C.
Konno & S. Kwon, JAEA-Conf 2019-001 (Proc. the2018 Symposium on Nuclear Data November 29-

Research Group for Nuclear Sensing
Papers1) Performance of large volume scintillation
detector equipped with specially-designed
shield for neutron resonance capture analysis, H.
Tsuchiya, M. Koizumi, F. Kitatani & H. Harada,
Nucl. Inst. & Methods in Phys. Res., A 932, 16(2019).
2) Conceptual study on a novel method for
detecting nuclear material using a neutron
source, M. Komeda & Y. Toh, Annals Nucl. Energy
135, 106993 (2020).
3) Simulation study on the design of nondestructive
measurement system using fast neutron directinterrogation method to nuclear materials in fueldebris, M. Maeda, K. Furutaka, M. Kureta, A.
Ohzu, M. Komeda & Y. Toh, J. Nucl. Sci. Tech.
56(7), 617 (2019).
4) Non-destructive analysis of samples with acomplex geometry by NRTA, F. Ma, S. Kopecky, G.
Alaerts, H. Harada, J. Heyse, F. Kitatani, G.
Noguere, C. Paradela, L. Šalamon, P.
Schillebeeckx, H. Tsuchiya & R. Wynants, J. Anal.
At. Spectrom. 35(3), 478 (2020).
5) Gamma-ray glow preceding downward
terrestrial gamma-ray flash, Y. Wada, T. Enoto, Y.
Nakamura, Y. Furuta, T. Yuasa, K. Nakazawa, T.
Morimoto, M. Sato, T. Matsumoto, D. Yonetoku,
T. Sawano, H. Sakai, M. Kamogawa, T. Ushio, K.
Makishima & H. Tsuchiya, Communications Phys.
2, 67 (2019).
6) Downward terrestrial gamma-Ray flash observedin a winter thunderstorm, Y. Wada, T. Enoto, K.
Nakazawa, Y. Furuta, T. Yuasa, Y. Nakamura, T.
Morimoto, T. Matsumoto, K. Makishima & H.
Tsuchiya, Phys. Rev. Lett. 123(6), 061103 (2019).

7) Neutron capture cross-section measurement
and resolved resonance analysis of Np-237, G.
Rovira, T. Katabuchi, K. Tosaka, S. Matsuura, K.
Terada, O. Iwamoto, A. Kimura, S. Nakamura, N.
Iwamoto, M. Segawa & M. Maeda, J. Nucl. Sci.
Tech. 57(1), 24 (2020).
8) Feasibility study of two-dimensional neutronresonance thermometry using molybdenum in
316 stainless-steel, T. Kai, K. Hiroi, Y. Su, M.
Segawa, T. Shinohara, Y. Matsumoto, J.D. Parker,
H. Hayashida & K. Oikawa, Mater. Res. Proc.
15(Neutron Radiography - WCNR-11), 149(2020).
9) Development of active neutron NDA System forradioactive nuclear materials, F. Kitatani, H.
Tsuchiya, A. Ohzu, M. Komeda, K. Furutaka, M.
Maeda & Y. Toh, Proc. INMM-60 (2018).
10) Performance evaluation of differential die-awaysystem in an integrated active neutron NDA
system for nuclear non-proliferation andnuclear security, A. Ohzu, M. Maeda, M.
Komeda & Y. Toh, Conf. Record 2018 IEEE
NSS/MIC (2019).
11) On-site measurement of nuclear material byusing the fast neutron direct interrogation
method, M. Komeda, ぶ ん せ き Bunseki
2019(10), 459 (2019) (in Japanese).
12) Gamma-ray observations at the coastal area ofJapan Sea in winter seasons, H. Tsuchiya, T.
Enoto, Y. Wada, Y. Furuta, K. Nakazawa, T. Yuasa,
D. Umemoto, K. Makishimai, & the GROWTH
collaboration, Proc. ICRC2019 (36th Int. Cosmic
Ray Conf.) (2019).
13) Sample shape effect on nuclear material28

FY2019 NSEC Publications
quantification with neutron resonancetransmission analysis, H. Tsuchiya, F. Ma, F.
Kitatani, C. Paradella, J. Heyse, S. Kopecky & P.
Schillebeeckx, Proc. 41st ESARDA Annual
Meeting, 374 (2019).

14) High-energy atmospheric phenomena initiatedby lightning, T. Enoto, Y. Wada & H. Tsuchiya, 日
本 物 理 学 会 誌 Butsuri 74(4), 192 (2019) (inJapanese).

JAEA Report
1) Development of active neutron NDA system, Y.
Toh, JAEA-Conf 2019-001 (Proc. the 2018
Symposium on Nuclear Data November 29-30,

2018, Tokyo Institute of Technology, Ookayama
Campus, Tokyo, Japan), 47 (2019).

Patents
1) Segawa M., Maeda M., Toh Y. & Kai T., “Method
and system for measuring temperature”,
Japanese Patent Application 2019-100962(2019.05.30)
2) Segawa M., Toh Y., Maeda M. & Nishinaka I.,“Method and system for analyzing alpha-ray

emitting nuclides”, Japanese Patent Application
2019-136227 (2019.07.24)
3) Komeda M. & Toh Y., “Nuclear material detection
device, Nuclear material detection method,
Sample analysis method”, Japanese Patent
Application 2020-006793 (2020.01.20)

Fuels and Materials Engineering Division
Research Group for Corrosion Resistant Materials
Paperscorrosion of stainless steels using cellular
automata, T. Igarashi, E. Irisawa, A. Komatsu, M.
Yamamoto & F. Ueno, Proc. EUROCORR 2019,
186704 (2019).
3) The accelerated corrosion of carbon steel in
air-solution alternating condition, K. Otani, T.
Tsukada, H. Terakado, K. Ebata & F. Ueno, Proc.
EUROCORR 2019, 176540 (2019).

1) Analysis for the mechanism of accelerated
corrosion on low alloy steel in air-solution
alternating condition, K. Otani, T. Tsukada & F.
Ueno, 材料と環境 Zairyo-to-Kankyo 68(8), 205(2019) (in Japanese)2) Modelling of intergranular corrosion using
cellular automata-II Numerical calculation
results and comparison of intergranular

Patent1) Ueda M., Hayashi Y., Kawamura K., Irisawa E.,
Komatsu A., Okubo N., et al., “Metal oxide thinfilm reduction sensor”, Japanese Patent
Application 2020-0062404 (2020.03.31)

Research Group for Radiation Materials Engineering
Papers(2020).
3) Influence of long-term thermal aging on SCC
initiation susceptibility of L-grade austenitic
stainless steel, K. Kondo, S. Aoki, Y. Fujimura, T.
Hirade, Y. Kaji & S. Yamashita, Proc. 2019 Environ.
Degradation of Mater. in Nucl. Power SystemsWater Reactors (2019).
4) Stability of γ’ precipitates in nickel based oxide
dispersion-strengthened superalloys under high-1) Alloy design for improvement of ductility andtoughness in magnesium alloy; First-principlescalculation approaches, T. Tsuru, J. Jpn Inst. Light
Metals 70(2), 73 (2020) (in Japanese).
2) Effects of one-dimensional migration of selfinterstitial atom clusters on the decreasing
behaviour of their number density in electronirradiated α-iron, Y. Abe, Y. Satoh, N. Hashimoto& S. Ohnuki, Philosophical Magazine 100(1), 110

29

FY2019 NSEC Publications
temperature and heavy irradiation Conditions, A.
Konno, N.H. Oono, S. Ukai, S. Kondo, O.
Hashitomi & A. Kimura, Mater. Trans. 60(11),2260 (2019).
5) FE-SEM observations of multiple nanohillocks on
SrTiO3 irradiated with swift heavy ions, A.
Kitamura, N. Ishikawa, K. Kondo, Y. Fujimura, S.
Yamamoto & T. Yamaki, Trans. The Mater. Res.
Soc. Jpn 44(3), 85 (2019).
6) Control of the size of etchable ion tracks in PVDF
– Irradiation in an oxygen atmosphere and withfullerene C60, A. Kitamura, T. Yamaki, Y. Yuri, H.
Koshikawa, S.-i. Sawada, T. Yuyama, A. Usui & A.
Chiba, Nucl. Inst. & Methods in Phys. Res., B 460,
254 (2019).
7) Anomalous solution softening by unique energybalance mediated by kink mechanism intungsten-rhenium alloys, T. Tsuru, M. Wakeda, T.
Suzudo, M. Itakura & S. Ogata, J. Applied Phys.
127, 025101 (2020).
8) Positronium in room temperature ionic liquids, T.
Hirade, AIP Conf. Proc. 2182, 030007 (2019).
9) Detector identification by waveform shapeanalysis for effective data acquisition:
Improvements in time resolution and count rate
for positron annihilation age–momentum
correlation measurement, T. Hirade, H. Ando, K.
Manabe & D. Ueda, Nucl. Inst. & Methods in Phys.
Res., A 931, 100 (2019).
10) TEM analysis of ion tracks and hillocks
produced by swift heavy ions of different
velocities in Y3Fe5O12, N. Ishikawa, T. Taguchi, A.
Kitamura, G. Szenes, M.E. Toimil-Molares & C.
Trautmann, J. Applied Phys. 127, 055902 (2020).
11) Degradation prediction of a γ-ray radiation
dosimeter using InGaP solar cells in a primarycontainment vessel of the Fukushima Daiichi
Nuclear Power Station, Y. Okuno, M. Yamaguchi,
N. Okubo & M. Imaizumi, J. Nucl. Sci. Tech. 57(4),457 (2020).
12) Irradiation influence on swelling and corrosion
behavior of ADS beam window materials, T91
Steels, in Lead Bismuth, N. Okubo & Y. Fujimura,
JPS Conf. Proc. 28 (Proc. 14th Int. WS on
Spallation Mater. Tech.), 071001 (2020).
13) Temperature dependence of ortho-Positronium
Annihilation in Room Temperature Ionic Liquids,
T. Hirade, K. Michishio, Y. Kobayashi & N. Oshima,
Acta Phys. Polonica A 137(2), 109 (2020).
14) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (1) Overview, Y. Kaji,
Y. Nemoto, T. Nagatake, H. Yoshida, M. Tojo, D.
Goto, S. Nishimura, H. Suzuki, M. Yamato & S.
Watanabe, Proc. ICONE27, 1343 (2019).

15) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (2) Fuel cladding
oxidation, Y. Nemoto, Y. Kaji, T. Kanazawa, K.
Nakashima & M. Tojo, Proc. ICONE27, 1345
(2019).
16) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (3) Thermalhydraulics experiment by using simulated 4×4
fuel bundle for constructing validation database,
T. Nagatake, M. Shibata, H. Yoshida, Y. Nemoto &Y. Kaji, Proc. ICONE27, 1642 (2019).
17) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (4) Investigation offuel loading effects in BWR spent fuel rack,
M.Tojo, T.Kanazawa, K.Nakashima, T.Iwamoto,
K.Kobayashi, D.Goto, Y. Nemoto & Y.Kaji, Proc.
ICONE27, 1477 (2019).
18) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (5) Investigation ofcooling effects of SFP spray and alternate water
injection using MAAP code, S. Nishimura, M.
Satake, Y. Nishi, Y. Nemoto & Y. Kaji, Proc. ICONE27,1603 (2019).
19) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (6) Analysis onoxidation behavior of fuel cladding tubes by the
SAMPSON code, Y. Morita, H. Suzuki, M. Naitoh, Y.
Nemoto & Y. Kaji, Proc. ICONE27, 1469 (2019).
20) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (7) Analysis on
effectiveness of spray cooling by the SAMPSON
Code, H. Suzuki, Y. Morita, M. Naitoh, Y. Nemoto,
T. Nagatake & Y. Kaji, Proc. ICONE27, 1475 (2019).
21) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (8) Safety Margin of
Spent Fuel in Large LOCA event by the Simple
Assessment Method, T. Someya, H. Chitose, S.
Watanabe, Y. Nemoto & Y. Kaji, Proc. ICONE27,
1153 (2019).
22) Development of cation and anion exchange
membranes for saline water concentration using
high-energy heavy-ion beams, S. Sawada, M.
Yasukawa, H. Koshikawa, A. Kitamura, M. Higa &T. Yamaki, Bull. Soc. Sea Water Sci. Jpn 73(4), 208(2019) (in Japanese).
23) Hydrogen desorption spectra from excess
vacancy-type defects enhanced by hydrogen intempered martensitic steel showing quasicleavage Fracture, K. Saito, T. Hirade & K. Takai,
Metal. Mater. Trans. A 50(11), 5091 (2019).
24) Mechanism of hardening and damage initiationin oxygen embrittlement of body-centred-cubic
niobium, P.-J. Yang, Q.-J. Li, T. Tsuru, S. Ogata, J.W. Zhang, H.-W. Sheng, Z.-W. Shan, G. Sha, W.-Z.

30

FY2019 NSEC Publications
Han, J. Li & E. Ma, Acta Mater. 168, 331 (2019).
25) First-principles modeling for dislocation motionof HEA alloys, T. Tsuru, M. Itakura, K. Yuge, Y.
Aoyagi, T. Shimokawa, M. Kubo & S. Ogata, Proc.

ISAM-4 (4th International Symposium on Atomistic
and Multiscale Modeling of Mechanics andMultiphysics), 1 (2019).

Patents
1) Okuno Y. & Okamoto T., “Radiation detector”,
Japanese Patent Application 2020-0062731(2020.03.31)
2) Ueda M., Hayashi Y., Kawamura K., Irisawa E.,

Komatsu A., Okubo N., et al., “Metal oxide thinfilm reduction sensor”, Japanese Patent
Application 2020-0062404 (2020.03.31)

Research Group for High Temperature Science on Fuel Materials
Papers1) Observation of simulated fuel debris usingsynchrotron radiation, Y. Yoneda, M. Harada & M.
Takano, Trans. the Mater. Res. Soc. Jpn 44(2), 61(2019).
2) Thermodynamic approach for determination offuel relocation condition in severe accident
progression, A. Itoh, Y. Kobayashi, A. Suzuki, T.
Sato, N. Shirasu, Y. Nagae & M. Kurata, J. Nucl.
Mater. 529, 151925 (2020).
3) High-temperature interaction between

zirconium and UO2, N. Shirasu, A. Suzuki, Y.
Nagae & M. Kurata, Proc. FDR2019 (Int. Topical
WS on Fukushima Decommissioning Res.), 1067
(2019).
4) Modelling of uranium dioxide interaction withzirconia at high temperature, A. Itoh, Y.
Kobayashi, T. Sato, N. Shirasu, Y. Nagae, M.
Kurata & A. Suzuki, Proc. FDR2019 (Int. Topical
WS on Fukushima Decommissioning Res.), 1072
(2019).

JAEA Report
1) Development of module for ADS nitride fuelperformance analysis, H. Shibata, H. Saito, H.

Hayashi & M. Takano, JAEA-Data/Code 2019-023(2020).

Nuclear Chemistry Division
Research Group for Radiochemistry
Papers1) Extractions and spectroscopic studies of various
metals with diglycolamide-type tridentate
ligands, Y. Sasaki, M. Saeki & K. Yoshizuka,
Solvent Extr. Res. Dev., Jpn 26(1), 21 (2019).
2) Impact of stoichiometry on the mechanism andkinetics of oxidative dissolution of UO2 inducedby H2O2 and γ-Irradiation, Y. Kumagai, A.B.
Fidalgo & M. Jonsson, J. Phys. Chem. C 123(15),9919 (2019).
3) Density functional theory (DFT)-based bonding
analysis correlates ligand field strength with Ru99 Mössbauer parameters of Ruthenium–
Nitrosyl complexes, M. Kaneko, A. Kato, S.
Nakashima & Y. Kitatsuji, Inorg. Chem. 58(20),14024 (2019).
4) γ-Radiation and H2O2 induced oxidative

dissolution of uranium(IV) oxide in aqueous
solution containing phthalic acid, Y. Kumagai & M.
Jonsson, Dalton Trans. 49(6), 1907 (2020).
5) Preliminary study on separation of Dy and Nd bymulti-step extraction using TDdDGA, Y. Sasaki, Y.
Ban, K. Morita, M. Matsumiya, R. Ono & H.
Shiroishi, Solvent Extr. Res. Dev., Jpn 27(1), 63(2020).
6) Separation of palladium by solvent extraction
withmethylamino-bis-N,N-dioctylacetamide
and direct electrodeposition from loaded
organic phase, M. Matsumiya, Y. Song, Y.
Tsuchida & Y. Sasaki, Separation Purification Tech.
234, 115841 (2020).
7) Optimization of sulfuric acid leaching of aVietnamese rare earth concentrate, N.T. Hung,31

FY2019 NSEC Publications
L.B. Thuan, T. C. Thanh, M. Watanabe, H. Nhuan,
D.V. Khoai, N.T. Thuy, N.V. Tung, N. Aoyagi, D.T.T.
Tra, N.T. Minh, M.K. Jha, J.-Y. Lee, & R.K. Jyothi,
Hydrometallurgy 191, 105195 (2020).
8) Spectroscopic studies of Mössbauer, infrared,
and laser-induced luminescence for classifying
rare-earth minerals enriched in iron-rich
deposits, N. Aoyagi, T.T. Nguyen, Y. Kumagai, T.V.
Nguyen, M. Nakada, Y. Segawa, H.T. Nguyen & T.
Ba Le, ACS Omega 5(13), 7096 (2020).

9) Effect of H2O2 concentration on oxidative
dissolution of UO2, Y. Kumagai, Biannual J. Jpn
Soc. Radiation Chem. 107, 77 (2019) (inJapanese).
10) Development of lanthanide and actinide
studies toward interface chemistry using
vibrationalsumfrequency
generation
spectroscopy, R. Kusaka, 放 射 化 学 Hosha
kagaku 41, 31 (2020) (in Japanese).

PatentGroup Element”, Japanese Patent 6558566(2019.07.26)

1) Suzuki T., Sasaki Y., Morita K., Matsumura T. &Shimogouchi T., “Method of collecting platinum

Research Group for Analytical Chemistry
PapersNitrosyl complexes, M. Kaneko, A. Kato, S.
Nakashima & Y. Kitatsuji, Inorg. Chem. 58(20),14024 (2019).
4) Inverse magnetic susceptibility fabrics in pelagic
sediment: Implications for magnetofossil
abundance and alignment, Y. Usui, T. Yamazaki, T.
Oka & Y. Kumagai, J. Geophys. Res.: Solid Earth124(11), 10672 (2019).
5) Direct quantitation of Cs-135 in spent Cs
adsorbent used for the decontamination ofradiocesium-containing water by laser ablationinductively coupled plasma mass spectrometry,
S. Asai, M. Ohata, Y. Hanzawa, T. Horita, T.
Yomogida & Y. Kitatsuji, Anal. Chem. 92(4), 3276
(2020).

1) External exposure dose estimation by electron
spin resonance technique for wild Japanesemacaque captured in Fukushima Prefecture, T.
Oka, A. Takahashi, K. Koarai, Y. Mitsuyasu, Y. Kino,
T. Sekine, Y. Shimizu, M. Chiba, T. Suzuki, K. Osaka,
K. Sasaki, Y. Urushihara, S. Endo, M. Suzuki, H.
Shinoda & M. Fukumoto, Rad. Meas. 134,
106315 (2020).
2) Thermodynamic study of the complexation of
humic acid by calorimetry, S. Kimuro, A.
Kirishima, Y. Kitatsuji, K. Miyakawa, D. Akiyama &N. Sato, J. Chem. Thermodyn. 132, 352 (2019).
3) Density functional theory (DFT)-based bonding
analysis correlates ligand field strength with Ru99 Mössbauer parameters of Ruthenium–

Environment and Radiation Sciences Division
Research Group for Environmental Science
Papers1) Large-eddy simulation studies for predicting
plume concentrations around nuclear facilities
using an overlapping technique, H. Nakayama &T. Takemi, Int. J. Environ. Pollution 64(1/2/3), 125(2018).
2) A new perspective on the Cs-137 retention
mechanism in surface soils during the early stage
after the Fukushima nuclear accident, J. Koarashi,
S. Nishimura, M. Atarashi-Andoh, K. Muto & T.
Matsunaga, Sci. Reports 9, 7034 (2019).
3) Development of regional downscaling capability
in STEAMER ocean prediction system based on

multi-nested ROMS model, Y. Kamidaira, H.
Kawamura, T. Kobayashi & Y. Uchiyama, J. Nucl.
Sci. Tech. 56(8), 752 (2019).
4) Characterizing vertical migration of Cs-137 inorganic layer and mineral soil in Japanese
forests: Four-year observation and model
analysis, K. Muto, M. Atarashi-Andoh, T.
Matsunaga & J. Koarashi, J. Environ.
Radioactivity 208-209, 106040 (2019).
5) Predictability of a short-term emergency
assessment system of the marine environmental
radioactivity, H. Kawamura, Y. Kamidaira & T.

32

FY2019 NSEC Publications
Kobayashi, J. Nucl. Sci. Tech. 57(4), 472 (2020).
6) Effect of dry-wet cycles on carbon dioxide
release from two different volcanic ash soils in a
Japanese temperate forest, H. Nagano, M.
Atarashi-Andoh & J. Koarashi, Soil Sci. Plant
Nutrition 65(5), 525 (2019).
7) Refinement of source term and atmosphericdispersion simulations of radionuclides during
the Fukushima Daiichi Nuclear Power Station
accident, H. Terada, H. Nagai, K. Tsuduki, A.
Furuno, M. Kadowaki & T. Kakefuda, J. Environ.
Radioactivity 213, 106104 (2020).
8) Processes affecting land-surface dynamics of I129 impacted by atmospheric I-129 releases
from a spent nuclear fuel reprocessing plant, M.
Ota, H. Terada, H. Hasegawa & H. Kakiuchi, Sci.
the Total Environ. 704, 135319 (2020).
9) Atmospheric-dispersion database system that
can immediately provide calculation results forvarious source term and meteorologicalconditions, H. Terada, H. Nagai, A. Tanaka, K.
Tsuduki & M. Kadowaki, J. Nucl. Sci. Tech. 57(6),745 (2020).
10) Marine radionuclide transport modelling:
Recent developments, problems and challenges,
R. Periáñez, R. Bezhenar, I. Brovchenko, C. Duffa,
M. Iosjpe, K.T. Jung, K.O. Kim, T. Kobayashi, L.
Liptak, A.Little, V. Maderich, P. McGinnitym B.I.
Min, H. Nies, I. Osvath, K.S. Suh & G. de With,
Environ. Modelling & Software 122, 104523(2019).
11) Repeatability and reproducibility ofmeasurements of low dissolved radiocesium
concentrations in freshwater using different preconcentration methods, M. Kurihara, T. Yasutaka,
T. Aono, N. Ashikawa, H. Ebina, T. Iijima, K.
Ishimaru, R. Kanai, Z. Karube, Y. Konnai, T. Kubota,
Y. Maehara, T. Maeyama, Y. Okizawa, H. Ota, S.
Otosaka, A. Sakaguchi, H. Tagomori, K. Taniguchi,
M. Tomita, H. Tsukada, S. Hayashi, S.y. Lee, S.
Miyazu, M. Shin, T. Nakanishi, T. Nishikiori, Y.
Onda, T. Shinano & H. Tsuji, J. Radioanal. Nucl.
Chem. 322(2), 477 (2019).
12) Carbon dioxide balance in early-successional

forests after forest fires in interior Alaska, M.
Ueyama, H. Iwata, H. Nagano, N. Tahara, C.
Iwama & Y. Harazono, Agri. Forest Meteor. 275,
196 (2019).
13) Development of field estimation technique andimprovement of environmental tritium behavior
Model, S. Yokoyama, T. Takahashi, M. Ota, H.
Kakiuchi, S. Sugihara, S. Hirao, N. Momoshima, T.
Tamari, N. Shima, M. Atarashi-Andoh, S. Fukutani,
S. Nakasoe, M. Furukawa, M. Tanaka & N. Akata,
Plasma Fusion Res. 14, 3405099 (2019).
14) Vertical distributions of Iodine-129 and iodide
in the Chukchi Sea and Bering Sea, K. Miwa, H.
Obata & T. Suzuki, J. Nucl. Sci. Tech. 57(5), 537(2020).
15) Seven-year temporal variation of Cesium-137
discharge inventory from the port of Fukushima
Dai-ichi Nuclear Power Plant: Continuous
monthly estimation of Cesium-137 discharge inthe period from April 2011 to June 2018, M.
Machida, S. Yamada, A. Iwata, S. Otosaka, T.
Kobayashi, M. Watanabe, H. Funasaka & T.
Morita, Trans. the Atomic Energy Soc. Jpn 18(4),226 (2019) (in Japanese).
16) Intercomparison of numerical atmosphericdispersion prediction models for emergency
response to emissions of radionuclides withlimited source information in the Fukushima Daiichi nuclear power plant accident, T. Iwasaki, T.T.
Sekiyama, T. Nakajima, A. Watanabe, Y. Suzuki, H.
Kondo, Yu Morino, H. Terada, H. Nagai, M.
Takigawa, H. Yamazawa, D. Quélo & A. Mathieu,
Atmospheric Environ. 214, 116830 (2019).
17) Wintertime grassland dynamics may influence
belowground biomass under climate change: amodel analysis, G. Katata, R. Grote, M. Mauder,
M.J. Zeeman & M. Ota, Biogeosci. 17(4), 1071
(2020).
18) Reconstruction of residents’ thyroid equivalentdoses from internal radionuclides after the
Fukushima Daiichi nuclear power station
accident, T. Ohba, T. Ishikawa, H. Nagai, S.
Tokonami, A. Hasegawa & G. Suzuki, Sci. Reports
10, 3639 (2020).

Book1) 2 - Estimation of environmental releases ofradioactive materials, M. Chino & H. Nagai,
Environmental Contamination from the
Fukushima Nuclear Disaster Dispersion,
Monitoring, Mitigation and Lessons Learned /Cambridge Univ. Press, 50 (2019).

2) 8 - Dispersion modelling of radioactive materials,
H. Nagai & H. Yamazawa, Environmental
Contamination from the Fukushima Nuclear
Disaster: Dispersion, Monitoring, Mitigation andLessons Learned / Cambridge Univ. Press, 230(2019).

33

FY2019 NSEC Publications

Research Group for Radiation Transport Analysis
Papersresistivity change of tungsten wire at cryogenic
temperature using high-energy proton
irradiation, Y. Iwamoto, M. Yoshida, H. Matsuda,
S. Meigo, D. Satoh, H. Yashima, A. Yabuuchi, A.
Kinomura & T. Shima, JPS Conf. Proc. 28, 061003(2020).
12) A simplified cluster analysis of electron track
structure for estimating complex DNA damage
Yields, Y. Matsuya, T. Nakano, T. Kai, N.
Shikazono, K. Akamatsu, Y. Yoshii & T. Sato, Int. J.
Molecular Sci. 21(5), 1701 (2020).
13) Analysis of the high-dose-range radioresistanceof prostate cancer cells, including cancer stem
cells, based on a stochastic model, R. Saga, Y.
Matsuya, R. Takahashi, K. Hasegawa, H. Date &Y. Hosokawa, J. Radiat. Res. 60(3), 298 (2019).
14) Cathodoluminescence induced in oxides byhigh-energy electrons: Effects of beam flux,
electron energy, and temperature, J.-M.
Costantini, T. Ogawa, AKM Saiful I. Bhuian & K.
Yasuda, J. Lumin. 208, 108 (2019).
15)
Computation
speedsandmemoryrequirements of mesh-type ICRP Referencecomputational phantoms in Geant4, MCNP6,
and PHITS, Y.S. Yeom, M.C. Han, C.s. Choi, H.g.
Han, B.h. Shin, T. Furuta & C.H. Kim, Health Phys.
116(5), 664 (2019).
16) PARaDIM: A PHITS-based Monte Carlo tool forinternal dosimetry with tetrahedral meshcomputational phantoms, L.M. Carter, T.M.
Crawford, T. Sato, T. Furuta, C.s. Choi, C.H. Kim,
J.L. Brown, W.E. Bolch, P.B. Zanzonico & J.S.
Lewis, J. Nucl. Med. 60(12), 1802 (2019).
17) Measurement of thermal neutron capture crosssection of Ga-71 with dual monitor foils andcovariance analysis, P. Panikkath, N. Otuka, Y.
Iwamoto & P. Mohanakrishnan, Eur. Phys. J. A
55(6), 91 (2020).
18) Neutron-induced damage simulations: Beyond
defect production cross-section, displacement
per atom and iron-based metrics, J.-Ch. Sublet,
I.P. Bondarenko, G. Bonny, J.L. Conlin, M.R.
Gilbert, L.R. Greenwood, P.J. Griffin, P.
Helgesson, Y. Iwamoto, V.A. Khryachkov, T.A.
Khromyleva, A.Yu. Konobeyev, N. Lazarev, L.
Luneville, F. Mota, C.J. Ortiz, D. Rochman, S.P.
Simakov, D. Simeone, H. Sjostrand, D. Terentyev& R. Vila, Eur. Phys. J. Plus 134(7), 350 (2019).
19) Impact of stellar superflares on planetary
habitability, Y.A. Yamashiki, H. Maehara, V.
Airapetian, Y. Notsu, T. Sato, S. Notsu, R. Kuroki,

1) Correction notice to: Nowcast and forecast ofgalactic cosmic ray (GCR) and solar energetic
particle (SEP) fluxes in magnetosphere andionosphere – Extension of WASAVIES to Earthorbit, T. Sato, R. Kataoka, D. Shiota, Y. Kubo, M.
Ishii, H. Yasuda, S. Miyake, Y. Miyoshi, H. Ueno
& A. Nagamatsu, J. Space Weather Space
Climate 9, A10 (2019).
2) Thick target neutron yields from 100- and 230MeV/nucleon helium ions bombarding water,
PMMA, and iron, P.-E. Tsai, L.H. Heilbronn, B.-L.
Lai, Y. Iwata, T. Murakami & R.-J. Sheu, Nucl. Inst.
& Methods in Phys. Res., B 449, 62 (2019).
3) Development of a function calculating internal
dose coefficients based on ICRP 2007
Recommendations, K. Manabe, K. Sato & F.
Takahashi, BIO Web of Conf. 14, 03011 (2019).
4) Estimating internal dose coefficients of shortlived radionuclides in accordance with ICRP
2007 recommendations, K. Manabe, K. Sato & F.
Takahashi, J. Nucl. Sci. Tech. 56(5), 385 (2019).
5) Intensity modulated radiation fields induce
protective effects and reduce importance of
dose-rate effects, Y. Matsuya, S.J. McMahon, M.
Ghita, Y. Yoshii, T. Sato, H. Date & K.M. Prise, Sci.
Reports 9, 9483 (2019).
6) DNA damage induction during localized chronic
exposure to an insoluble radioactive
microparticle, Y. Matsuya, Y. Satou, N. Hamada,
H. Date, M. Ishikawa & T. Sato, Sci. Reports 9,10365 (2019).
7) Dosimetric dependence of ocular structures on
eye size and shape for external radiation fields
of electrons, photons, and neutrons, T. Furuta,
D. El Basha, S. S R Iyer, C. M Correa Alfonso & W.
E Bolch, J. Radiol. Prot. 39(3), 825 (2019).
8) Modeling of yield estimation for DNA strand
breaks based on Monte Carlo simulations ofelectron track structure in liquid water, Y.
Matsuya, T. Kai, Y. Yoshii, Y. Yachi, S. Naijo, H.
Date & T. Sato, J. Applied Phys. 126(12), 124701(2019).
9) Depth profiles of energy deposition nearincident surface irradiated with swift heavy ions,T. Ogawa, N. Ishikawa & T. Kai, Nucl. Inst. &Methods in Phys. Res., B 461, 272 (2019).
10) Prediction of scintillation light yield based on
track-structure simulation, T. Ogawa, T. Sato & T.
Yamaki, Biannual J. Jpn Soc. Radiation Chem.
108, 11 (2019) (in Japanese).
11) Measurement of defect-induced electrical34

FY2019 NSEC Publications
K. Murashima, H. Sato, K. Namekata, T. Sasaki,
T.B. Scott, H. Bando, S. Nashimoto, F. Takagi, C.
Ling, D. Nogami & K. Shibata, Astrophys. J.
881(2), 114 (2019).
20) A biologically based mathematical model for
spontaneousandionizing
radiation
cataractogenesis, T. Sakashita, T. Sato & N.
Hamada, PLOS ONE 14(8), e0221579 (2019).
21) Dosimetric impact of a new computational
voxel phantom series for the Japanese atomic
bomb survivors: Pregnant Females, C. Paulbeck,
K. Griffin, C.s. Lee, H. Cullings, S.D. Egbert, S.
Funamoto, T. Sato, A. Endo, N. Hertel & W.E.
Bolch, Rad. Res. 191(5), 538 (2019).
22) Organ and detriment-weighted dose rate
coefficients for exposure to radionuclidecontaminatedsoilconsideringbodymorphometries that differ from reference
conditions: adults and children, C. Kofler, S.
Domal, D. Satoh, S. Dewji, K. Eckerman & W.E.
Bolch, Rad. Environ. Biophys. 58(4), 477 (2019).
23) Comparison of heavy-ion transport simulations:
Collision integral with pions and Δ resonances ina box, A. Ono, J. Xu, M. Colonna, P. Danielewicz,

C.M. Ko, M.B. Tsang, Y.-J. Wang, H. Wolter, Y.-X.
Zhang, L.-W. Chen, D. Cozma, H. Elfner, Z.-Q.
Feng, N. Ikeno, B.-A. Li, S. Mallik, Y. Nara, T.
Ogawa, A. Ohnishi, D. Oliinychenko, J. Su, T.s.
Song, F.-S. Zhang & Z. Zhang, Phys. Rev. C 100(4),044617 (2019).
24) Track structure study for energy dependency ofelectrons and X-rays on DNA double-strand
break induction, Y. Yachi, Y. Yoshii, Y. Matsuya, R.
Mori, J. Oikawa & H. Date, Sci. Reports 9, 17649(2019).
25) Measurement of displacement cross section of
structural materials utilized in the proton
accelerator facilities with the kinematic energy
above 400MeV, S. Meigo, H. Matsuda, Y.
Iwamoto, M. Yoshida, S. Hasegawa, F. Maekawa,
H. Iwamoto, T. Nakamoto, T. Ishida & S.
Makimura, JPS Conf. Proc. 28, 061004 (2020).
26) Anomalous radioisotope production for 68ZnO
using polyethylene by accelerator neutrons, K.
Tsukada, Y. Nagai, S. Hashimoto, F. Minato, M.
Kawabata, Y. Hatsukawa, K. Hashimoto, S.
Watanabe, H. Saeki & S. Motoishi, J. the Phys.
Soc. Jpn 89(3), 034201 (2020).

Books
Energy Soc. Jpn,) / Maruzen, 109 (2019) (inJapanese).
3) Estimation of observables, T. Ogawa & Y.
Iwamoto, 放射線遮蔽ハンドブック-応用編The handbook of radiation shielding -Advanced
Edition- / the Atomic Energy Soc. Jpn, 68 (2020)(in Japanese).

1) 5.1.2 Properties and characteristics of radiations,
F. Takahashi, 原子力のいまと明日 Nuclear
Energy’s now and future (ed. by the Atomic
Energy Soc. Jpn,) / Maruzen, 106 (2019) (inJapanese).
2) 5.1.3 Units of radiation (radioactivity), F.
Takahashi, 原 子 力 の い ま と 明 日 Nuclear
Energy’s now and future (ed. by the Atomic

LWR Key Technology Development Division
Development Group for Thermal-Hydraulics Technology
Papers1) Development of evaluation method for aerosol
particle deposition in a reactor building based on
CFD, N. Horiguchi, N. Miyahara, S. Uesawa, H.
Yoshida & M. Osaka, Proc. ICONE27, 2158 (2019).
2) Observation of aerosol particle behavior near
gas-liquid interface, S. Uesawa, N. Miyahara, N.
Horiguchi, H. Yoshida & M. Osaka, Proc. ICONE27,
1972 (2019).
3) Development of numerical simulation method toevaluate detailed thermal hydraulics aroundbeam window in ADS, S. Yamashita, T. Sugawara& H. Yoshida, Proc. ICONE27, 2019 (2019).
4) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (3) Thermalhydraulics experiment by using simulated 4×4
fuel bundle for constructing validation database,
T. Nagatake, M. Shibata, H. Yoshida, Y. Nemoto &Y. Kaji, Proc. ICONE27, 1642 (2019).
5) Numerical simulation study of two-phase flow in
4x4 simulated fuel bundle, A. Ono, S. Yamashita,
T. Suzuki & H. Yoshida, Mechanical Eng. J. 7(3),19-00583 (2020).

35

FY2019 NSEC Publications
6) Preliminary analysis of sodium experimental
apparatus PLANDTL-2 to develop evaluation
method for thermal hydraulics in reactor vesselof sodium-cooled fast reactor under decay heatremoval system operation conditions, A. Ono, M.
Tanaka, Y. Miyake, E. Hamase & T. Ezure, Proc.
ICONE27, 2318 (2019).
7) Study on the two-phase flow in simulated LWR
fuel bundle by CFD code, A. Ono, S. Yamashita, T.
Suzuki & H. Yoshida, Proc. NURETH-18 (18thInternational Topical Meeting on Nuclear
Reactor Thermal Hydraulics), 666 (2019).
8) Development of fission product chemistrydatabase ECUME for the LWR severe accident, S.
Miwa, N. Miyahara, K. Nakajima, S. Nishioka, E.
Suzuki, N. Horiguchi, J.-z. Liu, F. Miradji, J. Imoto,A. Mohamad, G. Takase, H. Karasawa & M. Osaka,
Proc. ICONE27, 1993 (2019).
9) Development of fission product chemistrydatabase ECUME for the LWR severe accident, S.
Miwa, K. Nakajima, N. Miyahara, S. Nishioka, E.
Suzuki, N. Horiguchi, J.z. Liu, F. Miradaiji, J. Imoto,A. Mohamad, G. Takase, H. Karasawa & M. Osaka,
Mechanical Eng. J. 7(3), 19-00537 (2020).

10) Fuel debris’ air cooling analysis using a lattice
Boltzmann method, N. Onodera, Y. Idomura, T.
Kawamura, S. Uesawa, S. Yamashita & H. Yoshida,
Proc. ICONE27, 2306 (2019).
11) Study on loss-of-cooling and loss-of-coolant
accidents in spent fuel pool, (1) Overview, Y. Kaji,
Y. Nemoto, T. Nagatake, H. Yoshida, M. Tojo, D.
Goto, S. Nishimura, H. Suzuki, M. Yamato & S.
Watanabe, Proc. ICONE27, 1343 (2019).
12) Study on boiling behavior on vertical heating
surface in pool boiling under higher pressure
condition, A. Ono, S. Uesawa, M. Shibata, H.
Yoshida & Y. Koizumi, Proc. 56th National Heat
Transfer Symposium, B215 (2019) (in Japanese).
13) Effect of flow condition on sea salts deposition
on boiling heat transfer surface, S. Uesawa, A.
Ono, Y. Koizumi, M. Shibata & H. Yoshida, Proc.
56th National Heat Transfer Symposium, B135
(2019) (in Japanese).
14) Sea water flow boiling heat transfer involving
sea salt deposition; Role of deposited sea salt, Y.
Koizumi, S. Uesawa, A. Ono, M. Shibata & H.
Yoshida, Proc. JSME Thermal Eng. Conf. 2019,
G122 (2019) (in Japanese).

Patent162820 (2019.09.06)

1) S. Uesawa, “Scrubbing method and system forpolluted gas”, Japanese Patent Application 2019-

Development Group for LWR Advanced Technology
Papers1) Evaporation of ruthenium from simulated
fission-produced alloy precipitates in a nuclear
fuel, J.Z. Liu, N. Miyahara, S. Miwa, M. Takano, A.
Hidaka & M. Osaka, J. Nucl. Mater. 527, 151819(2019).
2) Boron chemistry during transportation in thehigh temperature region of a boiling water
reactor under severe accident conditions, S.
Miwa, G. Takase, J. Imoto, S. Nishioka, N.
Miyahara & M. Osaka, J. Nucl. Sci. Tech. 57(3),291 (2020).
3) An experimental investigation of influencing
chemical factors on Cs-chemisorption behavior
onto stainless steel, S. Nishioka, K. Nakajima, E.
Suzuki & M. Osaka, J. Nucl. Sci. Tech. 56(11), 988(2019).
4) Cesium chemisorbed species onto stainless steel
surfaces: An atomistic scale study, F. Miradji, C.
Suzuki, K. Nakajima & M. Osaka, J. Phys. Chem.
Solids 136, 109168 (2020).
5) Development of fission product chemistrydatabase ECUME for the LWR severe accident, S.

Miwa, N. Miyahara, K. Nakajima, S. Nishioka, E.
Suzuki, N. Horiguchi, J.-z. Liu, F. Miradji, J. Imoto,A. Mohamad, G. Takase, H. Karasawa & M. Osaka,
Proc. ICONE27, 1993 (2019).
6) Development of fission product chemistrydatabase ECUME for the LWR severe accident, S.
Miwa, K. Nakajima, N. Miyahara, S. Nishioka, E.
Suzuki, N. Horiguchi, J.z. Liu, F. Miradaiji, J. Imoto,A. Mohamad, G. Takase, H. Karasawa & M. Osaka,
Mechanical Eng. J. 7(3), 19-00537 (2020).
7) Development of container using plasma sprayed
and laser treated material for sulfuric aciddecomposition of Ttermochemical watersplitting Iodine-sulfur Process, I. Ioka, Y. Kuriki, J.
Iwatsuki, S. Kubo, Y. Inagaki & N. Sakaba, Proc.
ICONE27, 2045 (2019).
8) Study of container using hybrid technique forsulfuric acid decomposition of thermochemical
water-splitting iodine-sulfur process, I. Ioka, J.
Iwatsuki, Y. Kuriki, D. Kawai, H. Yokota, S. Kubo, Y.
Inagaki & N. Sakaba, Mechanical Eng. J. 7(3), 1900377 (2020).

36

FY2019 NSEC Publications
9) Study on chemisorption model of cesiumhydroxide onto stainless steel type 304, K.
Nakajima, S. Nishioka, E. Suzuki & M. Osaka, Proc.
ICONE27, 2117 (2019).
10) Overview of accident-tolerant fuel R&D
program in Japan, S. Yamashita, I. Ioka, Y.
Nemoto, T. Kawanishi, M. Kurata, Y. Kaji, T.
Fukahori, T. Nozawa, D. Sato, N. Murakami, H.
Sato, T. Kondo, K. Sakamoto, K. Kusagaya, S. Ukai,
A. Kimura & A. Yamaji. Proc. GLOBAL/Top Fuel2019 (2019).
11) Low temperature heat capacity of Cs2Si4O9, E.
Suzuki, K. Nakajima, M. Osaka, Y. Ohishi, H.
Muta & K. Kurosaki, J. Nucl. Sci. Tech. 57(7), 852(2020).
12) Expansion of high temperature creep test data
for failure evaluation of BWR lower head insevere accident, Y. Yamaguchi, J. Katsuyama, Y.
Kaji, M. Osaka & Y.sh. Li, Proc. ICONE27, 1915
(2019).
13) Development of evaluation method for aerosol
particle deposition in a reactor building basedon CFD, N. Horiguchi, N. Miyahara, S. Uesawa, H.
Yoshida & M. Osaka, Proc. ICONE27, 2158
(2019).

14) Experimental investigation on boron oxidative
vaporization processes from zirconium-boron
and iron-boron alloys in a high temperature
steam atmosphere, J. Imoto, S. Miwa & M.
Osaka, Extended abst. FDR2019 (Int. Topical WS
on Fukushima Decommissioning Res.), 1062
(2019).
15) Experimental study on Cs chemisorption
behaviour onto stainless steel at around 873 K,
E. Suzuki, G. Takase, K. Nakajima, S. Nishioka, N.
Hashimoto, S. Isobe & M. Osaka, Extended abst.
FDR2019 (Int. Topical WS on Fukushima
Decommissioning Res.), 1068 (2019).
16) Chemical trapping of Sr vapor species by
Zircaloy cladding under a specific chemical
condition, A. Mohamad, K. Nakajima, S. Miwa,
M. Osaka, Y. Ohishi, H. Muta & K. Kurosaki,
Extended abst. FDR2019 (Int. Topical WS on
Fukushima Decommissioning Res.), 1065 (2019).
17) Development of Out of Pile Test for SiC Cladding
to Simulate DBA Conditions in PWRs, K.
Furumoto, D. Sato, S. Watanabe, T. Yumura, M.
Okamoto, S. Yamashita & T. Fukahori. Proc.
GLOBAL/Top Fuel 2019 (2019).

JAEA Report
1) Fission product chemistry database ECUME
version 1.1, Develop. G. for LWR Advanced

Technology, JAEA-Data/Code 2019-017 (2020).

Book1) Sub-sections 14.3.1 and 14.3.2 of “14 - Advancesin fuel chemistry during a severe accident:
Update after Fukushima Daiichi Nuclear Power

Station (FDNPS) accident”, M. Osaka, Advancesin Nuclear Fuel Chemistry / Elsevier (2020).

Partitioning and Transmutation Technology Division
Research Group for Partitioning
Papers1) Extraction of trivalent rare earths and minor
actinides from nitric acid with N,N,N’,N’tetradodecyldiglycolamide (TDdDGA) by using
mixer-settler extractors in a hot cell, Y. Ban, H.
Suzuki, S. Hotoku, T. Kawasaki, H. Sagawa, N.
Tsutsui & T. Matsumura, Solvent Extr. Ion Exch.
37(1), 27 (2019).
2) Effects of diluents on the separation of minor
actinides from lanthanides with tetradodecyl1,10-phenanthroline-2,9-diamide from Nitric
Acid Medium, N. Tsutsui, Y. Ban, H. Suzuki, M.

Nakase, S. Ito, Y. Inaba, T. Mmatsumura & K.
Takeshita, Analytical Sci. 36(2), 241 (2020).
3) Minor actinides separation by N,N,N’,N’,N’’,N’’hexaoctyl nitrilotriacetamide (HONTA) using
mixer-settler extractors in a hot cell, Y. Ban, H.
Suzuki, S. Hotoku, N. Tsutsui, Y. Tsubata & T.
Matsumura, Solvent Extr. Ion Exch. 37(7), 489(2019).
4)
Sorption
properties
ofaluminumhexacyanoferrate for platinum group elements,
R. Mishima, Y. Inaba, S. Tachioka, M. Harigai, S.

37

FY2019 NSEC Publications
Watanabe, J. Onoe, M. Nakase, T. Matsumura &K. Takeshita, Chem. Lett. 49(1), 83 (2020).
5) Direct temperature-swing extraction of rareearth elements from acidic solution using thehydrophobic interactions of poly (Nisopropylacrylamide) with diglycolamide-typed
ligands, K. Saga, H. Suzuki, T. Mastumura & T.
Tsukahara, Analytical Sci. 35(4), 461 (2020).
6) A review of separation processes proposed foradvanced fuel cycles based on technology
readiness level assessments, P. Baron, S.M.
Cornet, E.D. Collins, G. DeAngelis, G. Del Cul, Yu.
Fedorov, J.P. Glatz, V. Ignatiev, T. Inoue, A.
Khaperskaya, I.T. Kim, M. Kormilitsyn, T. Koyama,
J.D. Law, H.S. Lee, K. Minato, Y. Morita, J. Uhlíř, D.
Warin & R.J. Taylor, Prog. Nucl. Energy 117,
103091 (2019).
7) Zr Separation from high level liquid waste with anovel hydroxyacetoamide type extractant, K.
Morita, H. Suzuki, T. Matsumura, Y. Takahashi, T.
Omori, M. Kaneko & K. Asano, Proc.
GLOBAL/Top Fuel 2019 (2019).
8) Extraction separation of minor actinides andlanthanides
by
1,10-Phenanthroline-2,9diamide with phenyl group in nitric acid systems,
N. Tsutsui, M. Nakase, S. Ito, Y. Ban, T.
Matsumura & K. Takeshita, Proc. GLOBAL/Top
Fuel 2019 (2019).
9) Development of SELECT process for minor
actinides partitioning from high level waste, T.

Matsumura, 機 能 材 料 Function & materials
Jan. 2020 / 40(1), 60 (2020) (in Japanese).
10) Separation and recovery of raremetals using
the hydrophiric extraction with phase transfer
phenomena, T. Tsukahara, H. Suzuki, T.
Matsumura & K. Saga, 分離技術 Separation
process eng. 49(4), 29 (2019) (in Japanese).
11) Separation process of long-lived fission
products from high-level radioactive wastes, Y.
Takahashi, T. Omori, E. Murata, Y. Yamashita, M.
Kaneko, K. Asano, K. Morita, H. Suzuki & T.
Matsumura, Proc. GLOBAL/Top Fuel 2019 (2019).
12) Characterization of HONTA/SiO2-P adsorbent
for MA(III)/Ln(III) separation flow-sheet, M.
Takeuchi, S. Watanabe, Y. Sano, H. Kofuji, H.
Suzuki & T. Matsumura, Proc. GLOBAL/Top Fuel2019 (2019).
13) Influence of filling fraction of simulated highlevel waste on consistency in flexible waste
management system, A. Suzuki, Y. Endo, T.
Fukasawa, Y. Muroya & T. Matsumura, Proc.
GLOBAL/Top Fuel 2019 (2019).
14) No secondary waste recycle technology for
raremetals using the hydrophiric extraction withphase transfer phenomena, T. Tsukahara, K. Saga,
H. Suzuki & T. Matsumura, クリーンテクノロ
ジー Clean technology Dec. 2019 / 29(12), 4(2019) (in Japanese).

JAEA Report
1) Evaluation of decay heat value from high-levelliquid waste; Data for safety assessment ofpartitioning process, Y. Morita & Y. Tsubata, JAEAData/Code 2019-015 (2020).

Patents
1) Matsumura T., Sano Y., Tsubata Y., Koyama S.,
Yamamura T., Suzuki T., Takao K., Kani Y.,
Takahashi Y., Oyama S., Komamine S., Fujita R. &Ozawa M., “Process for treating insoluble
residue”, Japanese Patent 6515369 (2019.04.26)
2) Suzuki H., Matsumura T., Urabe S., Kurosawa T.,
Kawasaki T., Kunii S., Yoshida T., Narita K. &Tanaka M., “Method of extracting Actinoids
and/or Lanthanoids”, Japanese Patent 6521286(2019.05.10)
3) Suzuki H., Matsumura T., Kunii S. & Yoshida T.,“Scandium and/or Lanthanoid extraction

method”, Japanese Patent 6554745 (2019.07.19)
4) Suzuki T., Sasaki Y., Morita K., Matsumura T. &Shimogoucghi T., “Method of collecting platinumgroup element”, Japanese Patent 6558566(2019.07.26)
5) Suzuki H., Matsumura T., Kunii S. & Yoshida T.,“Extraction method for actinoid and/or rareearth”, Japanese Patent 6635259 (2019.12.27)
6) Matsumura T. & Suzuki H., “Extraction method
for americium”, Japanese Patent Application
2019-151070 (2019.08.21)

Research Group for Nuclear Transmutation System
Papers1) Application of linear combination method topulsed neutron source measurement at Kyoto

38

FY2019 NSEC Publications
process and validation, N. Watanabe, H.
Obayashi, T. Sugawara, T. Sasa, K. Nishihara & D.
Castelliti, Proc. NURETH-18 (18th International
Topical Meeting on Nuclear Reactor Thermal
Hydraulics), 248 (2019).
7) Design of accelerator-driven system consistentto partitioning technology, T. Sugawara, Y. Ban, R.
Katano, H. Tateno & K. Nishihara, Proc. Int. Conf.
the Management of Spent Fuel from Nuclear
Power Reactors (2019).
8) PR4-3 measurement of MA reaction rates under
sub-critical condition with spallation neutron
source in A-core of KUCA for ADS, A. Oizumi, M.
Fukushima, K. Tsujimoto, G. Chiba, M. Yamanaka,
T. Sano & C.H. Pyeon, KURNS PROGRESS REPORT
2018, 38 (2019).
9) CO3-7 sample worth measurements withsystematically changed mixing ratios of Lead andBismuth in A-core of KUCA for ADS, M.
Fukushima, A. Oizumi, M. Yamanaka & C.H.
Pyeon, KURNS PROGRESS REPORT 2018, 143(2019).
10) Current status of R&D and PIE program for ADS
material development in JAEA, S. Saito, N. Okubo,
H. Obayashi, T. Wan, T. Sugawara, T. Sasa & F.
Maekawa, JPS Conf. Proc. 28 (Proc. 14th Int. WS
on Spallation Mater. Tech.), 071003 (2020).

University critical assembly, R. Katano, M.
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2) Systematic measurements and analyses for leadvoid reactivity worth in a plutonium core andtwo uranium cores with different enrichments,
M. Fukushima, J. Goda, A. Oizumi, J. Bounds, T.
Cutler, T. Grove, D. Hayes, J. Hutchinson, G.
McKenzie, A. McSpaden, R. Sanchez, J. Walker &K. Tsujimoto, Nucl. Sci. Eng. 194(2), 138 (2020).
3) Area ratio method via linear combination of theneutron counts in pulsed neutron experiment., R.
Katano, Proc. ICONE27, 1327 (2019).
4) Measurement of prompt neutron decay constantwith spallation neutrons at Kyoto University
Critical Assembly using linear combination
method, R. Katano, M. Yamanaka & C.H. Pyeon,
J. Nucl. Sci. Tech. 57(2), 169 (2020).
5) First nuclear transmutation of Np-237 and Am241 by accelerator-driven system at Kyoto
University Critical Assembly, C.H. Pyeon, M.
Yamanaka, A. Oizumi, M. Fukushima, G. Chiba,
K. Watanabe, T. Endo, W.G. Van Rooijen, K.
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6) Immortal experimental loop at JAEA - Post-

JAEA Report
1) Development of prototype for TEF-T integral
control system of J-PARC, K. Sakai, H. Obayashi, S.

Saito, T. Sasa, T. Sugawara & A. Watanabe, JAEATechnology 2019-009 (2019) (in Japanese).

Research Group for MA Transmutation Fuel Cycle
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for minor actinide transmutation nitride fuel, H.
Tateno, T. Sato, Y. Tsubata & H. Hayashi, J. Nucl. Sci.
Tech. 57(3), 224 (2020).
2) Recent progress on development ofpyroprocessing technology for minor actinide
transmutation nitride fuels, H. Hayashi, T. Sato, H.
Tateno, S. Akashi, H. Shibata & Y. Tsubata, Proc.
GLOBAL/Top Fuel 2019 (2019).

Nuclear Science and Engineering Center
PapersJapanese).
2) Let's aim at AESJ without Ethics Committee, K.
Oba, J. the Atomic Soc. Jpn 61(4), 347 (2019) (inJapanese).

1) Enhancing emergency response in the field
based on analysis of workload distribution at
Fukushima Daiichi Nuclear Power Station, A.
Yoshizawa, K. Oba & M. Kitamura, Trans. theAtomic Energy Soc. Jpn 18(2), 55 (2019) (in39Editorial Board‐ Chief Editor:
TAKAHASHI Fumiaki‐ Editors:
MAEDA Makoto , KOMATSU Atsushi, OKA Toshitaka,
KADOWAKI Masanao, HORIGUCHI Naoki, OIZUMI Akito,
OBA Kyoko, KURETA Masatoshi, NAKAHARA Yukio

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