FY2020 (2020.4‐2021.3) NSEC
Annual Report

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

September 2021

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, 2021

FY2020 NSEC Annual Report

Table of Contents

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

R&D Highlights............................................................................. 2Group Activities............................................................................ 8

Organization of NSEC∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙ 9

Nuclear and LWR Engineering Division∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙ 10

Nuclear Data Center
Research Group for Reactor Physics and Standard Nuclear Code System
Research Group for Nuclear Sensing
Development Group for Thermal‐Hydraulics Technology
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
Development Group for LWR Advanced Technology
Nuclear Chemistry Division ∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙ 18
Research Group for Radiochemistry
Research Group for Analytical Chemistry
Environment and Radiation Sciences Division ∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙ 20
Research Group for Environmental Science
Research Group for Radiation Transport Analysis
Partitioning and Transmutation Technology Division ∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙∙ 22
Research Group for Partitioning
Research Group for Nuclear Transmutation System
Research Group for MA Transmutation Fuel Cycle

Publication List........................................................................... 25

FY2020 NSEC Annual Report

PrefaceKUGO TeruhikoDirector 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 2020. 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 2020, 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 2021
1

FY2020 NSEC R&D Highlight

FY2020 NSEC R&D Highlights

The following 5 highlights are selected among various outcomes of the R&D
activities accomplished by the NSEC's 5 divisions in FY2020.

 Nuclear and LWR Engineering Division:"Deuteron Nuclear Database for Design of Intensive Fast Neutron
Sources" Fuels and Materials Engineering Division:"Experimental Evaluation of Sr and Ba Distribution in MCCI Products
Formed under Temperature Gradient" Nuclear Chemistry Division:"Raman Microscopy Analysis of Uranyl Peroxides: Expectation to
Analysis of Fuel Debris"
 Environment and Radiation Sciences Division;"Reassessment of organ doses received by A‐bomb survivors by precisely
reproducing body dimensions of the Japanese in 1945"
 Partitioning and Transmutation Technology Division:"Estimating nuclear data using a machine learning technique"2

FY2020 NSEC R&D Highlight

Deuteron Nuclear Database for Design of Intensive Fast Neutron Sources
NAKAYAMA Shinsuke
Nuclear Data CenterIn the fields such as experimental nuclear physics,
medicine, and fusion reactor development,
intensive neutron beams with energies above 10
MeV are required. However, conventional neutron
sources using nuclear reactors and electron or
proton accelerators cannot satisfy theserequirements as illustrated in Fig.1. On the otherhand,neutronsourcesusing
deuteronaccelerators efficiently generate neutrons withenergies above 10 MeV. In Fig.1, neutron energy
distribution obtained from a lithium target
bombarded by a 40‐MeV deuteron is presented.
For the design studies of such facilities, it isnecessary to accurately predict the amount andenergy distribution of neutrons generated fromthe nuclear reactions induced by deuterons.
However, conventional calculation method does
not satisfy it. This is because the quantum
mechanical wave properties of deuterons are notconsidered appropriately.
In this work1), we developed a new calculation
method by integrating the several theoreticalmodels taking quantum mechanical effects into
account. Furthermore, the calculated results werecompiled into a database applicable to thesimulation code employed in the design studies ofneutron sources. The database was named as
JENDL/DEU‐2020, and it stores the deuteronnuclear data on lithium, beryllium and carbon
isotopes that are expected to be used as
deuteron‐beam targets in deuteron‐accelerator
neutron sources.
We present an example of the validation results ofthe simulation using JENDL/DEU‐2020 in Fig.2. The
figure shows the calculated and experimental
neutron yields from a 7.5‐mm thick lithium target
bombarded by a 25‐MeV deuteron. The red solidline and the blue dashed line are the simulation
results with the PHITS code, but the red solid line
represents the result where the data of
JENDL/DEU‐2020
are
used
as
the
deuteron‐induced reaction cross‐sections on Li‐6,7.
On the other hand, the blue dashed line is theresult where the theoretical models implemented
in PHITS is adopted for the calculation of theabove mentioned cross‐sections. As shown in Fig.2,
the result using JENDL/DEU‐2020 reproduce theexperimental data better than that using themodels in PHITS. Moreover, we have confirmedthat the prediction accuracy of the simulation
using JENDL/DEU‐2020 for beryllium and carbon

targets is as good as that for lithium target.
By using JENDL/DEU‐2020, the reliability of thesimulation is greatly improved and consequently
the designs of various neutron sources suitable for
their purposes will be easier. JENDL/DEU‐2020 is
expected to promote the use of intensive fastneutrons in various fields such as basic science,
medicine, and so on. JENDL/DEU‐2020 is available
from the website of Nuclear Data Center2).
This work was partially supported by JSPS
KAKENHI Grant Number 19K15483.

Fig.1 Neutron energy distributions obtained fromtypical neutron sources. Each distribution isnormalized to have a maximum value of 1.0,
and is presented in the range above 0.1 MeV.

Fig.2 Neutron yields from a lithium target
bombarded by a 25‐MeV deuteron.

Reference
1) S. Nakayama, et al., J. Nucl. Sci. Technol., 58, 805‐821(2021).
2) https://wwwndc.jaea.go.jp/ftpnd/jendl/jendl‐deu‐2020.
html (accessed 2021‐09‐07).

3

FY2020 NSEC R&D HighlightExperimental Evaluation of Sr and Ba Distribution in MCCI Products Formed
under Temperature Gradient
SUDO Ayakoa, SATO Takumib, OGI Hiroshib, TAKANO MasahideaaResearch Group for High Temperature Science on Fuel MaterialsbCollaborative Laboratories for Advanced Decommissioning Science (CLADS)
In the severe accident at Fukushima Daiichi
Nuclear Power Station (1F), the molten corematerials were predicted to relocate from thereactor pressure vessel and spread over theconcrete floor, resulting in molten core‐concreteinteraction (MCCI) at high temperatures. The MCCI
products still continue to be exposed to water, andconsequently the water‐soluble radionuclides may
be gradually dissolved from the MCCI products.
The dissolution behavior is crucial for evaluating
secondary source terms within 1F. In this study, we
focused on Sr and Ba as the representative fission
products. To obtain information on the
distribution of Sr and Ba in MCCI products, thereaction test between simulated corium(containing non‐radioactive Sr and Ba) andconcrete was performed1).
Fig.1 (a) shows the schematic illustration of thesample before heating. The powder mixture of
U0.5Zr0.5O2, ZrH2, stainless steel (SS), B4C,
Mo‐Ru‐Rh‐Pd, BaCO3, and SrCO3 as a simulated
corium was pressed into a tablet and placed on apiece of basaltic concrete. The light from ahigh‐power Xe lamp was directed onto the tablet
surface by a light‐concentrating heating device toform a simulated MCCI product under verticaltemperature gradient.
The cross‐sectional image of the solidified sample
is shown in Fig.1 (b). The corium and concrete
were interacted as liquid phases and solidified in
the upper region of sample (once melted zone).
Below the once melted zone, concrete wasthermally dehydrated. Fig.1 (c) and (d) show SEM
images of the upper region and bottom region of
once melted zone, respectively. Main phases aredark silicate glass containing 3 at%‐Sr and 2
at%‐Ba, and bright (U,Zr)O2 particles in which Sr
and Ba are not detected. (U,Zr)O2 precipitated asfine particles (2–3 µm) in the upper region, while
it precipitated as bigger particles (10–20 µm) inthe bottom region. Additionally, content of(U,Zr)O2 are much higher in the bottom region.
During the heating tests, sedimentation of(U,Zr)O2 particles may have occurred in the liquidsilicate glass because of its higher density.
An image of the layered structure of MCCI productis drawn in Fig.2. Sr and Ba are likely to beconcentrated in the upper silicate glass‐rich zone.
In the actual situation, the crust layer might formon the top surface with cracks and cavities. The
water is possible to contact the silicate glass‐richzone, which may result in dissolution of Sr and Ba
into water. Leaching behavior of Sr and Ba fromthe silicate glass will be the next issue to beinvestigated.
Reference
1) A. Sudo, et.al., J. Nucl. Sci. Technol., 58, 473‐481 (2021).

Fig.1 (a) Schematic illustration of thesample setup. (b) Optical micrograph of thesample cross section. (c) SEM image ofupper region of once melted zone. (d) SEM
image of bottom region of once melted
zone.

Fig.2 Image of the layered structure of the
MCCI product.

4

FY2020 NSEC R&D Highlight

Raman Microscopy Analysis of Uranyl Peroxides:
Expectation to Analysis of Fuel Debris
KUSAKA Ryoji
Research Group for Radiochemistry
will contribute to the analysis of actual fuel debris.
This work was supported by JAEA Nuclear Energy
S&T and Human Resource Development Projectthrough concentrating wisdom, Grant Number
JPJA18P18071886.

Fuel debris at the Fukushima‐Daiichi nuclear
power plants will be a complex solid mixture
generated after melting and cooling of nuclear
fuel and structural materials. Knowledge of thechemical state such as what kind of chemical
substance the fuel debris is composed of will be
one of important information that may influence
the decommissioning process such as removalfrom the reactor, storage, processing and disposalof fuel debris. However, the method of clarifying
the chemical state of fuel debris has not been
determined.
Therefore, in this research1), we focused on theuse of Raman microscopy, which has many
achievements in chemical analysis in many fields
such as biology. Measurements by Raman
microscopy do not require sample pretreatment
and can be performed on very small samples,
which will make it safer and easier to measure fueldebris with high radioactivity.
Since fuel debris is in contact with water in thereactor, it is expected to react with hydrogen
peroxide generated by radiolysis of water and to
be in a chemical state different from that at thetime of the accident. In this study, in order toenable to analyze fuel debris based on theinformation of the chemical change, U3O8, which
is one of basic uranium oxides, was reacted withhydrogen peroxide and the reacted U3O8 wasanalyzed with Raman microscopy.
As a result of Raman measurements, it wasclarified that two types of uranyl peroxides,
studtite and metastudtite, were formed on thesurface of U3O8 by the reaction with hydrogen
peroxide (Fig.1). Furthermore, the distribution ofthese products on the sample surface suggested
that studtite was predominantly produced overmetastudtite (Fig.2).
Uranyl peroxide is known to be produced byreaction with spent nuclear fuel and UO2. Recently,
it has been found that uranyl peroxide is also
produced by reaction with simulated debris ofuranium‐stainless‐zirconium system, which will beclose to actual debris. Therefore, uranyl peroxide
could also be produced in actual fuel debris, andthe present study shows that Raman microscopy

Fig.1 Raman spectra of U3O8 immersed in hydrogen
peroxide aqueous solution.
Two types of uranyl peroxides (Studtite andMetastudtite) were observed.

Fig.2 Distribution of studtite and metastudtite
generated of the surface of U3O8.
These images indicate that studtite waspredominantly produced over metastudtite.

Reference
1) R. Kusaka, et al., J. Nucl. Sci. and Technol., 58, 629‐634(2021).

5

FY2020 NSEC R&D Highlight

Reassessment of organ doses received by A‐bomb survivors by precisely
reproducing body dimensions of the Japanese in 1945
Tatsuhiko SATO1, Sachiyo FUNAMOTO2, Colin PAULBECK3, Keith GRIFFIN4, Choonsik LEE4,
Harry CULLINGS2, Stephen D. EGBERT5, Akira ENDO6, Nolan HERTEL7, Wesley E. BOLCH3
1

Research Group for Radiation Transport Analysis
Radiation Effects Research Foundation, Japan
3
University of Florida, USA
4
National Cancer Institute, USA
5
No affiliation
6
Nuclear Science and Engineering Center
7
Georgia Institute of Technology, USA
2

Epidemiological studies of A‐bomb survivors
conducted by the Radiation Effects Research
Foundation (RERF) are some of the mostimportant resources for data on the healtheffects of radiation. Precise estimation of
the organ doses is the key issue in thestudies, and the dosimetry system forestimating doses received by individualorgans for each survivor has devolved andimproved over the years. For further
refinements to the dosimetry system, aJapan‐U.S. joint project team was formed,
comprising Nuclear Science and Engineering
Center of JAEA, RERF, the University of
Florida, and the U.S. National Cancer
Institute. Members of this project teamdeveloped a new set of models of thehuman body (called “phantoms”) for adults,
children, and pregnant women by rigorously
reproducing the standard body dimensionsof Japanese people in 1945, which areplanned to replace those in the current
dosimetry system developed in the 1980s
using primitive geometrical shapes.
Examples of the newly developed phantoms
are shown in Fig.1. The project team also
developed a method for more accurately
estimating the organ doses of A‐bomb
survivors with these phantoms by utilizing
the latest computational techniques such as
PHITS, which was developed mainly by JAEA.
Based on idealized conditions inhypotheticalsurvivors,
ourinitialcomparisons of doses using the newphantoms and methods with doses derived
from the current dosimetry system foundthat doses were generally consistent,
although for some organs dose estimates
could change by approximately ±15 % at the
maximum1). Further studies are necessary
for implementing the new phantom series
in the dosimetry system.

Fig.1 Adults, children, and pregnant women
phantoms developed in this study.

Reference
1) T. Sato, et.al., Radiat. Res. 194, 390‐402 (2020).

6

FY2020 NSEC R&D Highlight

Estimating nuclear data using a machine learning technique
IWAMOTO Hiroki
Research Group for Nuclear Transmutation System
As illustrated in Fig.2, the proposed method
provides uncertainty information of the estimatedcross‐sections, which takes a lot of effort to obtainin the conventional method. The obtained
uncertainty information allows us to discuss
effectiveness of experiments from the viewpointof improving the accuracy of nuclear data, and is
expected to is applicable to the quantification of
the uncertainty due to nuclear data in research
fields using nuclear data such as shielding analysis
and reactor physics.

Nuclear data are indispensable for the simulationof particle transport in estimating radiation doses,
radioactive isotope production, and safetyparameters of nuclear systems. The quality andquantity of nuclear data in the evaluated nuclear
data libraries have been steadily enhanced owing
to physicists’ strenuous efforts; however,discrepancies between experimental data and thetheoretical model calculations remain particularly
at high incident energies. While it is important toimprove the theoretical models, conventional
approaches require substantial amount of timeand effort. In such cases, a machine learning(ML) technique may serve a useful role inestimating nuclear data. In this study1), we
proposed a method to estimate nuclear data fromexperimental data using ML based on Gaussian
processes2).
Fig.1 shows the proton‐induced sodium‐22 (22Na)
production cross‐section for silicon (natSi) nucleus
which is a key material of the semiconductor
devices. It is difficult to account for theexperimental data even with the latest theoreticalmodels. On the other hand, since the proposed
method estimates the cross‐section while learningfrom the experimental data, significant
discrepancy between the estimated andexperimental values does not occur in principle.

Fig.2 Uncertainty information of thenatSi(p,X)22Na cross‐section estimated by the
proposed ML method.
Top panel shows one standard deviation,
which gives the uncertainty of theevaluated cross‐section at incident energy;
bottom panel: correlation matrix, whichallows us to understand the strength of thelinear relationship between the crosssections between energy points.

Reference

Fig.1
Comparisonoftheestimatednat
Si(p,X)22Na cross‐section between thetheoretical model and the proposed ML
method.
The light blue band indicates 2 uncertainty
about the estimated cross‐section.

1) H. Iwamoto, J. Nucl. Sci. Technol., 57, 932‐938, (2020).
2) C.E. Rasmussen and C.K.I. Williams, Gaussian Processes
for Machine Learning, the MIT Press (2005).

7

FY2020 NSEC Group Activity

FY2020 NSEC Group Activities

The NSEC of JAEA consists of 15 Groups.

8

FY2020 NSEC Annual Report

Organization of NSEC

（as of September 2021）

URL: https://nsec.jaea.go.jp/organization/en_index.html
9

FY2020 NSEC Group Activity

Nuclear Data Center
because of the large neutron intensity. However,double bunch structure of the neutron beam
prevented
theaccuratecross
sectionmeasurement for fast neutrons. To overcome
this, we introduced the neutron filter system that
produce quasi mono‐energetic neutron beams. It
was confirmed to work well via Au‐197
measurement3), resulting in good agreementwith the evaluated values which is accurately
known.

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. They are available from our
website (https://wwwndc.jaea.go.jp).

Development of JENDL‐5
Development of the next version of evaluatednuclear data library JENDL‐5 is in progress.
JENDL‐5 aims to meet various needs from
nuclear energy application including not only
nuclear reactor development but also nuclear
backend such as decommissioning and wastes
management. Large amount of neutron induced
reaction data from light to heavy nuclides havebeen revised and newly evaluated. The test
libraries were created, and benchmarking forreactor and shielding has been done to validate
and improve the evaluated data. JENDL‐5 will
include not only neutron data but also charged
particle ones to meet the needs of radiation
applications.4)

Thermal Neutron Capture Cross
Section Measurement
Thermal neutron capture cross sections areimportant for thermal reactors which are
dominated in currently operating nuclear power
plants. Our group has been targeting crosssection measurements on minor actinides (MA)and fission products that are main componentsof nuclear wastes. The thermal cross sections
were measured by activation method with theresearch reactor of Kyoto University (KUR).
For Cs‐135, which is one of major long lived
fission products, mass spectrometry was utilized
to accurately quantify isotopes in Cs samples incombination
with
decay
gamma‐raymeasurement from decay of contaminatedCs‐137 in the sample. Resonance integral ofneutron capture cross section, which indicates
capture strength in resonance region, were also
deduced. The obtained result revealed thecurrent evaluated value of JENDL‐4.0 was
possibly overestimated by 30%.1)
The capture cross section of Am‐243 affects theamounts of Cm isotopes production in reactors,
which are major heat sources in spent fuels. In
this work, the capture cross sections were
measured for components of ground andisomeric state production. The present results
agree with the recent measurement at ANNRI of
J‐PARC by time‐of‐flight method which shows
possible underestimation of the current
evaluation of JENDL by 10%.2)** This work includes the result of “Research anddevelopment for accuracy improvement of
neutron nuclear data on minor actinides”
entrusted by MEXT.
** This work is supported by the Innovative
Nuclear Research and Development Programfrom MEXT, Grant Number: JPMXD0217942969.
Reference
1) S. Nakamura, et al., J. Nucl. Sci. Technol., 57, 388‐400(2020).
2) S. Nakamura, et al., J. Nucl. Sci. Technol., 58, 259‐277(2021).
3) G. Rovira, et al., Nucl. Instr. Meth. A, 1003, 165318(2021).
4) O. Iwamoto, et al., EPJ Web Conf., 239, 09002 (2020).

Neutron Filter System with
ANNRI**

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

The accelerator driven system (ADS) of MA
burner requires to improve accuracy of MA crosssections for fast neutrons. ANNRI has a large
potential for the MA cross section measurement10

FY2020 NSEC Group Activity

Research Group for Reactor Physics and Standard Nuclear Code
SystemThe role of nuclear codes is increasing with rapid
progress in computer technology. It enables toevaluate in detail the energy and spatial
distribution of neutrons and photons emitted
after fission reactions in a nuclear reactor.
Important properties such as criticality andradioisotope 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 technology.
The main codes are MVP and FRENDY. We arealso collaborating tightly with the JENDL projectand preparing many cross section libraries. We
produced a new multigroup library for ORIGEN in
SCALE6.2 from JENDL/AD‐2017 and developed ahandy criticality analysis tool for fuel debris
systems in JFY2020.

released in 2018. Thus we have produced a new
multigroup library (200 group, 300 K) for ORIGEN
in SCALE6.2 from JENDL/AD‐2017 with the
AMPX‐6 code9) in order to popularize
JENDL/AD‐2017 widely. JPDR activation analyses
with ORIGEN and the new library demonstratethat the new library has a performanceequivalent to the ORIGEN library in SCALE6.2.

HAND

HAND10) is a handy criticality analysis tool for fueldebris systems generated from the severe
accident at the Fukushima Daiichi Nuclear Power
Station. HAND is designed for the use in planning
fuel debris retrieval. HAND enables users to
perform quick criticality analysis without expert
knowledge of reactor physics. The input form of
HAND is very simple and users can intuitively
understand the calculation results. This tool is
expected to be the effective tool to estimate thecriticality of fuel debris systems. HAND is an
open‐source code and can be downloaded fromour group’s home page.2)

MVP
MVP realizes fast and accurate Monte Carlosimulation of neutron and photon transport
processes. The version 3 of MVP1) was released
in 2018 and available from RIST and OECD/NEA
Data Bank as NEA‐1673 MVP/GMVP V.3. The
cross section libraries for MVP3 can be
downloaded from our group’s home page.2)

Reference
1) Y. Nagaya, et al., JAEA‐Data/Code, 2016‐018 (2017).
2) https://rpg.jaea.go.jp/main/en/program/(accessed 2021‐09‐06).
3) K. Tada, et al., JAEA‐Data/Code, 2018‐014 (2019).
4) K. Tada and T. Endo, 2021 Annual Meeting of AESJ,
1B01 (2021). (in Japanese)
5) A. Yamamoto, et al., 2020 Fall Meeting of AESJ, 2H03
(2020). (in Japanese)
6) W.A. Wieselquist, et al., ORNL/TM‐2005/39 Version
6.2.4 (2020).
7) I.C. Gauld, et al., ORNL/TM‐2005/39 (2006).
8) https://wwwndc.jaea.go.jp/ftpnd/jendl/jendl‐ad‐2017.
html (accessed 2021‐09‐06).
9) D. Wiarda, et al., ORNL/TM‐2016/43 (2016).
10) K. Tada, JAEA‐Data/Code, 2020‐014 (2020).
(in Japanese)

FRENDYFRENDY is a nuclear data processing code.3) It
enables processing of evaluated nuclear datasuch 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 version 1 was released
in 2019 as an open‐source code from our group’s
home page.2) Current developments include theestimation of statistical uncertainty in probability
table generation for unresolved resonance crosssections,4) and the generation of multigroupcross sections.5) These capabilities are to be
implemented in version 2.

New ORIGEN library

Contact (Group Leader):NAGAYA Yasunobu
nagaya.yasunobu@jaea.go.jp

The SCALE6.2 code system6) was released in 2016
(the latest version is SCALE6.2.4). The ORIGEN
code6) in SCALE6.2 used for activation
calculations in decommissioning is completely
different from the previous ORIGEN‐S code.7)
JENDL Activation Cross Section File for Nuclear
Decommissioning 2017 (JENDL/AD‐2017)8) was

11

FY2020 NSEC Group Activity

Research Group for Nuclear Sensing
Non‐destructive analysis (NDA) is one of themost essential and fundamental methods inmany fields, such as nuclear material
accountancy, nuclear safeguards and security,
decommissioning and many other scientific fields.
Despite being a mature method, further
improvements in NDA are required and enable
us to meet the distinctive demands ofresearchers and engineers. We have therefore
developed an advanced NDA system for highly
radioactive nuclear materials, and an analyticalmethod of At‐211 for radiotheranostics.

Developments of an Analytical
Method of At‐211
The α‐emitting radio halogen At‐211 has drawn
great interest because of its potential use in thetreatment of cancers. After At‐211, produced bya nuclear reaction, is separated from theirradiated targets in the chemical procedures,
basic researches related to the chemical
properties of At‐211 and radiolabeling reactions
for pharmaceuticals have been performed forvarious purposes. At present, the radioactivity
and chemical forms of At‐211 have been
determined separately. The former has been
determined by γ‐ray spectroscopy using
semiconductor detectors. The latter has beenmeasured by imaging plates (IPs) visualizing
thin‐layer chromatography. However, IPs needtypically more than 10 h for the visualization. In
addition, these are sensitive to the x‐raysemitted from radioactive nuclides, such as
Po‐207 biproducts of Rn‐211, as well as At‐211,
so that not all the chemical forms of At‐211 areanalyzed with the visualization of IPs. To prevent
severe loss of At‐211 due to its short half‐life of
7.2 h, and to obtain accurate analytical results, a
rapid analytical method for both the radioactivity
and all chemical forms of At‐211 was required.
We propose a new method by means of an
α‐scintillation‐camera system comprising ofthin‐layer chromatography and a high‐sensitive
CCD camera. The performance of the system was
experimentally verified: low‐radioactivity At‐211
of 56‐672 Bq was measured in a short time of
1,000 sec and all chemical forms of At‐211 wereable to be evaluated. The results reveal that themethod enables us to analyze two features of
At‐211 within a significantly short time.2)

Developments of Prompt
Gamma‐ray Analysis Apparatus in
Active‐N
No established non‐destructive method exists tomeasure the amount of highly radioactive
nuclear fuel materials such as spent fuels, and it
is one of the urgent issues in nuclear material
accountancy. Therefore, we have started a
research on development of innovative
non‐destructive analysis (NDA) system, named“Active‐N”, which provides the following
active‐neutron NDA methods: Differential
Die‐away
Analysis,
NeutronResonance
Transmission analysis, and Prompt Gamma‐ray
Analysis (PGA). To reduce neutrons that induceradiation damage to the germanium detector for
PGA, its extra shielding was developed. Througha series of Monte Carlo simulations, the ability ofseveral common materials in reducing theneutrons was investigated, and the reduction of
fast neutrons and suppression of 2.22‐MeV
gamma rays originated from hydrogen were
optimized. The results of the simulations showthat by using 1:1 mixture of HDPE and LiF withnatural isotopic composition, the same levels offast neutron reduction and 2.22‐MeV gamma
suppression can be achieved with a shielding inwhich 6LiF plates of 1cm‐thickness are inserted
every 3 cm. It is found that by adding the extra
shielding, the fast neutron fluence at the
germanium crystal position can be reduced
approximately an order of magnitude, from
1.9×10‐5 to 2.7×10‐6 /cm2/source, which is low
enough to avoid the severe damage of PGA
detector. 1)
This research was implemented under thesubsidiary for nuclear security promotion of
MEXT.

Reference
1) K. Furutaka, et al., Proc. Joint Inter. Conf. Monte Carlo
2020, 297‐394 (2020).
2) M. Segawa, et al., J. Radioanal. Nucl. Chem., 326,
773‐778, (2020).

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

12

FY2020 NSEC Group Activity

Development Group for Thermal‐Hydraulics Technology
JUPITER to enhance the safety of the LWRs.

For the establishment of thermal‐hydraulics
numerical simulation methods for multi‐phaseflow, we are developing multi‐phase CFD
numerical simulation codes, TPFIT and JUPITER,
measurement
techniquestoobtainthermal‐hydraulicsdata
andperforming
thermal‐hydraulics experiments to constructvalidation databases. These advanced techniques
are applied to the research works for improving
the safety of the LWRs and considering thedecommissioning
processoftheFukushima‐Daiichi nuclear power station.

Experimental Studies
We perform various experiments to validate
those simulations and construct basic physicalmodels. As one of the experiments, we
performed optical measurement of aerosol
particles (microparticles) capturing behavior
near the gas‐liquid interface (Figure 2)3).
Microparticles’ capturing at interface is utilized
in water filtering industrially. The capturing is
also used in filtered venting systems and poolscrubbing in the nuclear reactors. By thisexperiment, we could visualize aerosol particle
behavior. Based on experimental results, weconstructed a physical model to express
microparticle behavior vicinity and on theinterface. We introduced the constructed model
to TPFIT to improve numerical simulation
accuracy.

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.
Besides, JUPITER can perform the massively
parallel simulation of multi‐phase flow withmore than two hundred thousand cores, byadapting high‐efficient parallel computing
techniques.
As one of the examples of CFD codes, we
performed a numerical simulation of air‐water
two‐phase flow with microparticles in a pool
(Figure 1)1). In this simulation, microparticles'
motion in two‐phase flow was simulated by
TPFIT with the Lagrangian particle tracking
method. In Fig.1, we visualized interfaces as
white surfaces, and yellow spheres show
microparticles. A two‐phase flow in the waterpool is obtained, and we can simulate two‐phaseflow with microparticles by TPFIT.
TPFIT and JUPITER were released at PRODAS2).
We are continuously improving TPFIT and

Fig.2 Continuous images of the particle moving
in the vicinity along the gas‐liquid interface.

Reference
1) H. Yoshida and S. Uesawa, Proceedings of ASME's
Nuclear Engineering Conference powered by ICONE(ICONE2020), ICONE2020‐16393 (2020).
2) PRODAS (PROgram and DAtabase retrieval System),https://prodas.jaea.go.jp/ (accessed 2021‐09‐06).
3) S. Uesawa and H. Yoshida, Mech. Eng. J., 7, 19‐00539(2020).

Contact (Group Leader):YOSHIDA Hiroyuki
yoshida.hiroyuki@jaea.go.jp(a) t=0.03[s](b) t=0.06[s]Fig.1 Numerical simulation of two‐phase flow
with microparticles in water pool.

13

FY2020 NSEC Group Activity

Research Group for Corrosion Resistant Materials
artificial seawater components. It is clear thatthe corrosion rate of carbon steel in thealternating condition accelerates with increasing
concentration in the concentration region
between deionized water to 200 times diluted
artificial seawater (ASW), and the corrosion rate
decreases with increasing concentration in theconcentration region between 20 times diluted
ASW to undiluted ASW. (Fig. 2) It can beconsidered that the reason why the carbon steel
corrosion was suppressed in highly ASW would
be caused by Mg ions and Ca ions in the artificial
seawater precipitate and cover on the surface
due to the increase in pH near the surface byoxygen reduction reaction.

We have been researching on corrosion of metalmaterials used for nuclear facilities. If thecorrosion occurs, the components of the nuclear
facility will degrade, which may cause holes andcracks. Therefore, we are focusing on the
corrosion mechanism to develop the methods ofcorrosion prediction and prevention. Throughthese research activities, we contribute toimproving the reliability of nuclear facilities.

Researches on localized corrosion
mechanisms in stainless steels1)
Stainless steel (SS) is popular material frequently
used in nuclear facilities, but the localized
corrosion often occurs due to chloride ions (Cl‐).
Cu alloyed with SS is known to be both beneficial
and detrimental to localized corrosion. To
understand the role of Cu in localized corrosion,
the developed extra‐high‐purity (EHP) SS, which
is Cu‐free, were used and anodic polarization
measurements were conducted in two solutions,
one with Cu2+ and one without Cu2+, toinvestigate the effects of Cu2+ in the bulk solution
on the localized corrosion resistance. (Fig. 1) At
first, the specimens were polarized to 0.4 V in 0.1
M NaCl‐1mM CuCl2 (condition a1 and b1) todeposit metal Cu and Cu compound onto thesurface. Subsequently, the solution was replaced
to 0.1 M NaCl (a2) or 0.1 M NaCl‐1mM CuCl2 (b2).
Shown as rapid increase in current density at ca.
0.8 V, pitting occurred in b2, but no pitting
occurred in a2. In conditions of a1 and b1,
deposition of Cu compound on the surface wasconfirmed. These results suggest that both
deposited Cu on the surface and Cu2+ in the bulk
solution were necessary for the pitting to occur.
Therefore, the decrease in pitting corrosion
resistance of 316 EHP SS in 0.1 M NaCl with 1
mM CuCl2 is mainly due to precipitated Cucompounds and continuous Cu2+ supply to thesurface.

(a1,2) From Cu2+ containing to Cu2+ free solution(b1,2) Cu2+ containing solution

Figure 1 Anodic polarization curves of EHP SS.

Artificial Sea Water
NaCl Solution
Cation Containing
Solution

Figure 2 Corrosion rate of carbon steel in various
test solutions with different concentration.

Researches on corrosion
mechanisms under air‐waterinterfacial environment2)

Reference
1) T. Aoyama, et.al., Metals, 11, 511, (2021).
2) K. Otani, et.al., Zairyo‐to‐Kankyo, 69, 246–252, (2020).

After the accident of Fukushima Daiichi Nuclear
Power Station (1F), seawater had been injected
and purified cooling water is circulated into theprimary containment vessel (PCV) in the present.
To understand the corrosion mechanism in the
air/solution alternating condition that is theair/solution interfacial environment, thecorrosion rate of carbon steel under air/solution
alternating conditions was investigated inContact (Group Leader):KATO Chiakikato.chiaki16@jaea.go.jp

14

FY2020 NSEC Group Activity

Research Group for Radiation Materials Engineering
In our group, a wide variety of nuclear materials,
including the materials which are under theconsideration of future potential use, have beenstudied for the purpose of deepening theunderstanding on their radiation tolerance. A
tandem accelerator is one of the most familiar
experimental tools for material irradiation studyof our group. Especially, as for ceramic materials,
systematic irradiation studies have been done,
and a review paper of the studies1) has been
published recently. In order to explore a new
advanced material not only for nuclear use but
also non‐nuclear one, we are also making themost use of a shared supercomputer system
which was renewed recently.

an important tool in modeling disordered alloys
with atomic resolution. By using these atomic
structure models, it is expected that local lattice
distortion, short range ordering, and a stacking
fault energy of this HEA will be evaluated.
(a)

(b)

(c)

Fig.1 (a) High‐Resolution TEM image of hillock
observed in CeO2 with irradiated a 200 MeV Auion, and schematic formation processes of ion
tracks and hillocks in (b) CeO2, (c) amorphizable
ceramics (YIG, LiNbO3, and ZrSiO4).

Systematic understanding ofcharacteristic damage structuresin ceramics irradiated with SHI
Irradiation with high energy is known to create
various radiation damages in a target material.
Due to continuous effort over a lengthy period oftime, we have gradually learned more aboutcharacteristic damage structures, such as ion
tracks and hillocks, in a variety of ceramics
irradiated with swift heavy ions (SHI). In ourrecent work, we have summarized the formation
processes of ion tracks and hillocks in various
ceramics irradiated with SHI. Figure 1 presents
one of typical high‐resolution images of atransmission electron microscope (TEM), andformation processes of ion tracks and hillocks in
non‐amorphizable and amorphizable ceramics
with a 200 MeV Au ion, giving us the informationsuch that the difference in shape of hillocks
possibly comes from the difference in volume of
protrusion and that the material dependence ofnanostructure formation can be ascribed to theintricate recrystallization process.

Fig.2 Atomic structure models of FCC alloy createdby using Special Quasi‐random Structure (SQSs).
Five different atomic structure models were
produced as a CoCrFeNiMn random alloy2).

Reference
1) N Ishikawa, et al., “Comprehensive Understanding of
Hillocks and Ion Tracks in Ceramics Irradiated with
Swift Heavy Ions“, Quantum Beam Sci. 4(4), 43 (2020).
2) “Development of new reduced activation HEAs byadditive manufacturing method”, JFY2020 progress
report. This work was supported by MEXT Innovative
Nuclear Research and Development Program Grant
Number JPMXD0220354336.

Computational materials sciencebased on atomistic simulation
High entropy alloy (HEA) has a lot of fascinating
features as a structural material not only for
nuclear industry but also non‐nuclear one. Many
types of HEAs are proposed, and experimental
and theoretical studies on these alloys are now
aggressively proceeding all over the world. In ourgroup, we have recently started experimental
and theoretical works in a collaboration programwith some of the domestic universities. Figure 2,
for example, shows atomic structure models of
CoCrFeNiMn alloy (one of the mostrepresentative HEAs) which was created by using
special quasi‐random structures (SQSs). SQSs areContact (Group Leader):YAMASHITA Shinichiro
yamashita.shinichiro@jaea.go.jp

15

FY2020 NSEC Group Activity

Research Group for High Temperature Science on Fuel Materials
well‐designed CO removal unit.2) These resultsmeans that the concept of the prototype system
can be applied to the actual fuel fabrication.
By the R&D activities described above, we haveconsiderably advanced in solving the 15N2 issues
for the nitride fuel fabrication.
Isotopic scramble

1

14

N

Abundance ratio

0.8

Nitride fuel for MA
transmutation

14

N2

15

Distillation columns

We treat issues on nuclear fuel materials forboth light water reactors and advanced reactors
in the future. Experimental works on uranium
and non‐radioactive materials are carried out in
the Research building No. 4, with various heating
devices and analytical apparatus. Those ontransuranium elements (TRU; Pu and minor
actinides) are performed at TRU‐HITEC,
consisting of specially designed hot cells and a
glove box with highly purified argon atmosphere.
We also take advantage of computer science tounderstand or predict phenomena concerning
the fuel materials at high temperatures andunder the irradiation conditions.

N
15

N2

0.6
0.4
14 15

N N

0.2
0
0

For fabrication of the actual nitride fuels forminor actinide (MA) transmutation, the N2 gas
highly enriched with N‐15 is needed to avoid theaccumulation of C‐14 in the fuel from 14N(n,p)14C
reaction. To realize the availability of 15N2 gas inseveral hundred kg – 1 ton/year is an important
issue. In cooperation with the gas plant industry,
we have designed basic specifications of a N2
cryogenic distillation plant, based on the existing
O‐18 commercial plants with the similar concept.
Fig. 1 shows an example of distillation simulation
results and a CAD image of the plant. The annual
production of the designed plant is 1 ton of 15N2
gas enriched with 99 % N‐15.1) The product costis estimated to be 1/30 of the current
distribution price, produced from the existing NO
cryogenic distillation plants.
Another technical issue is the economical use of
15N gas in the fuel fabrication process. MA
2nitride is obtained by carbothermic reduction of
the oxide under highly‐pure N2 gas flow, withevolution of CO gas. We have designed andassembled a “nitrogen circulation refining system”
for laboratory‐scale demonstration of N2 gas use
in closed cycle without exhaust. This prototype
system consists of the CO removal unit to purify
N2 gas with nickel catalyst, and the circulation
unit that can automatically keep the systempressure and the N2 gas flow rate, as is shown in
Fig. 2. Comparative experiments on the
nitridation of lanthanide oxide as surrogate of
MA by using this system or ordinary“once‐through” N2 gas flow resulted in that the
impurity oxygen in both nitride products are thesame level. Especially, CO in N2 gas flow at the
furnace outlet (several thousand ppm) wascompletely removed to zero ppm through the

2

4
6
8
10
Column number

12

CO removal unit

Nitridation
furnace

CO monitor

N2

O2/moisture
removalcolumns

N 2+H 2

CO monitor

Fig.1 Example of the N‐15 distillation simulation
results (left) and CAD image of the plant (right). 13
distillation columns with 70 m height.

Circulation unit

Fig.2 Schematic diagram of the prototype“nitrogen circulation refining system.”

Reference
1) M. Takano, JAEA‐Review 2020‐080 (2021).
2) T. Iwasa, et al., JAEA‐Technology 2020‐024 (2021).

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

16

FY2020 NSEC Group Activity

Development Group for LWR Advanced technology
to promote the developments in industries. To
investigate the detail oxidation behavior of the
FeCrAl‐ODS material during hypotheticalaccidental condition which may affect the
integrity of the fuel, we conducted oxidation
tests in high temperature steam flow inthermobalance in the temperature range from
600 to 1150 °C, and mass gain during oxidation
was visibly observed over 750 °C. Followed
parabolic law, the oxidation rate was the highest
at 1150 °C (Fig.2), while which at 750 °C was
unexpectedly higher than that in the range from
800 to 950 °C. Raman spectroscopy on thesample surface indicated that oxides such as
Al2O3, Fe2O3, Fe3O4, etc. were formed, and ratioof Al2O3 increased as the testing temperaturerises. Oxidation resistance of FeCrAl‐ODS during
accident is considered that it is ensured by thesurface Al2O3 layer, however this study suggested
that it is not the case at lower temperature suchas 750 °C.

This group was founded to conduct a research
program to improve LWR (Light Water Reactor)
safety by evaluating the rationality of regulation
standard, safety margin estimation, accident
management, etc., from a scientific point of view.
Through this, the group aims to advance thesafety technology in LWR, and also contribute toaccelerate the decommissioning and dismantlingof Fukushima Dai‐ichi Nuclear Power Station (1F).
This group mainly conducts studies on fission
product (FP) behaviors under severe accident(SA) condition, and development of accident
tolerant fuel (ATF) cladding.

Fission product (FP) behavior

We are updating a database of FP chemistrynamed ECUME (Effective Chemistry database offission products Under Multiphase rEaction).
ECUME covers important phenomena revealed
after the 1F SA.
Radioactive cesium (Cs) is one of the principal
radiation sources and information on the Cs
distribution within reactor pressure vessel (RPV)
is of crucial importance to make a reasonablesafety assessment for the fuel debris retrieval
and the reactor decommissioning at 1F.
Especially, a large amount of Cs can be present in
the upper region of the RPV by chemical
reactions of Cs vapor species with structures,
known as chemisorption. Thus, a chemisorption
model is incorporated into current SA analysis
codes. However, the existing chemisorption
model cannot accurately reproduce experimental
results and is considered not to be suitable forthe estimation of the Cs‐chemisorbed amounts
under various conditions experienced in 1F.
Therefore, a modified Cs chemisorption model
which accounts for effects of chemically affecting
factors (i.e., silicon content in stainless steel andgaseous Cs concentration) was constructed. As aresult, modified model called ECUME model wasable to describe these effects and moreaccurately reproduce the experimental data thanthe existing model (Fig.1). Thus, the Cs
distribution in various chemical condition in 1F
accident is expected to be estimated with higher
reliability by implementing ECUME model into SA
analysis code SAMPSON, which is developed
under the collaboration with the Institute ofApplied Energy (IAE).

Fig.1 Dependence of gaseous Cs concentration
for the chemisorption rate constant1)

Fig.2 Profile of mass gain on FeCrAl‐ODS duringoxidation test in high temperature steam2)

Reference
1) K. Nakajima, et al., Mech. Eng. J. Vol.7, No.3 (2020).
2) Y. Nemoto, et al., abstract for the AESJ Fall meeting in
2020, 1E07 (2020) (in Japanese).

Accident Tolerant Fuel (ATF)

For further improvement of safety of the existing
LWRs, ATFs are being developed. In Japanesedevelopment program, FeCrAl‐ODS steel for BWR,
SiC fiber reinforced SiC matrix composite(SiC/SiC) for BWR and PWR, and also Cr and CrN
coated zircalloy for PWR, were selected as major
ATF cladding concepts. We are conducting
fundamental studies on ATF cladding candidates

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

17

FY2020 NSEC Group Activity

Research Group for RadiochemistryRadiochemistry
providesfundamental
information about the essential materials indeveloping nuclear technology by identificationof the chemical reaction of radioactive materials
by measurement and chemical separation. We
chemically resolve various issues arisen from thenuclear industry by developing new technique of
measurement and computational method. Tworemarkable achievements of JFY2020 would be
introduced as followings.

species based on the Gibbs energies in the
stepwise nitration reactions (Fig. 3). Correctionof association energy between the nitrated
species and a substituting ligand increased thefractions of the complexes with x = 2, 3 in high
HNO3 concentration, being consistent with theexperimental observation.

Ligand Design for Minor Actinides
Separation from Lanthanides
Partitioning and transmutation strategy of minor
actinides (MAs) has been developed to reduceradiotoxicity of high‐level liquid waste (HLLW).
We have designed ligands with high separation
ability of trivalent MAs (Am3+, Cm3+) fromlanthanides by the aid of density functional
theory (DFT) calculation.
DFT calculation designed a novel ligand, TPAMEN,
which is predicted as a potential candidate forMAs separation from lanthanides, andsynthesized
thecomplex
with
Eu3+,
3+
[Eu(TPAMEN)] , as well as the single crystal (Fig.
1).1) X‐ray crystallography revealed a 10‐foldcoordination sphere of [Eu(TPAMEN)]3+. Detailed
geometry optimizations of [M(TPAMEN)]3+ (M =Eu3+, Am3+) using the obtained crystal structure
as the starting coordinate reproduced thecoordination geometry of [Eu(TPAMEN)]3+ andindicated the shorter Am3+‐N bond lengths thanthe Eu3+‐N bond lengths (Fig. 1). Further electron
density analysis suggested that the potential highperformance of TPAMEN in Am3+/Eu3+ separation
attributed to the stronger covalency in the
Am3+‐N bonds than the Eu3+‐N bonds.

Fig.1 Molecular structures of TPAMEN and[Eu(TPAMEN)]3+ (upper) and bond lengths of[M(TPAMEN)]3+ (down).

Fig.2 Stepwise nitration reaction of Ru(NO)3+.

Speciation of Platinum‐Group
Metals in High‐Level Liquid Waste

Fig. 3 DFT simulation of Ru speciation dependingon HNO3 concentration.

Light platinum‐group metals (Ru, Rh, Pd), existing
as fission products in HLLW, are known toprecipitate with coexisting ions. This isconsidered to hinder the vitrification process of
HLLW. As the first step to understand thechemical behaviors of PGMs in HLLW we havediscussed stepwise nitration reaction ofruthenium‐nitrosyl ion, Ru(NO)3+, using DFT
calculation.2) We compared the relative stability
among the coordinative isomers of the nitrated
products, [Ru(NO)(NO3)x(H2O)5−x](3−x)+ (x = 1‐5).
This indicated that the stepwise nitration
reactions proceed via the NO3− coordination to
the equatorial plane toward the Ru‐NO axis (Fig.
2). We also simulated the fraction of the nitrated

Reference
1) Schnaars, K. et al., Inorganic Chemistry, 60, 2477‐2491,(2021).
2) Kato, A. et al., RSC Advances, 10, 24434‐24443, (2020).

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

18

FY2020 NSEC Group Activity

Research Group for Analytical Chemistry
Accurate analyses of radioactive substances arefundamental technologies supporting nuclear
development. Control of the chemical state ofanalytes and removal of interference elements
prior to instrumental analysis are key techniques
for the high precision chemical quantitative
analysis. We developed practical analyticalmethods for radionuclides and traces ofirradiation based on studies of elucidation ofchemical reactions and separation phenomena
such as adsorption, precipitation, aggregation,etc. It is engaged on instrumental analyses suchas electrochemical method, mass spectrometry,and so on.

Electrochemical Studies of
Uranium(IV) to Build a Redox
Flow Battery using Uranium
As one of the perspective candidates of theapplication of depleted uranium, we are studying
a redox flow battery (RFB) using uranium (U) as
an electrode active material. To develop the RFB
with U, UIII, and UV species which are unstable inan aqueous solution must be stabilized. We
conceive to use an ionic liquid (IL) for theirstabilization. Also, an organic solvent was mixed
to solve high viscosity which was a disadvantage
of an IL. The electrochemical behavior of
uranium(IV) tetrachloride in [EtMeIm][Tf2N]–
DMF (1:1 v/v) mixture was studied at 298 K.2) We
found a quasi‐reversible UIII/UIV couple by using
glassy carbon as a working electrode in an IL–
DMF mixture having a viscosity that could bepumped. Since the mixture system has low
resistance, it is suitable for building an RFB whichmust handle a large current. The reversibility of
the UIII/UIV couple and the improvement of theelectromotive force in an RFB system by additionof Cl‐. We believe that these results will help
build a novel URFB system.

Speciation analysis is necessary to understandthe behavior of radioactive elements such as
actinides. Our trace‐detection and microscopic
analysis techniques were applied to themeasurement of real samples. In thedecommissioning of the TEPCO’s Fukushima
Dai‐ichi Nuclear Power Station (1F), there isconcern about internal exposure due to ingestionof particulate matter containing alpharadionuclide into the body. Our micro‐analysis
technique was applied to elucidation of forms ofparticulate alpha emitter in a stagnant water in
1F.
Spin‐off research using analytical techniques ofactinides is also our key issue. Electrochemical
analysis and uranium handling techniques were
utilized to reaction kinetics study for a large
capacity battery.

External Exposure Dose
Estimation using ESR TechniqueElectron spin resonance (ESR) dosimetry using
tooth is one of the powerful tools for theindividual external exposure dose estimation.
The principal of ESR dosimetry is to measure thelong‐lived CO2 radicals in tooth enamel as a traceof radiation. Organic dentine and metalcomponents in tooth interfere the ESR
measurement, therefore, it is necessary to
remove them and prepare “pure” inorganic
enamel. We have established the enamel
preparation methodology by centrifugation andappropriate chemical treatments, it enables us to
improve the detection limit of ESR dosimetry todetect the exposure dose below 100 mGy. We
have been estimating the exposure dose of wild
animals captured in Fukushima Prefecture1); ourfuture aim is to assess the exposure dose forchildren in Fukushima Prefecture.

Fig.1

Concept of the U redox flow battery.

Reference
1) T. Oka, et al., Radiat. Meas., 134, 106315 (2020)
2) K. Ouchi, et.al., Chem. Lett., 50, 1169‐1172 (2021).

Contact (Group Leader):KITATSUJI Yoshihiro
kitatsuji.yoshihiro@jaea.go.jp

19

FY2020 NSEC Group Activity

Research Group for Environmental Science
We research dynamics of radioactive materials in
the atmospheric, terrestrial, and oceanic
environments to improve assessment technology
of environmental impact of radioactive materials.
Computer models are developed and validated
to predict the movement of radioactive materials
in the environment. In particular, we developed
atmospheric prediction systems (WSPEEDI‐II andWSPEEDI‐DB) and an oceanic prediction system(STEAMER). We also obtain observational data by
field survey and analyze the data with advanced
analysis technology. The data are used to clarify
dynamics of radioactive materials and validate
accuracy of the computer models.

In addition, we applied the combined model topredict the real plume dispersion in an urban
area, the Central Business District of Oklahoma
City. It took 60 hours to predict the atmosphericdispersion fields in the area using the LES modelby a single Intel CPU core. On the other hand, it
took 1.5 hours to predict those using the
combined model (RANS calculation withpre‐calculated LES data). It was also
demonstrated that the combined model results
quantitatively agree with the LES results. These
results suggested that the combined model can
predict the real plume dispersion in the urban
area with low computational costs and highaccuracy.

Development of a Combined
LES/RANS Model
We developed a large‐eddy simulation (LES)
model to predict the atmospheric dispersion ofradioactive materials in local areas. The LES
model was used in many studies to predict
turbulent flows in urban areas. However, it takes
much time to perform atmospheric dispersion
simulations using the LES model, because it
precisely calculates unsteady flow fields. On theother hand, a Reynolds‐averaged Navier‐Stokes(RANS) model solves averaged equations tocompute mean flow fields. The RANS model has
the advantage of low computational costs,
although the RANS model is generally lessaccurate than the LES model for predicting
atmospheric fields.
To reduce the calculation time in emergency
response, our previous study proposed apractical and quick atmospheric dispersion
simulation method for a fixed source location
based on atmospheric dispersion fields
precalculated by the LES model1). This study aims
to develop a combined LES/RANS model toperform atmospheric dispersion simulations forchangeable source locations with low
computational costs and high accuracy2). In the
combined model, the flow fields are
pre‐calculated using the LES model. Then, theatmosphericdispersion
simulations
areperformed using the RANS model based on the
pre‐calculated LES data. The empiricalparameters in the turbulent flux were adjusted
by comparison with results of wind‐tunnel
experiment (WD)3). The combined model
successfully calculated horizontal dispersion
fields consisting with those calculated by the LES
model (Fig. 1).

Fig.1 Horizontal profiles of the passive scalar
concentrations in the street canyon at the surface.
The concentrations are normalized by the values
at release point (x = 0). The profiles of LES, RANS,
and WD were obtained from the previous study3).

Reference
1) H. Nakayama and T. Takemi, International Journal ofEnvironment and Pollution, 64, 125‐144, (2018).
2) T. Yoshida and H. Nakayama, Transactions of theJapan Society for Computational Engineering andScience, 2020, 20200013, (2020).
3) Y. Tominaga and T. Stathopoulos, Journal of Wind
Engineering and Industrial Aerodynamics, 99, 340‐348,(2011).

Contact (Group Leader):KAWAMURA Hideyuki
kawamura.hideyuki@jaea.go.jp20

FY2020 NSEC Group Activity

Research Group for Radiation Transport Analysis
Nowadays, computer simulation techniques that
can analyze radiation transport in materials are
essential tools for research and development in
the field of nuclear and radiation sciences. We
have developed a radiation transport simulation
code, the Particle and Heavy Ion Transport code
System (PHITS)1), and apply it to industrial,
scientific, and medical studies. PHITS has been
upgraded to improve its higher reliability and to
its wider areas to be applied. In addition, we also
conduct studies on radiological protection andradiation effects. This paper presents ourprogresses in FY2020: upgrades of PHITS anddevelopment of a radiation dose database forpublic exposure in Japan.

New Calculation Method for DPA3)
DPA is an average number of displacement
atoms per atom of a material and is widely used
as an exposure unit to predict the operating
lifetime of materials in radiation environments.
In FY 2020, we improved PHITS to derive theAthermalRecombination
Correction‐dpa(arc‐dpa), because the arc‐dpa model provides
more physically realistic descriptions of primary
defect creation in materials compared to aformer standard model (NRT‐dpa model). In our
analysis, the arc‐dpa cross sections are smaller
than the NRT‐dpa cross sections by a factor of
about 3 for the displacement cross sections of Cu
and W under proton irradiations with energies
above 100 MeV.

Upgrades of the PHITS CodeRadiation Dose Database for
Public Exposure

DCHAIN‐PHITS2)DCHAIN‐PHITS
isthetime‐dependentradio‐nuclide production, buildup, burnup, anddecay code which is coupled to PHITS. Hybrid
activation cross section libraries are newly
available for DCHAIN‐PHITS, utilizing various
combinations of evaluated data. We improved
DCHAIN‐PHITS to output the statisticaluncertainties by propagating those of the PHITS
simulation. Support for mesh tallies has also
been added, allowing for induced activity
calculations in tetrahedral geometries as well aswith rectangular coordinate mesh tallies (xyzmesh) superimposed on any geometry, utilized in
the connected induced activity and dose
calculation depicted in Fig. 1.

In radiological protection, radiation dose criteria
are usually set with the effective dose that isderived from organ doses calculated with the
ICRP phantoms (Male: RCP‐AM, Female: RCP‐AF).
The ICRP phantoms are constructed by referring
to body physiques of standard Caucasian adults.
The body physiques can affect shielding ofradiation within body tissues for external
exposure. So far, studies have been made on thedosimetric characteristics of adult Japanese forphoton irradiations. In FY 2020, we analyzed theimpact of body sizes on organ doses due toexternal neutron irradiation. Here, the male andfemale phantoms with different body physiques
were constructed by changing busts, chests,
waists and hips of Japanese adult standard
phantoms; JM‐103 (male) and JF‐103 (female).
After that, the radiation dose database for public
exposure is developed based upon the results of
our analyses.

(A) Induced activities (B) Dose distribution(by PHITS)(by DCHAIN‐PHITS)
Fig.1 Estimation of doses from induced activities
by calculations of DCHAIN‐PHITS and PHITS

Reference
1) PHITS homepage, https://phits.jaea.go.jp/ (accessed
2021‐09‐07).
2) H. Ratliff, et al., Nucl. Instrum. Methods Phys. Res. B,
484, 29‐41 (2020).
3) Y. Iwamoto, et al., J. Nucl. Mater. 538, 152261, (2020).

Implementation of SCINFUL‐QMD
Algorithm
A new algorithm was developed to calculate
responses of an organic scintillator based on acomputer code SCINFUL‐QMD that has beenutilized in many experimental studies. PHITS canreproduce well the neutron responses anddetection efficiencies of an organic scintillator(e.g., light outputs from an organic scintillator)
with the new algorithm. Thus, the improved
PHITS is a powerful tool for various research anddevelopment efforts in the field of radiologicalscience.

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

21

FY2020 NSEC Group Activity

Research Group for Partitioning
Partitioning and transmutation has been
proposed as a strategy for managing high‐level
radioactive waste (HLW) generated byreprocessing of spent nuclear fuels via ahydrometallurgical method. HLW consists ofmany elements of different radiotoxicities andchemical properties. Thus, it is reasonable toseparate the elements into groups instead oftreating them together from the viewpoint of
increasing transmutation efficiency and reducing
disposal area.
To this end, our research group has beendeveloping several extractants and has
investigated their extraction properties. Recently,
we proposed a novel hydrometallurgical process
called SELECT (Solvent Extraction from Liquid
waste using Extractants of CHON‐type forTransmutation) to recycle nuclear materials andseparate actinides for transmutation. A
conceptual flow sheet of SELECT is shown in
Figure 1. The extractants used in this process
consist of carbon, hydrogen, oxygen, andnitrogen, and thus can be decomposed into
gases by incineration. This contributes toreducing the volume of secondary solid waste.

radioactive nuclides during the separation,
radiation tolerance is a critical requirement forthe process feasibility. Therefore, our researchgroup has also been investigating radiation
physics and chemistry research in conjunction
with the SELECT development.
A Monte‐Carlo particle‐transport code called
PHITS was employed to calculate the radiationdose absorbed by the SELECT solvents. A droplet
model combined with an approach using a
refraction boundary was proposed to simplify
and reduce the computational time needed tosimulate radiation‐energy transfer in theheterogeneous structures seen in thesolvent‐extraction process, such as emulsions
forming in the mixture of the organic (i.e.,
SELECT solvents) and aqueous (e.g., HLW)
solutions.1) The simulation results indicated thatthe dose absorbed by the extraction solvent
from alpha radiation depends upon the emulsion
structure, and that from beta and gamma
radiation depends upon the size of amixer‐settler apparatus.
The subsequent radiation impacts on theextractants degradation and extraction ability
were examined using a solvent test loop in
conjunction with cobalt‐60 gamma irradiation as
collaborative research with Idaho National
Laboratory (US).
N,N,N’,N’,N’’,N’’‐Hexaoctyl‐
nitrilotriacetamide (HONTA) was tested as an
extractant to separate MAs from REs in SELECT
process, and was found to decay exponentiallywith increasing dose, affording a dose coefficientof d = (4.48 ± 0.19) × 10–3 kGy–1.2)
Using the calculated absorbed dose and theobtained dose coefficient, the radiation
tolerance of the extractant in SELECT process
could be evaluated quantitatively.
Reference
1) T. Toigawa, et al., Solvent Extra. Ion Exch., 39, 74‐89,(2021).
2) T. Toigawa, et al., Phys. Chem. Chem. Phys., 23,1343‐1351 (2021).

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

Contact (Group Leader):BAN Yasutoshi
ban.yasutoshi@jaea.go.jp

Radiation Tolerance Evaluation of
SELECT Solvents
Because the extraction solvents will receive
radiation energy from various kinds of22

FY2020 NSEC Group Activity

Research Group for Nuclear Transmutation Systemnatural circulation state. The inner cylinder sets
above an ADS core to rectify the LBE(Lead‐Bismuth Eutectic) flow. By using thecomputational science, we could discuss therequirement of the inner cylinder.

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 ofconceptual design and testing by small‐scaleequipment for each component and material.
To improve ADS design, we are developing
analysis system consisting of particle transport,
thermal‐hydraulics, structure analysis and plant
behavior using many computational codes.

104

106

108

Proton

LBE inlet

VacuumLBE

ADS Conceptual Design Based on
Computational Science(a) Heat density distribution [W/m3]
573

673

773

Duct

Beam window

Beam window design
A design of a beam window which is a boundary
between an accelerator and a subcritical core is
one of the most important issues in the R&D of
ADS. We have developed the coupled analysis
system consisting of particle transport (PHITS),
thermal‐hydraulics (FLUENT) and structure
analyses (ANSYS) for the efficient beam window
design. Figure 1 presents calculation results by
the coupled analysis system. The system employs
the same calculation geometry and sharescalculation results such as heat density
calculated by PHITS or temperature calculated by
FLUENT. By using the temperature distribution
shown in Fig. 1 (b), the structural analysis isperformed for the calculation model of the beam
window. The system enables the efficient beam
window design and more feasible concept will becreated.

(b) Temperature distribution [K]Fig.1 Calculation results by beam window coupledanalysis system

Heat exchanger
of DRACS

LBE flowCore

Natural convection in reactor vessel
It is supposed that the ADS is safer thanconventional critical reactors because it isoperated in a subcritical state. Among transient
event for the typical ADS, all events except lossof heat sink (LOHS) satisfy the no‐damage
criteria1). To avoid the damage by LOHS, the ADS
equips Direct Reactor Auxiliary Cooling System(DRACS) to remove the decay heat. The mostimportant points of a DRACS operation are its
reliability and to ensure the flowrate in a natural
circulation state.
So, the CFD (Computation Fluid Dynamics)
analysis of the natural circulation was performed
to clarify the flowrate in the ADS reactor vessel.
The calculation results showed that the flowrate
in the natural circulation state became about
4.3 % of the nominal value and the decay heat
was removed adequately (Fig. 2). It was also
investigated the effect of an inner cylinder in theFig.2 Temperature distribution in reactor vessel
under natural circulation state

Reference
1) T. Sugawara, et al., Ann. Nucl. Energy, 55, 238‐247,(2013).

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

23

FY2020 NSEC Group Activity

Research Group for MA Transmutation Fuel Cycle
molten salts. NpCl3 was obtained by the reactionof Np‐Pd alloy with CdCl2 at 673 K in vacuum.
Figure 1 shows the X‐ray diffraction (XRD)
profiles of the products. These experimental
results suggest that (1) MAPd3 phase can beformed in spent MA nitride fuels, (2) MAs
existing in MAPd3 phases can be converted tochlorides, which is soluble in molten salts, by thechemical reaction with CdCl2.
This study contains the results of “R&D on
Nitride Fuel Cycle for MA Transmutation to
Enhance Safety and Economy” entrusted toJapan Atomic Energy Agency by the Ministry of
Education, Culture, Sports, Science andTechnology of Japan (MEXT).

Feasibility study on transmutation system showsthat 20 % of minor actinides (MAs) in the fuels
can be transmuted in one burning cycle of about
2 years. Reprocessing of the spent fuels isnecessary to transmute MAs remaining in the
spent fuels. Repeating fuel fabrication,transmutation, and reprocessing can transmute
most of MAs coming to the dedicated MA
transmutation fuel cycle in the double‐strata fuelcycle concept. We have been carrying out
research and development of the technology 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; this technique issuitable for reprocessing spent MA nitride fuels.

Fission Product (FP) Compounds
in the Spent MA Nitride Fuels

▲

▼

▼

Np-Pd/CdCl 2
reaction product

Intensity (a.u.)

Uranium(U)‐free MA nitride fuels have beenchosen as the first candidate for transmutationof MAs using accelerator drive system (ADS) in
JAEA. To develop reprocessing technology forhigh burnup spent fuels, the influences of thefission product elements (FPs) should beconsidered. Data on the chemical states of FPs in
the spent U‐free MA nitride fuels are very limited,
however, those for uranium nitride (UN) anduranium‐plutonium mixed nitride ((U,Pu)N) fuels
have been studied1). Rare earth elements (REs),
the most abundant group in FPs, are soluble tothe fuel to form solid solutions of nitrides1).
Existence of REs scarcely affect the conditions ofpyroprocessing (i.e., molten salt electrorefining),
because the chemical stability of RE nitrides are
similar to those of actinide nitrides2). On theother hand, the platinum group elements (Ru, Rh,Pd), the second most abundant group, tend to
precipitate out as the intermetallic compounds
such as (U,Pu) (Ru, Rh, Pd)31). Their chemical
stability can affect the conditions ofpyroprocessing. It was reported that UPd3 did
not dissolve by the molten salt electrorefining ofa burnup‐simulated UN sample2).
Therefore, we investigated chemical behavior of
platinum group elements coexistent with MA
nitride samples in this study3). The chemical
reaction of NpN synthesized via the
carbothermic reduction of 237NpO2, with Pd
powder at 1323 K in Ar gas flow made a Np‐Pd
alloy, in which NpPd3 was a main product.
Chlorination of Np‐Pd alloy was attempted using
CdCl2 which is considered to be used for
dissolving the residue of the electrorefining into

▲▲
▲ ▲

▲

：NpCl 3：Pd※：sample holder(W)

※

▼
▲
▲▲ ▲

×
●
NpN/Pdreaction product

※

※

▲
▲

▲
▲

▲
▼

▲

▼
▲ ▼※

●：NpPd 3
× ×：sample holder(Pt)

×

●

●

×

● ●

×

●
■
■
■

NpN

10

：NpN

■

■
■

20
2θ (deg.)

■

30

■■

40

Fig.1 XRD profiles of the products

Reference
1) Hj. Matzke, “Science of Advanced LMFBR Fuels,”
pp.428‐461 (1986).
2) T. Satoh, et al., J. Nucl. Sci. Technol. 46, 557‐563 (2009).
3) H. Hayashi, et.al., Abstract of 2021 Annual Meeting of
the AESJ, Paper No. 3H13 (2021) (in Japanese).

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

24

FY2020 NSEC Publications

Publication list
* Works with underlined numbers were published before
FY2020 (not included in the lists of previous NSEC reports).

Nuclear and LWR Engineering Division
Papers2) HPRL – International cooperation to identify andmonitor priority nuclear data needs for nuclear
applications, E. Dupont, M. Bossant, R. Capote,
A.D. Carlson, Y. Danon, M. Fleming, Z. Ge, H.
Harada, O. Iwamoto, N. Iwamoto, A. Kimura, A.J.
Koning, C. Massimi, A. Negret, G. Noguere, A.
Plompen, V. Pronyaev, G. Rimpault, S. Simakov, A.
Stankovskiy, W. Sun, A. Trkov, H. Wu & K.
Yokoyama, EPJ Web of Conf. 239, 15005 (2020).

1) Overview of the OECD‐NEA Working Party on
International
Nuclear
Data
Evaluation
Cooperation (WPEC), M. Fleming, D. Bernard, D.
Brown, M. Chadwick, C. de Saint Jean, E. Dupont,
Z. Ge, H. Harada, A. Hawari, M. Herman, O.
Iwamoto, I. Kodeli, A. Koning, F. Malvagi, D.
McNabb, R.W. Mills, G. Noguère, G. Palmiotti, A.
Plompen, M. Salvatores, V. Sobes, M. White & K.
Yokoyama, EPJ Web of Conf. 239, 15002 (2020).

Nuclear Data Center
Papers1) Neutron capture and total cross‐section
measurements of Gd‐155 and Gd‐157 at ANNRI
in J‐PARC, A. Kimura, S. Nakamura, O. Iwamoto,N. Iwamoto, H. Harada, T. Katabuchi, K. Terada,
J.‐i. Hori, Y. Shibahara & T. Fujii, EPJ Web of Conf.
239, 01012 (2020).
2) Recent progress of a code system DEURACS
toward deuteron nuclear data evaluation, S.
Nakayama, O. Iwamoto & Y. Watanabe, EPJ Web
of Conf. 239, 03014 (2020).
3) Toward next JENDL Fission Yield Data and Decay
Data, F. Minato, EPJ Web of Conf. 242, 05004(2020).
4) Status of JENDL, O. Iwamoto, N. Iwamoto, K.
Shibata, A. Ichihara, S. Kunieda, F. Minato & S.
Nakayama, EPJ Web of Conf. 239, 09002 (2020).
5) Evaluation of gamma‐ray strength function
based on measured gamma‐ray pulse‐heightspectra in time‐of‐flight neutron captureexperiments, N. Iwamoto, S. Nakamura, A.
Kimura, T. Katabuchi, G. Rovira, K. Y. Hara & O.
Iwamoto, EPJ Web of Conf. 239, 17016 (2020).
6) Thermal‐neutron capture cross sections andresonance integrals of the 243Am(n,γ)244gAm and243Am(n,γ)244m+gAm reactions, S. Nakamura, Y.
Shibahara, S. Endo & A. Kimura, J. Nucl. Sci. Tech.
58(3), 259 (2021).
7) JENDL/DEU‐2020: deuteron nuclear data libraryfor design studies of accelerator‐based neutron
sources, S. Nakayama, O. Iwamoto, Y. Watanabe& K. Ogata, J. Nucl. Sci. Tech. 58(7), 805 (2021).
8) Neutron capture cross sections of curium
isotopes measured with ANNRI at J‐PARC, S.
Kawase, A. Kimura, H. Harada, N. Iwamoto, O.
Iwamoto, S. Nakamura, M. Segawa & Y. Toh, J.
Nucl. Sci. Tech. 58(7), 764 (2021).
9) Neutron capture cross section measurements of
Am‐241 at the n_TOF facility, A. Oprea, et al. (Then_TOF Collaboration (H. Harada & A. Kimura)),
EPJ Web of Conf. 239, 01009 (2020).
10) Study of photon strength functions of Pu‐241
andCm‐245fromneutroncapturemeasurements, E. Mendoza, et al. (The n_TOF
Collaboration (A. Kimura)), EPJ Web of Conf. 239,
01015 (2020).
11) Measurement of the neutron capture cross‐section of Np‐237 using ANNRI at MLF/J‐PARC, G.
Rovira, T. Katabuchi, K. Tosaka, S. Matsuura, K.
Terada, O. Iwamoto, A. Kimura, S. Nakamura & N.
Iwamoto, EPJ Web of Conf. 239, 01017 (2020).
12) Measurement of the 242Pu(n, γ) cross section
from thermal to 500 keV at the Budapest
research reactor and CERN n_TOF‐EAR1 facilities,
J. Lerendegui‐Marco, et al. (The n_TOF
Collaboration (H. Harada & A. Kimura)), EPJ Web
of Conf. 239, 01019 (2020).
13) Measurement of the Cm‐244 capture crosssections at both CERN n_TOF experimental areas,
C. Massimi, et al. (The n_TOF Collaboration (A.
Kimura)), EPJ Web of Conf. 239, 01034 (2020).

25

FY2020 NSEC Publications14) Measurement and analysis of 155,157Gd(n,γ)
from thermal energy to 1 keV, V. Alcayne, et al.
(The n_TOF Collaboration (H. Harada & A.
Kimura)), EPJ Web of Conf. 239, 01041 (2020).
15) Fast Neutron Capture Reaction Data
Measurement of Minor Actinides forDevelopment of Nuclear Transmutation Systems,
T. Katabuchi, O. Iwamoto, J.‐i. Hori, A. Kimura, N.
Iwamoto, S. Nakamura, Y. Shibahara, K. Terada, G.
Rovira & S. Matsuura, EPJ Web of Conf. 239,
01044 (2020).
16) A new reference database for beta‐delayed
neutrons, P. Dimitriou, I. Dillmann, B. Singh, V.
Piksaikin, J.‐L. Tain, K. Rykaczewski, A. Algora, K.
Banerjee, I. Borzov, D. Cano‐Ott, S. Chiba, M.
Fallot, D. Foligno, R. Grzywacz, X.l. Huang, T.
Marketin, F. Minato, G. Mukherjee, B.‐C. Rasco,
A. Sonzogni & M. Verpelli, EPJ Web of Conf. 239,
04001 (2020).
17) Study of the neutron‐induced fission crosssection of Np‐237 at CERN's n_TOF facility over awide energy range, A. Stamatopoulos, et al. (Then_TOF Collaboration (H. Harada & A. Kimura)),
EPJ Web of Conf. 239, 05006 (2020).
18) First results of the 241Am(n,f) cross section
measurement at the Experimental Area 2 of then_TOF facility at CERN, Z. Eleme, et al. (Then_TOF Collaboration (A. Kimura)), EPJ Web ofConf. 239, 05014 (2020).
19) New reaction rates for the destruction of Be‐7
during big bang nucleosynthesis measured at
CERN/n_TOF and their implications on thecosmological lithium problem, A. Mengoni, et al.
(The n_TOF Collaboration (A. Kimura)), EPJ Web
of Conf. 239, 07001 (2020).
20) The Gd‐154 neutron capture cross section
measured at the n_TOF facility and its
astrophysical implications, M. Mastromarco, etal. (The n_TOF Collaboration (A. Kimura)), EPJ
Web of Conf. 239, 07003 (2020).
21) Accurate measurement of the standard
235U(n,f) cross section from thermal to 170 keV
neutron energy, S. Amaducci, et al. (The n_TOF
Collaboration (H. Harada & A. Kimura)), EPJ Web
of Conf. 239, 08002 (2020).
22) Overview of the OECD‐NEA Working Party on
International
Nuclear
Data
Evaluation
Cooperation (WPEC), M. Fleming, D. Bernard, D.
Brown, M. Chadwick, C. de Saint Jean, E. Dupont,
Z. Ge, H. Harada, A. Hawari, M. Herman, O.
Iwamoto, I. Kodeli, A. Koning, F. Malvagi, D.
McNabb, R.W. Mills, G. Noguère, G. Palmiotti, A.
Plompen, M. Salvatores, V. Sobes, M. White & K.
Yokoyama, EPJ Web of Conf. 239, 15002 (2020).

23) Results of the Collaborative International
Evaluated Library Organisation (CIELO) Project,
M. Fleming, M. Chadwick, D. Brown, R. Capote, Z.
Ge, M. Herman, A. Ignatyuk, T. Ivanova, O.
Iwamoto, A. Koning, A. Plompen & A. Trkov, EPJ
Web of Conf. 239, 15003 (2020).
24) International network of nuclear structure anddecay data evaluators, P. Dimitriou, S. Basunia, L.
Bernstein, J. Chen, Z. Elekes, X.l. Huang, A. Hurst,
H. Iimura, A. K. Jain, J. Kelley, T. Kibédi, F. Kondev,
S. Lalkovski, E. McCutchan, I. Mitropolsky, G.
Mukherjee, A. Negret, C. Nesaraja, N. Nica, S.
Pascu, A. Rodionov, B. Singh, S. Singh, M. Smith,
A. Sonzogni, J. Timár, J. Tuli, M. Verpelli, D. Yang
& V. Zerkin, EPJ Web of Conf. 239, 15004 (2020).
25) HPRL – International cooperation to identify
and monitor priority nuclear data needs fornuclear applications, E. Dupont, M. Bossant, R.
Capote, A.D. Carlson, Y. Danon, M. Fleming, Z. Ge,
H. Harada, O. Iwamoto, N. Iwamoto, A. Kimura,
A.J. Koning, C. Massimi, A. Negret, G. Noguere, A.
Plompen, V. Pronyaev, G. Rimpault, S. Simakov, A.
Stankovskiy, W. Sun, A. Trkov, H. Wu & K.
Yokoyama, EPJ Web of Conf. 239, 15005 (2020).
26) Status and perspectives of the neutron time‐of‐flight facility n_TOF at CERN, E. Chiaveri, et al.
(The n_TOF Collaboration (A. Kimura)), EPJ Web
of Conf. 239, 17001 (2020).
27) Study of the Li(d, xn) reaction for thedevelopment of accelerator‐based neutron
sources, Y. Watanabe, H. Sadamatsu, S. Araki, K.
Nakano, S. Kawase, T. Kin, Y. Iwamoto, D. Satoh,
M. Hagiwara, H. Yashima, T. Shima & S.
Nakayama, EPJ Web of Conf. 239, 20012 (2020).
28) Discovery of a new low energy neutron
resonance of Y‐89, T. Katabuchi, Y. Toh, M.
Mizumoto, T. Saito, K. Terada, A. Kimura, S.
Nakamura, H. Minghui, G. Rovira & M. Igashira,Eur. Phys. J. A 57, 4 (2020).
29) Transverse asymmetry of  rays from neutron‐
induced compound states of La‐140, T.
Yamamoto, T. Okudaira, S. Endo, H. Fujioka, K.
Hirota, T. Ino, K. Ishizaki, A. Kimura, M. Kitaguchi,
J. Koga, S. Makise, Y. Niinomi, T. Oku, K. Sakai, T.
Shima, H. M. Shimizu, S. Takada, Y. Tani, H.
Yoshikawa & T. Yoshioka, Phys. Rev. C 101(6),064624 (2020).
30) Development and application of a He‐3
Neutron Spin Filter at J‐PARC, T. Okudaira. T. Oku.
Ino, H. Hayashida, H. Kira, K. Sakai, K. Hiroi, S.
Takahashi, K. Aizawa, H. Endo, S. Endo, M. Hino,
K. Hirota, T. Honda, K. Ikeda, K. Kakurai, W.
Kambara, M. Kitaguchi, T. Oda, H. Ohshita, T.
Otomo, H.M. Shimizu, T. Shinohara, J. Suzuki & T.

26

FY2020 NSEC Publications
Yamamoto, Nucl. Inst. & Methods in Phys. Res., A
977, 164301 (2020).
31) Gamma‐ray spectra from thermal neutron
capture on gadolinium‐155 and natural
gadolinium, T. Tanaka, K. Hagiwara, E. Gazzola, A.
Ali, I. Ou, T. Sudo, P. K. Das, M. Singh Reen, R. Dhir,
Y. Koshio, M. Sakuda, A. Kimura, S. Nakamura, N.
Iwamoto, H. Harada, G. Collazuol, S. Lorenz, M.
Wurm, W. Focillon, M. Gonin & T. Yano, Prog.
Theor. Exp. Phys. 2020(4), 043D02 (2020).
32) A compact fission detector for fission‐tagging
neutron capture experiments with radioactive
fissile isotopes, M. Bacak, et al. (The n_TOF
Collaboration (H. Harada & A. Kimura)), Nucl. Inst.
& Methods in Phys. Res., A 969, 163981 (2020).
33) Neutron Capture on the s‐Process Branching
Point Tm‐171 via Time‐of‐Flight and Activation,
C. Guerrero, et al. (The n_TOF Collaboration (H.
Harada & A. Kimura)), Phys. Rev. Lett. 125(14),142701 (2020).
34) Investigation of the 240Pu(n,f) reaction at then_TOF/EAR2 facility in the 9 meV–6 MeV range,
A. Stamatopoulos, et al. (The n_TOF
Collaboration (H. Harada & A. Kimura)), Phys. Rev.
C 102(1), 014616 (2020).
35) Spallation and fragmentation cross sections for
168 MeV/nucleon Xe‐136 ions on proton,
deuteron, and carbon targets, X.H. Sun, H. Wang,
H. Otsu, H. Sakurai, D.S. Ahn, M. Aikawa, N.
Fukuda, T. Isobe, S. Kawakami, S. Koyama, T.
Kubo, S. Kubono, G. Lorusso, Y. Maeda, A.
Makinaga, S. Momiyama, K. Nakano, S.
Nakayama, M. Niikura, Y. Shiga, P.‐A. Söderström,
H. Suzuki, H. Takeda, S. Takeuchi, R. Taniuchi, Ya.
Watanabe, Yu. Watanabe, H. Yamasaki, X.F. Yang,
Y.L. Ye & K. Yoshida, Phys. Rev. C 101(6), 064623(2020).
36) Measurement of double‐differential thick‐target neutron yields of the C(d,n) reaction at 12,
20, and 30 MeV, Md K.A. Patwary, T. Kin, K. Aoki,
K. Yoshinami, M. Yamaguchi, Y. Watanabe, K.
Tsukada, N. Sato, M. Asai, T.K. Sato, Y. Hatsukawa& S. Nakayama, J. Nucl. Sci. Tech. 58(2), 252(2021).
37) Theoretical study of Nb isotope productions bymuon capture reaction on Mo‐100, M. Ciccarelli,
F. Minato & T. Naito, Phys. Rev. C 102(3), 034306(2020).
38) Evaluation of fission product yields andassociated covariance matrices, K. Tsubakihara, S.
Okumura, C. Ishizuka, T. Yoshida, F. Minato & S.

Chiba, J. Nucl. Sci. Tech. 58(2), 151 (2021).
39) Measurement of cesium isotopic ratio by
thermal ionization mass spectrometry forneutron capture reaction studies on Cs‐135, Y.
Shibahara, S. Nakamura, A. Uehara, T. Fujii, S.
Fukutani, A. Kimura & O. Iwamoto, J. Radioanal.
Nucl. Chem. 325(1), 155 (2020).
40) Low‐lying electric and magnetic dipole
strengths in Pb‐207, T. Shizuma, F. Minato, M.
Omer, T. Hayakawa, H. Ohgaki & S. Miyamoto,Phys. Rev. C 103(2), 024309 (2021).
41) High‐spin states in S‐35, S. Go, E. Ideguchi, R.
Yokoyama, N. Aoi, F. Azaiez, K. Furutaka, Y.
Hatsukawa, A. Kimura, K. Kisamori, M. Kobayashi,
F. Kitatani, M. Koizumi, H. Harada, I. Matea, S.
Michimasa, H. Miya, S. Nakamura, M. Niikura, H.
Nishibata, N. Shimizu, S. Shimoura, T. Shizuma, M.
Sugawara, D. Suzuki, M. Takaki, Y. Toh, Y. Utsuno,
D. Verney & A. Yagi, Phys. Rev. C 103(3), 034327(2021).
42) Offline collinear laser spectroscopy of barium II
toward measurement of RIs at SLOWRI facility, M.
Tajima, A. Takamine, Y. Sasaki, T. Asakawa, H.
Iimura, M. Wada, H.A. Schuessler, Y. Matsuo & H.
Ueno, RIKEN Accel. Prog. Rep. 53, 15 (2019).
43) First confirmation of stopped RIs at parasitic gas
cell with new approach, T. 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,
T. Sumikama, H. Suzuki, H. Takeda, M. Tanigaki, H.
Tomita, K. Yoshida & H. Ishiyama, RIKEN Accel.
Prog. Rep. 53, 105 (2019).
44) Stopping examination for high‐energy RI beams
in the parasitic gas cell, T. 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, RIKEN Accel. Prog. Rep. 53,
106 (2019).
45) Collinear laser spectroscopy of Ba+ in 6s 2S1/2‐
6p2P3/2 transition, Y. Sasaki, M. Tajima, A.
Takamine, H. Iimura, M. Wada, Y. Matsuo & H.
Ueno, RIKEN Accel. Prog. Rep. 53, 129 (2019).
46) CO2‐1 Measurement for thermal neutron
capture cross sections and resonance integrals of
the 243Am(n,)244gAm, 244m+gAm reactions, S.
Nakamura, S. Endo, A. Kimura & Y. Shibahara,
KURNS PROGRESS REPORT 2019, 132 (2020).

27

FY2020 NSEC Publications
JAEA Reports
1) Recent progress and future plan on the JENDL
project, O. Iwamoto, JAEA‐Conf 2020‐001 (Proc.
the 2019 Symposium on Nuclear Data November
28‐30, 2019, Kyushu University, Chikushi Campus,
Fukuoka, Japan), 11 (2020).
2) Neutron Capture Cross Section Measurement of
Minor Actinides in Fast Neutron Energy Region
for Study on Nuclear Transmutation System, T.
Katabuchi, J.‐i. Hori, N. Iwamoto, O. Iwamoto, A.
Kimura, S. Nakamura, Y. Shibahara, K. Terada, K.
Tosaka, S. Endo, G. Rovira, Y. Kodama & H.
Nakano, JAEA‐Conf 2020‐001 (Proc. the 2019
Symposium on Nuclear Data November 28‐30,
2019, Kyushu University, Chikushi Campus,
Fukuoka, Japan), 5 (2020).

3) Measurement of neutron total cross‐section of
Nb‐93 at J‐PARC MLF ANNRI, S. Endo, A. Kimura,
S. Nakamura, O. Iwamoto, N. Iwamoto, Y. Toh, M.
Segawa, M. Maeda & M. Tsuneyama, JAEA‐Conf
2020‐001 (Proc. the 2019 Symposium on Nuclear
Data November 28‐30, 2019, Kyushu University,
Chikushi Campus, Fukuoka, Japan), 113 (2020).
4) High‐Energy Measurement of the Neutron
Capture Cross Section of Np‐237, G. Rovira, T.
Katabuchi, K. Tosaka, S. Matsuura, K. Terada, Y.
Kodama, H. Nakano, O. Iwamoto, A. Kimura, S.
Nakamura & N. Iwamoto, JAEA‐Conf 2020‐001(Proc. the 2019 Symposium on Nuclear Data
November 28‐30, 2019, Kyushu University,
Chikushi Campus, Fukuoka, Japan), 119 (2020).

Research Group for Reactor Physics and Standard Nuclear Code System
Papers1) Optimization of light water reactor High Level
Waste disposal scenario in the situation ofdelayed reprocessing with existing anddemonstrated technology, Y. Fukaya, Annals Nucl.
Energy 144, 107503 (2020).
2) The joint evaluated fission and fusion nuclear
data library, JEFF‐3.3, A.J.M. Plompen, O.
Cabellos, C. De Saint Jean, M. Fleming, A. Algora,
M. Angelone, P. Archier, E. Bauge, O. Bersillon, A.
Blokhin, F. Cantargi, A. Chebboubi, C. Diez, H.
Duarte, E. Dupont, J. Dyrda, B. Erasmus, L. Fiorito,
U. Fischer, D. Flammini, D. Foligno, M.R. Gilbert,
J.R. Granada, W. Haeck, F.‐J. Hambsch, P.
Helgesson, S. Hilaire, I. Hill, M. Hursin, R. Ichou,
R. Jacqmin, B. Jansky, C. Jouanne, M.A. Kellett,
D.H. Kim, H.I. Kim, I. Kodeli, A.J. Koning, A. Yu.
Konobeyev, S. Kopecky, B. Kos, A. Krása, L.C. Leal,
N. Leclaire, P. Leconte, Y.O. Lee, H. Leeb, O. Litaize,
M. Majerle, J.I Márquez Damián, F. Michel‐Sendis, R.W. Mills, B. Morillon, G. Noguère, M.
Pecchia, S. Pelloni, P. Pereslavtsev, R.J. Perry, D.
Rochman, A. Röhrmoser, P. Romain, P. Romojaro,
D. Roubtsov, P. Sauvan, P. Schillebeeckx, K.H.
Schmidt, O. Serot, S. Simakov, I. Sirakov, H.
Sjöstrand, A. Stankovskiy, J.C. Sublet, P. Tamagno,
A. Trkov, S. van der Marck, F. Álvarez‐Velarde, R.
Villari, T.C. Ware, K. Yokoyama & G. Žerovnik, Eur.
Phys. J. A 56, 181 (2020).
3) Development of FRENDY Nuclear Data
Processing Code: Generation Capability of Multi‐group Cross Sections from ACE File, A. Yamamoto,

T. Endo & K. Tada, Trans. the American Nucl. Soc.
122(1), 714 (2020).
4) A pseudo‐material method for graphite with
arbitrary porosities in Monte Carlo criticality
calculations, S. Okita, Y. Nagaya &Y. Fukaya, J.
Nucl. Sci. Tech. 58(9), 992 (2021).
5) INVESTIGATION OF APPROPRIATE LADDERNUMBER ON PROBABILITY TABLE GENERATION,
K.Tada, EPJ Web of Conf. 247, 09002 (2021).
6) A negative probability table problem of heating
number in FENDL‐3.1d ACE file, C. Konno & S.
Kwon, Proc. SNA+MC2020 (Joint Int. Conf.
Supercomputing in Nucl. Applications + Monte
Carlo 2020) 320 (2020).
7) Benchmarks of depletion and decay heatcalculation between MENDEL and MARBLE, K.
Yokoyama & S. Lahaye, Proc. SNA+MC2020(Joint Int. Conf. Supercomputing in Nucl.
Applications + Monte Carlo 2020) 109 (2020).
8) Overview of the OECD‐NEA Working Party on
International
Nuclear
Data
Evaluation
Cooperation (WPEC), M. Fleming, D. Bernard, D.
Brown, M. Chadwick, C. de Saint Jean, E. Dupont,
Z. Ge, H. Harada, A. Hawari, M. Herman, O.
Iwamoto, I. Kodeli, A. Koning, F. Malvagi, D.
McNabb, R.W. Mills, G. Noguère, G. Palmiotti, A.
Plompen, M. Salvatores, V. Sobes, M. White & K.
Yokoyama, EPJ Web of Conf. 239, 15002 (2020).
9) HPRL – International cooperation to identify andmonitor priority nuclear data needs for nuclear
applications, E. Dupont, M. Bossant, R. Capote,28

FY2020 NSEC Publications
A.D. Carlson, Y. Danon, M. Fleming, Z. Ge, H.
Harada, O. Iwamoto, N. Iwamoto, A. Kimura, A.J.
Koning, C. Massimi, A. Negret, G. Noguere, A.

Plompen, V. Pronyaev, G. Rimpault, S. Simakov,
A. Stankovskiy, W. Sun, A. Trkov, H. Wu & K.
Yokoyama, EPJ Web of Conf. 239, 15005 (2020).

JAEA Reports
1) HAND: A Handy criticality analysis tool for fueldebris, K. Tada, JAEA‐Data/Code 2020‐014(2020).
2) Development of multi‐group neutron activation
cross‐section library from JENDL/AD‐2017, C.

Konno, JAEA‐Conf 2020‐001 (Proc. the 2019
Symposium on Nuclear Data November 28‐30,
2019, Kyushu University, Chikushi Campus,
Fukuoka, Japan), 193 (2020).

Research Group for Nuclear Sensing
PapersHarada, K. Oikawa, Y. Matsumoto, J.D. Parker, T.
Shinohara, Y. Nagae & I. Sato, JPS Conf. Proc. 33,
011074 (2021).
8) Development of Event‐Type Neutron Imaging
Detectors at the Energy‐Resolved Neutron
Imaging System RADEN at J‐PARC, J.D. Parker, M.
Harada, H. Hayashida, K. Hiroi, T. Kai, Y.
Matsumoto, T. Nakatani, K. Oikawa, M. Segawa,T. Shinohara, Y. Su, A. Takada, T. Tanimori & Y.
Kiyanagi, Mater. Res. Proc. 15(NeutronRadiography ‐ WCNR‐11), 102 (2020).
9) The energy‐resolved neutron imaging system,
RADEN, T. Shinohara, T. Kai, K. Oikawa, T.
Nakatani, M. Segawa, K. Hiroi, Y. Su, M. Ooi, M.
Harada, H. Iikura, H. Hayashida, J.D. Parker, Y.
Matsumoto, T. Kamiyama, H Sato & Y. Kiyanagi,Rev. Sci. Inst. 91(4), 43302 (2020).
10) Neutron capture cross sections of curium
isotopes measured with ANNRI at J‐PARC, S.
Kawase, A. Kimura, H. Harada, N. Iwamoto, O.
Iwamoto, S. Nakamura, M. Segawa & Y. Toh, J.
Nucl. Sci. Tech. 58(7), 764 (2021).
11) Discovery of a new low energy neutron
resonance of Y‐89, T. Katabuchi, Y. Toh, M.
Mizumoto, T. Saito, K. Terada, A. Kimura, S.
Nakamura, H. Minghui, G. Rovira & M. Igashira,Eur. Phys. J. A 57, 4 (2020).
12) High‐spin states in S‐35, S. Go, E. Ideguchi, R.
Yokoyama, N. Aoi, F. Azaiez, K. Furutaka, Y.
Hatsukawa, A. Kimura, K. Kisamori, M. Kobayashi,
F. Kitatani, M. Koizumi, H. Harada, I. Matea, S.
Michimasa, H. Miya, S. Nakamura, M. Niikura, H.
Nishibata, N. Shimizu, S. Shimoura, T. Shizuma, M.
Sugawara, D. Suzuki, M. Takaki, Y. Toh, Y. Utsuno,
D. Verney & A. Yagi, Phys. Rev. C 103(3), 034327(2021).

1) Analytical method for the determination of At‐
211 using an α‐scintillation camera system andthin‐layer chromatography, M. Segawa, I.
Nishinaka, Y. Toh & M. Maeda, J. Radioanal. Nucl.
Chem. 326(1), 773 (2020).
2) Study of shields against D‐T neutrons for Prompt
Gamma‐ray Analysis apparatus in Active‐N, K.
Furutaka & Y. Toh, Proc. SNA+MC2020 (Joint Int.
Conf. Supercomputing in Nucl. Applications +Monte Carlo 2020) 297 (2020).
3) Photoneutron detection in lightning by
gadolinium orthosilicate scintillators, Y. Wada, K.
Nakazawa, T. Enoto, Y. Furuta, T. Yuasa, K.
Makishima & H. Tsuchiya, Phys. Rev. D 101(10),102007 (2020).
4) Photonuclear Reactions in Lightning: 1.
Verification and Modeling of Reaction and
Propagation Processes, Y. Wada, T. Enoto, K.
Nakazawa, H. Odaka, Y. Furuta & H. Tsuchiya, J.
Geophys.
Res.:
Atmospheres
125(20),e2020JD033193 (2020).
5) Photonuclear Reactions in Lightning: 2.
Comparison
BetweenObservation
andSimulation Model, Y. Wada, T. Enoto, K.
Nakazawa, T. Yuasa, Y. Furuta, H. Odaka, K.
Makishima & H. Tsuchiya, J. Geophys. Res.:
Atmospheres 125(20), e2020JD033194 (2020).
6) Thundercloud Project: Exploring high‐energy
phenomena in thundercloud and lightning, T.
Yuasa, Y. Wada, T. Enoto, Y. Furuta, H. Tsuchiya, S.
Hisadomi, Y. Tsuji, K. Okuda, T. Matsumoto, K.
Nakazawa, K. Makishima, S. Miyake & Y. Ikkatai,
Prog. Theor. Exp. Phys. 2020(10), 103H01 (2020).
7) Feasibility study of PGAA for boride identificationin simulated melted core materials, Y.
Tsuchikawa, Y. Abe, Y. Ohishi, T. Kai, Y. Toh, M.
Segawa, M. Maeda, A. Kimura, S. Nakamura, M.

29

FY2020 NSEC Publications
JAEA Reports
1) Stellar Neutron Capture Cross Section of Ir‐191,
M. Tsuneyama, M. Segawa, S. Endo, S. Nakamura,
M. Maeda, A. Kimura & Y. Toh, MLF Annual
Report (J‐PARC Annual Report 2019 Vol.2
Materials and Life Science Experimental Facility)
82 (2021).
2) Measurement of neutron total cross‐section of

Nb‐93 at J‐PARC MLF ANNRI, S. Endo, A. Kimura,
S. Nakamura, O. Iwamoto, N. Iwamoto, Y. Toh, M.
Segawa, M. Maeda & M. Tsuneyama, JAEA‐Conf
2020‐001 (Proc. the 2019 Symposium on Nuclear
Data November 28‐30, 2019, Kyushu University,
Chikushi Campus, Fukuoka, Japan), 113 (2020).

Development Group for Thermal‐Hydraulics Technology
Papersreaction model in JUPITER code, P.g. Chai, S.
Yamashita & H. Yoshida, Annals Nucl. Energy 145,
107606 (2020).
7) Numerical Simulation of Liquid Jet Behavior in
Shallow Pool by Interface Tracking Method, T.
Suzuki, H. Yoshida, N. Horiguchi, S. Yamamura &Y. Abe, Proc. ICONE2020, ICONE2020‐16213(2020).
8) Locally mesh‐refined lattice Boltzmann method
for fuel debris air cooling analysis on GPU
supercomputer, N. Onodera, Y. Idomura, S.
Uesawa, S. Yamashita & H. Yoshida, MechanicalEng. J. 7(3), 19‐00531 (2020).
9) Computational approach to the evaluation offission product behaviors, S. Miwa, K. Nakajima,
C. Suzuki, R. Muhammad, E. Suzuki, N. Horiguchi& M Osaka, Proc. SNA+MC2020 (Joint Int. Conf.
Supercomputing in Nucl. Applications + Monte
Carlo 2020) 253 (2020).
10) Experimental study on transport behavior ofcesium iodide in the reactor coolant system
under LWR severe accident conditions, N.
Miyahara, S. Miwa, M. Gouëllo, J. Imoto, N.
Horiguchi, I. Sato & M. Osaka, J. Nucl. Sci. Tech.
57(12), 1287 (2020).

1) Observation of aerosol particle capturing
behavior near gas‐liquid interface, S. Uesawa &H. Yoshida, Mechanical Eng. J. 7(3), 19‐00539(2020).
2) Macrolayer Formation Model for Prediction of
Critical Heat Flux in Saturated and Subcooled
Pool Boiling, A. Ono, H. Sakashita & H. Yoshida,
Heat Transfer Eng. ‐, Latest Article (2020).
3) Preliminary analysis of sodium experimental
apparatus PLANDTL‐2 for development ofevaluation method for thermal‐hydraulics inreactor vessel of sodium fast reactor under
decay heat removal system operation condition,
A. Ono, M. Tanaka, Y. Miyake, E. Hamase, T. Ezure,
Mechanical Eng. J. 7(3), 19‐00546 (2020).
4) Numerical Simulation of Micro Particles Motionin Two‐Phase Bubbly Flow, H. Yoshida & S.
Uesawa, Proc. ICONE2020, ICONE2020‐16393(2020).
5) A Numerical Simulation Method for CoreInternals Behavior in Severe Accident
Conditions: Chemical Reaction Analyses in Core
Structures by JUPITER, S. Yamashita, C. Kino & H.
Yoshida, Proc. ICONE2020, ICONE2020‐16817(2020).
6) Development and validation of the eutectic

Fuels and Materials Engineering Division
Research Group for Corrosion Resistant Materials
Papers境1) Effect of seawater components on corrosion rateof steel in air/solution alternating condition, K.
Otani, T. Tsukada, F. Ueno & C. Kato, 材料と環

Zairyo‐to‐Kankyo 69(9), 246 (2020) (inJapanese).
2) 我が国初の軽水型発電炉 JPDR における腐食30

FY2020 NSEC Publications
High‐Purity Type 316 Stainless‐Steel by Cu2+ in
NaCl, T. Aoyama, H. Ogawa, C. Kato & F. Ueno,
Metals 11(3), 511 (2021).

割 れ 損 傷 事 例 , T. Tsukada & Y. Soma,
Maintenology 19(4), 37 (2021) (in Japanese).
3) Decrease in Pitting Corrosion Resistance of Extra‐

JAEA Report
1) Estimation of Oxygen Consumption Amount in
LBE‐cooled Accelerator‐Driven System, T.

Sugawara & A. Komatsu, JAEA‐Research 2020‐016 (2021) (in Japanese).

Research Group for Radiation Materials Engineering
Papers1) Evaluation of Mechanical Properties andMaterials Design based on Atomistic Simulations,
T. Tsuru, ま て り あ Materia Japan 60(1), 25(2021) (in Japanese).
2) Comprehensive Understanding of Hillocks and
Ion Tracks in Ceramics Irradiated with Swift
Heavy Ions, N. Ishikawa, T. Taguchi & H. Ogawa,
Quantum Beam Sci. 4(4), 43 (2020).
3)
Hydrogen‐accelerated
spontaneous
microcracking in high‐strength aluminium alloys,
T. Tsuru, K. Shimizu, M. Yamaguchi, M. Itakura, K.
Ebihara, A. Bendo, K. Matsuda & H. Toda, Sci.
Reports 10, 1998 (2020).
4) High‐temperature creep deformation in FeCrAl‐
oxide dispersion strengthened alloy cladding, S.
Ukai, S. Kato, T. Furukawa & S. Ohtsuka, Mater.
Sci. Eng.: A 794, 139863 (2020).
5) Degradation prediction using displacement
damage dose method for AlInGaP solar cells bychanging displacement threshold energy underirradiation with low‐energy electrons, Y. Okuno,
N. Ishikawa, M. Akiyoshi, H. Ando, M. Harumoto& M. Imaizumi, Jpn J. Applied Phys. 59(7),074001 (2020).
6) Microstructure and texture evolution and ring‐tensile properties of recrystallized FeCrAl ODS
cladding tubes, S.M.S. Aghamiria, T. Sowa, S.
Ukai, N. Oono, K. Sakamoto & S. Yamashita,
Mater. Sci. Eng.: A 771, 138636 (2020).
7) Corrosion behaviour of Al‐added high Mnaustenitic steels in molten lead bismuth eutectic
with saturated and low oxygen concentrations at
450 oC, H.r. Wang, H. Yu, S. Kondo, N. Okubo & R.
Kasada, Corrosion Sci. 175, 108864 (2020).
8) Relationship between the microstructure andlocal corrosion properties of weld metal inaustenitic stainless steels, S. Tokita, K. Kadoi, S.
Aoki & H. Inoue, Corrosion Sci. 175, 108867(2020).
9) Visualizing cation vacancies in Ce:Gd3Al2Ga3O12

scintillators by gamma‐ray‐induced positronannihilation lifetime spectroscopy, K. Fujimori, M.
Kitaura, Y. Taira, M. Fujimoto, H.sh. Zen, S.
Watanabe, K. Kamada, Y. Okano, M. Katoh, M.
Hosaka, J.‐i. Yamazaki, T. Hirade, Y. Kobayashi & A.
Ohnishi, Applied Phys. Express 13(8), 085505(2020).
10) Irradiation Effects of Swift Heavy Ions Detectedby Refractive Index Depth Profiling, H. Amekura,
R. Li, N. Okubo, N. Ishikawa & F. Chen, Quantum
Beam Sci. 4(4), 39 (2020).
11) Swift heavy ion irradiation to non‐amorphizable
CaF2 and amorphizable Y3Al5O12 (YAG) crystals, H.
Amekura, R. Li, N. Okubo, N. Ishikawa & F. Chen,
Nucl. Inst. & Methods in Phys. Res., B 474, 78(2020).
12) Matrix‐material dependence on the elongationof embedded gold nanoparticles induced by 4
MeV C60 and 200 MeV Xe ion irradiation, R. Li, K.
Narumi, A. Chiba, Y. Hirano, D. Tsuya, S.
Yamamoto, Y. Saitoh, N. Okubo, N. Ishikawa, C.
Pang, F. Chen & H. Amekura, Nanotechnology
31(26), 265606 (2020).
13) Tomography for Bridging Nano and Macro:Semi‐spontaneous Interfacial Debonding, H.
Toda, M. Yamaguchi, T. Tsuru, K. Shimizu, K.
Matsuda & K. Hirayama, ま て り あ Materia
Japan 60(1), 13 (2021) (in Japanese).
14) Dependences of Grain Size and Strain‐Rate on
Deformation Behavior of Commercial Purity
Titanium Processed by Multi‐Directional Forging,
S. Yamamoto, Y. Miyajima, C. Watanabe, R.
Monzen, T. Tsuru & H. Miura, Mater. Trans.
61(12), 2320 (2020).
15) Brittle‐fracture simulations of curved cleavage
cracks in α‐iron: A molecular dynamics study, T.
Suzudo, K. Ebihara & T. Tsuru, AIP Advances10(11), 115209 (2020).
16) Change in damping capacity arising from twin‐boundary
segregationinsolid‐solution

31

FY2020 NSEC Publications
Bendo, K. Matsuda, K. Nishimura, N. Nunomura,
T. Tsuchiya, S.g. Lee, C.D. Marioara, T. Tsuru, M.
Yamaguchi, K. Shimizu & H. Toda, Mater. Sci.
Tech. 36(15), 1621 (2020).
19) Non‐Basal Dislocation Nucleation Site of Solid
Solution Magnesium Alloy, H. Somekawa, D.A.
Basha, A. Singh, T. Tsuru & M. Yamaguchi, Mater.
Trans. 61(6), 1172 (2020).
20) Spin conversion reaction of spin‐correlated
ortho‐positronium and radical in liquids, T.
Hirade, Proc. APSRC 2020 (the 8th Asia PacificSymposium on Radiation Chemistry) 1 (2020).

magnesium alloys, H. Somekawa, D.A. Basha, A.
Singh, T. Tsuru & H. Watanabe, Philosophical
Magazine Lett. 100(10), 494 (2020).
17) Spontaneous debonding behaviour ofreinforcement fine particles in aluminium;
Toward high‐strength metallic materials
development, H. Toda, T. Tsuru, M. Yamaguchi, K.
Matsuda, K. Shimizu & K. Hirayama, 化 学
Chemistry 75(10), 48 (2020) (in Japanese).
18) The possible transition mechanism for themeta‐stable phase in the 7xxx aluminium, A.

JAEA Report
1) Manufacturing Miniature Beam Window for
Accelerator‐Driven System by Cutting T91 Steel,
N. Watanabe, T. Sugawara, N. Okubo & K.

Nishihara, JAEA‐Technology 2020‐026 (2021) (inJapanese).

Book
合金 : カクテル効果が生み出す多彩な新物
性 / Uchida Rokakuho (2020) (in Japanese).

1) "Chapter 4, Modeling of mechanical properties",
S. Ogata, T. Tsuru & K. Yuge, ハイエントロピー

Research Group for High Temperature Science on Fuel Materials
Papers629 (2021).
3) Solidification and re‐melting mechanisms of SUS‐
B4C eutectic mixture, T. Sumita, T. Kitagaki, M.
Takano & A. Ikeda‐Ohno, J. Nucl. Mater. 543,
152527 (2021).
4) Flexible fuel cycle system for the effective
management of plutonium, T. Fukasawa, K.
Hoshino, J. Yamashita & M. Takano, J. Nucl. Sci.
Tech. 57(11), 1215 (2020).

1) Experimental evaluation of Sr and Ba distribution
in ex‐vessel debris under a temperature gradient,
A. Sudo, T. Sato, H. Ogi & M. Takano, J. Nucl. Sci.
Tech. 58(4), 473 (2021).
2) Distribution of studtite and metastudtite
generated on the surface of U3O8: application ofRaman imaging technique to uranium
compound, R. Kusaka, Y. Kumagai, T. Yomogida,
M. Takano, M. Watanabe, T. Sasaki, D. Akiyama,
N. Sato & A. Kirishima, J. Nucl. Sci. Tech. 58(6),JAEA Reports
1) Design and demonstration of the prototype
nitrogen circulation refining system for nitride
fuel fabrication (Contract research), T. Iwasa & M.
Takano, JAEA‐Tech. 2020‐024 (2021) (inJapanese).
2) Survey of N‐15 isotopic enrichment plant and its
cost for nitride fuel fabrication (Contract
research), M. Takano, JAEA‐Review 2020‐080(2021) (in Japanese).
3) Measurement of Plutonium Spectrum using
Laser Induced Breakdown Spectroscopy ‐High
Resolution Spectroscopy (350‐670nm)‐, K.
Akaoka, M. Oba, M. Miyabe, H. Otobe & I.
Wakaida, JAEA‐Res. 2020‐001 (2020) (inJapanese).

Book1) "7.05 ‐ Thermodynamic and Thermophysical
Properties of the Actinide Nitrides", M. Uno, T.

Nishi & M. Takano, Comprehensive Nuclear
Materials (2nd Ed.) Vol.7, 202 / Springer (2020).

32

FY2020 NSEC Publications

Development Group for LWR Advanced Technology
PapersICONE2020, ICONE2020‐16783 (2020).
5) Investigation of high‐temperature chemicalinteraction of calcium silicate insulation andcesium hydroxide, M. Rizaal, K. Nakajima, T. Saito,
M. Osaka & K. Okamoto, J. Nucl. Sci. Tech. 57(9),1062 (2020).
6) Experimental study on transport behavior ofcesium iodide in the reactor coolant system
under LWR severe accident conditions, N.
Miyahara, S. Miwa, M. Gouëllo, J. Imoto, N.
Horiguchi, I. Sato & M. Osaka, J. Nucl. Sci. Tech.
57(12), 1287 (2020).
7) Synthesis of simulated fuels containing CsI undergas‐tight condition, J.Z. Liu, S. Miwa, K. Nakajima& M. Osaka, Nucl. Mater. Energy 26, 100916(2021).
8) Room‐temperature adsorption behavior ofcesium onto calcium silicate insulation, M. Rizaal,
T. Saito, K. Okamoto, N. Erkan, K. Nakajima & M.
Osaka, Mechanical Eng. J. 7(3), 19‐00563 (2020).

1) Study on chemisorption model of cesiumhydroxide onto stainless steel type 304, K.
Nakajima, S. Nishioka, E. Suzuki & M. Osaka,
Mechanical Eng. J. 7(3), 19‐00564 (2020).
2) Computational approach to the evaluation offission product behaviors, S. Miwa, K. Nakajima,
C. Suzuki, R. Muhammad, E. Suzuki, N. Horiguchi& M Osaka, Proc. SNA+MC2020 (Joint Int. Conf.
Supercomputing in Nucl. Applications + Monte
Carlo 2020) 253 (2020).
3) Evaluation on the crystal structure of ningyoiteusing XRD analysis and DFT calculation, C.
Suzuki, M. Osaka & T. Nakagiri, Proc.
SNA+MC2020 (Joint Int. Conf. Supercomputing
in Nucl. Applications + Monte Carlo 2020) 131(2020).
4) Corrosion Property of Container Using Hybrid
Material for Thermal Decomposition Process of
Sulfuric Acid, I. Ioka, Y. Kuriki, J. Iwatsuki, D.
Kawai, H. Yokota, Y. Inagaki & S. Kubo, Proc.

Patent1) Ioka I., H. Iwatsuki & Kuriki Y., “COMPOSITE
MATERIAL, SULFURIC ACID DECOMPOSITIONVESSEL USING THE SAME, AND HYDROGEN

PRODUCING APPARATUS”, Japanese Patent
6731613 (2020.07.09)

Nuclear Chemistry Division
Research Group for Radiochemistry
Papers4) Density functional modeling of Am3+/Eu3+
selectivity with diethylenetriaminepentaacetic
acid and its bisamide chelates., M. Kaneko, Y.
Sasaki, M. Matsumiya, M. Nakase & K. Takeshita,
J. Nucl. Sci. Tech. 58(5), 515 (2021).
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) Simultaneous separation of Am and Cm from Nd
and Sm by multi‐step extraction using the
TODGA‐DTPA‐BA‐HNO3 system, Y. Sasaki, K.
Morita, M. Matsumiya & M. Nakase, Radiochim.
Acta 108(9), 689 (2020).
7) Extraction and Separation between Light and1) Liquid interfaces related to lanthanide andactinide chemistry studied using vibrational sum
frequency generation spectroscopy, R. Kusaka, J.
Nucl. Radiochem. Sci. 20, 28 (2020).
2)
Applicationofphotoluminescencemicrospectroscopy: a study on transfer of uranyl
and europium ions on dry silica gel plate, R.
Kusaka & M. Watanabe, J. Nucl. Sci. Tech. 57(9),1046 (2020).
3) Distribution of studtite and metastudtite
generated on the surface of U3O8: application ofRaman imaging technique to uranium
compound, R. Kusaka, Y. Kumagai, T. Yomogida,
M. Takano, M. Watanabe, T. Sasaki, D. Akiyama,
N. Sato & A. Kirishima, J. Nucl. Sci. Tech. 58(6),629 (2021).

33

FY2020 NSEC Publications
Heavy Lanthanides by N,N,N',N'‐Tetraoctyl‐
diglycolamide from Organic Acid, Y. Sasaki, M.
Matsumiya, M. Nakase & K. Takeshita, Chem. Lett.
49(10), 1216 (2020).
8) Basic Research on Batchwise Multi‐stage
Extractions Using TODGA for Dy/Nd Separation,
Y. Sasaki, M. Matsumiya & Y. Tsuchida, AnalyticalSci. 36(11), 1303 (2020).
9) Fundamental Study on Multistage Extraction
Using TDdDGA for Separation of Lanthanides
Present in Nd Magnets, Y. Sasaki, K. Morita, M.
Matsumiya, R. Ono & H. Shiroishi, JOM 73(4),1037 (2021).
10) Effect of Oxygen‐Donor Charge on Adjacent
Nitrogen‐Donor Interactions in Eu3+ Complexesof Mixed N,O‐Donor Ligands Demonstrated on a
10‐Fold [Eu(TPAMEN)]3+ Chelate Complex, K.
Schnaars, M. Kaneko & K. Fujisawa, Inorg. Chem.
60(4), 2477 (2021).
11) Radiation‐induced effects on the extraction
properties of hexa‐n‐octylnitrilo‐triacetamide(HONTA) complexes of americium and europium,
T. Toigawa, D.R. Peterman, D.S. Meeker, T.S.
Grimes, P.R. Zalupski, S.P. Mezyk, A.R. Cook, S.
Yamashita, Y. Kumagai, T. Matsumura & G.P.

Horne, Phys. Chem. Chem. Phys. 23(2), 1343
(2021).
12) Re‐evaluation of Radiation‐Energy Transfer toan Extraction Solvent in a Minor‐Actinide‐
Separation Process Based on Consideration ofRadiation Permeability, T. Toigawa, Y. Tsubata, T.
Kai, T. Furuta, Y. Kumagai & T. Matsumura,
Solvent Extr. Ion Exch. 39(1), 74 (2021).
13) Complexation and bonding studies on[Ru(NO)(H2O)5]3+ with nitrate ions by using
density functional theory calculation, A. Kato, M.
Kaneko & S. Nakashima, RSC Adv. 10(41), 24434(2020).
14) Trichotomic separation of light and heavy
lanthanides and Am by batchwise multi‐stage
extractions using TODGA, M. Matsumiya, Y.
Tsuchida, Y. Sasaki, R. Ono, M. Nakase & K.
Takeshita, J. Radioanal. Nucl. Chem. 327(1), 597(2021).
15) Separation of rare earth elements by synergistic
solvent extraction with phosphonium‐basedionic liquids using a β‐diketone extractant and aneutral ligand, M. Matsumiya, D. Nomizu, Y.
Tsuchida & Y. Sasaki, Solvent Extr. Ion Exch. ‐,latest article (2021).

Book1) N. Sato, Y. Kirishima & M. Watanabe, The
Chemistry of Uranium (I) ‐ Basic and Application‐/ Tohoku Univ. Press (2020) (in Japanese).

Patents
E., Kaneko M., Omori T., Asano K., Sasaki Y.,
Suzuki S. & Ito K., “METHOD FOR SEPARATING
AND RECOVERING LONG‐LIVED NUCLIDECONTAINED IN RADIOACTIVE WASTE LIQUID”,
Japanese Patent 6784369 (2020.10.27)

1) Nakase M., Takeshita K. & Sasaki Y., “Method forseparation of lanthanides and actinides using
novel
reagent,
ethylenediamine‐
tetradiethylamide”, Japanese Patent Application
2020‐034169 (2020.02.28)
2) Takahashi Y., Yamashita T., Kanemura S., Murata

Research Group for Analytical Chemistry
PapersIonic Liquid‐DMF Mixture to Build a Redox Flow
Battery Using Uranium as an Electrode Active
Material, K. Ouchi, A. Komatsu, K. Takao, Y.
Kitatsuji & M. Watanabe, Chem. Lett. 50(6), 1169
(2021).
4) Application of an Augmentation Method to MCR‐ALS Analysis for XAFS and Raman Data Matrices
in the Structural Change of Isopolymolybdates,
M. Saeki, T. Yomogida, D. Matsumura, T. Saito, R.
Nakanishi, T. Tsuji & H. Ohba, Analytical Sci.
36(11), 1371 (2020).

1) External dose estimation for wild animals using
ESR spectroscopy, T. Oka & A. Takahashi,
Biannual J. Jpn Soc. Radiation Chem. 110, 13(2020) (in Japanese).
2) Improvement of Adsorption Performances of Sr
Adsorption Fiber and Investigation for Realizing
Simple Sr‐90 Analysis, T. Horita, S. Asai, M. Konda,
M. Matsueda, Y. Hanzawa & Y. Kitatsuji, 分析化
学 BUNSEKI KAGAKU 69(10.11), 619 (2020) (inJapanese).
3) Electrochemical Studies of Uranium (IV) in an

34

FY2020 NSEC Publications5) Development of a method for positronannihilation lifetime measurement in thinpolyethylene films using a Na‐22 source, M.
Yamawaki, N. Uesugi, T. Oka, N. Nagasawa, H.
Ando, B.E. O'Rourke & Y. Kobayashi, Jpn J.
Applied Phys. 59(11), 116504 (2020).
6) Examination of application of external exposure
dose assessment method for individual raccoons
living in difficult‐to‐return areas, Y. Mitsuyasu, T.
Oka, A. Takahashi, K. Koarai, Y. Kino, K. Okutsu, T.
Sekine, T. Yamashita, Y. Shimizu, M. Chiba, T.
Suzuki, K. Osaka, K. Sasaki, Y. Fujishima, V.S. Ting
Goh, K. Ariyoshi, A. Nakata, H. Yamashiro, H.
Shinoda & T. Miura, Proc. 21st WS on Environ.
Radioactivity, 144 (2020) (in Japanese).

7) A Fault dating method using an electron spinresonance, K. Tanaka, J. Muto, H. Nagahama &T. Oka, Biannual J. Jpn Soc. Radiation Chem. 110,
21 (2020) (in Japanese).
8) Morphological reproductive characteristics oftestes and fertilization capacity of cryopreserved
sperm after the Fukushima accident in raccoon(Procyon lotor), K. Komatsu, T. Iwasaki, K. Murata,
H. Yamashiro, V.S. Ting Goh, R. Nakayama, Y.
Fujishima, T. Ono, Y. Kino, Y. Simizu, A. Takahashi,
H. Shinoda, K. Ariyoshi, K. Kasai, M. Suzuki, M.G.
Palmerini, M. Belli, G. Macchiarelli, T. Oka, M.
Fukumoto, M.A. Yoshida, A. Nakata & T. Miura,
Reproduction in Domestic Animals 56(3), 484(2021).

Environment and Radiation Sciences Division
Research Group for Environmental Science
Papers1) Effectiveness of decontamination by litter
removal in Japanese forest ecosystems affectedby the Fukushima nuclear accident, J. Koarashi,
M. Atarashi‐Andoh, S. Nishimura & K. Muto, Sci.
Reports 10, 6614 (2020).
2) Development of a combined LES/RANS model topredict atmospheric dispersion over urban areas,
T. Yoshida, H. Nakayama, Trans. JSCES 2020,20200013 (2020).
3) Development of a Data Assimilation Method
Using Vibration Equation for Large‐Eddy
Simulations of Turbulent Boundary Layer Flows,
H. Nakayama & T. Takemi, JAMES 12(8),e2019MS001872 (2020).
4) Spatial characteristics of turbulent organizedstructures within the roughness sublayer overidealized urban surface with obstacle‐heightvariability, T. Yoshida & T. Takemi, Environ. Fluid
Mechanics 21, 129 (2021).
5) Observation of morphological abnormalities insilkworm pupae after feeding 137CsCl‐
supplemented diet to evaluate the effects of low
dose‐rate exposure, S. Tanaka, T. Kinouchi, T. Fujii,
T. Imanaka, T. Takahashi, S. Fukutani, D. Maki, A.
Nohtomi & S. Takahashi, Sci. Reports 10, 16055(2020).
6) Global budget of atmospheric I‐129 during
2007–2010 estimated by a chemical transportmodel: GEARN–FDM, M. Kadowaki, H. Terada &H. Nagai, Atmospheric Environ.: X 8, 100098(2020).
7) Impact of soil erosion potential uncertainties on
numerical simulations of the environmental fateof radiocesium in the Abukuma River basin, T.
Ikenoue, H. Shimadera & A. Kondo, J. Environ.
Radioactivity 225, 106452 (2020).
8) Development of a user‐friendly interface IRONS
for atmospheric dispersion database for nuclear
emergency preparedness based on the
Fukushima database, H. El‐Asaad, H. Nagai, H.
Sagara & C.Y. Han, Annals Nucl. Energy 141,107292 (2020).
9) Formation and mobility of soil organic carbon ina buried humic horizon of a volcanic ash soil, J.N.
Wijesinghe, J. Koarashi, M. Atarashi‐Andoh, Y.
Saito‐Kokubu, N. Yamaguchi, Takashi Sase, M.
Hosono, Y. Inoue, Y. Mori & S. Hiradate,
Geoderma 374, 114417 (2020).
10) Preliminary Investigation of Pretreatment
Methods for Liquid Scintillation Measurementsof Environmental Water Samples Using Ion
Exchange Resins, S. Nakasone, S. Yokoyama, T.
Takahashi, M. Ota, H. Kakiuchi, S. Sugihara, S.
Hirao, N. Momoshima, T. Tamari, N. Shima, M.
Atarashi‐Andoh, S. Fukutani, A. Ishimine, M.
Furukawa, M. Tanaka & N. Akata, Plasma Fusion
Res. 15, 2405027 (2020).
11) A model intercomparison of atmospheric Cs‐
137 concentrations from the Fukushima Daiichi
Nuclear Power Plant accident, phase III:35

FY2020 NSEC Publications
Simulation with an identical source term andmeteorological field at 1‐km resolution, Y. Sato,
T.T. Sekiyama, S. Fang, M. Kajino, A. Quérel, D.
Quélo, H. Kondo, H. Terada, M. Kadowaki, M.
Takigawa, Y. Morino, J. Uchida, D. Goto & H.
Yamazawa, Atmospheric Environ.: X 7, 100086(2020).
12) Seven‐year temporal variation of Caesium‐137
discharge inventory from the port of Fukushima
Daiichi Nuclear Power Plant: continuous monthly
estimation of Caesium‐137 discharge in the
period from April 2011 to June 2018, M. Machida,
S. Yamada, A. Iwata, S. Otosaka, T. Kobayashi, M.
Watababe, H. Funasaka & T. Morita, J. Nucl. Sci.
Tech. 57(8), 939 (2020).
13) Identifcation of coral spawn source areas
around Sekisei Lagoon for recovery andpoleward habitat migration by using a particle-

tracking model, N. Takeda, M. Kashima, S. Odani,
Y. Uchiyama, Y. Kamidaira & S. Mitarai, Sci.
Reports 11, 6963 (2021).
14) Simple Pretreatment Method for Tritium
Measurement in Environmental Water Samples
using a Liquid Scintillation Counter, S. Nakasone,
S. Yokoyama, T. Takahashi, M. Ota, H. Kakiuchi, S.
Sugihara, S. Hirano, N. Momoshima, T. Tamari, N.
Shima, M. Atarashi‐Andoh, S. Fukutani, K.
Nakamura, A. Ishimine, M. Furukawa, M. Tanaka& N. Akata, Plasma Fusion Res. 16, 2405035(2021).
15) Development of Short‐Term Emergency
Assessment system of Marine Environmental
Radioactivity, T. Kobayashi, H. Kawamura & Y.
Kamidaira, J. the Atomic Energy Soc. Jpn 62(11),635 (2020) (in Japanese).

JAEA Report
Kokubu, N. Fujita, N. Kinoshita, H. Nagai, N. Liang,
H. Matsuzaki & G. Katata, JAEA‐Tech. 2020‐012(2020).

1) Practical Guide on Soil Sampling, Treatment, andCarbon Isotope Analysis for Carbon Cycle Studies,
J. Koarashi, M. Atarashi‐Andoh, H. Nagano, U.
Sugiharto, C. Saengkorakot, T. Suzuki, Y. Saito‐

Research Group for Radiation Transport Analysis
Papers1) Individual dosimetry system for targeted alphatherapy based on PHITS coupled withmicrodosimetric kinetic model, T. Sato, T. Furuta,
Y. Liu, S. Naka, S. Nagamori, Y. Kanai & T. Watabe,
EJNMMI Physics 8, 4 (2021).
2) Dosimetric Impact of a New Computational Voxel
Phantom Series for the Japanese Atomic Bomb
Survivors: Methodological Improvements andOrgan Dose Response Functions, T. Sato, S.
Funamoto, C. Paulbeck, K. Griffin, C.s. Lee; H.
Cullings, S.D. Egbert; A. Endo, N. Hertel & W.E.
Bolch, Rad. Res. 194(4), 390 (2020).
3) Estimation of reliable displacements‐per‐atombased on athermal‐recombination‐correctedmodel in radiation environments at nuclear
fission, fusion, and accelerator facilities, Y.
Iwamoto, S.‐i. Meigo & S. Hashimoto, J. Nucl.
Mater. 538, 152261 (2020).
4) Calculation of athermal recombination corrected
dpa cross sections for proton, deuteron andheavy‐ion irradiations using the PHITS code, Y.
Iwamoto & S.‐i. Meigo, EPJ Web of Conf. 239,
20011 (2020).
5) Measurements of Displacement Cross Section ofTungsten under 389‐MeV Proton Irradiation andThermal Damage Recovery, Y. Iwamoto, M.
Yoshida, H. Matsuda, S.I. Meigo, D. Satoh, H.
Yashima, A. Yabuuchi & T. Shima, Mater. Sci.
Forum 1024, 95 (2021).
6) Total cross section model with uncertainty
evaluated by KALMAN, S. Hashimoto & T. Sato,
EPJ Web of Conf. 239, 03015 (2020).
7) ORGAN ABSORBED DOSE ESTIMATIONREFLECTING SPECIFIC ORGAN MASSES WITHSIMPLE SCALING OF REFERENCE DOSES USINGTHE ORGAN MASSES, K. Manabe & S. Koyama,
Radiation Protection Dosimetry 189(4), 489(2020).
8) A Model for Estimating Dose‐Rate Effects on Cell‐
Killing of Human Melanoma after Boron Neutron
Capture Therapy, Y. Matsuya, H. Fukunaga, M.
Omura & H. Date, Cells 9(5), 1117 (2020).
9) A theoretical cell‐killing model to evaluate
oxygen enhancement ratios at DNA damage andcell survival endpoints in radiation therapy, Y.
Matsuya, T Sato, R. Nakamura, S. Naijo & H. Date,
Phys. Med. Biol. 65(9), 095006 (2020).
10) Modernization of the DCHAIN‐PHITS activation

36

FY2020 NSEC Publications
Rosenfeld, A. Bianchi, P. Olko, L. Struelens & F.
Vanhavere, Phys. Med. Biol. 65(23), 235010(2020).
17) Measurement of displacement cross‐sectionsof copper and iron for proton with kinetic
energies in the range 0.4 – 3 GeV, H. Matsuda, S.‐
I. Meigo, Y. Iwamoto, M. Yoshida, S. Hasegawa, F.
Maekawa, H. Iwamoto, T. Nakamoto, T. Ishida &S. Makimura, J. Nucl. Sci. Tech. 57(10), 1141
(2020).
18) Study of the Li(d, xn) reaction for thedevelopment of accelerator‐based neutron
sources, Y. Watanabe, H. Sadamatsu, S. Araki, K.
Nakano, S. Kawase, T. Kin, Y. Iwamoto, D. Satoh,
M. Hagiwara, H. Yashima, T. Shima & S.
Nakayama, EPJ Web of Conf. 239, 20012 (2020).
19) Re‐evaluation of Radiation‐Energy Transfer toan Extraction Solvent in a Minor‐Actinide‐
Separation Process Based on Consideration ofRadiation Permeability, T. Toigawa, Y. Tsubata, T.
Kai, T. Furuta, Y. Kumagai & T. Matsumura,
Solvent Extr. Ion Exch. 39(1), 74 (2021).
20) Relation between biomolecular dissociationand energy of secondary electrons generated inliquid water by fast heavy ions, H. Tsuchida, T. Kai,
K. Kitajima, Y. Matsuya, T. Majima & M. Saito, Eur.
Phys. J. D 74(10), 212 (2020).
21) Verification of dose estimation of Auger
electrons emitted from Cu‐64 using a
combination of FNTD measurements and Monte
Carlo simulations, T. Kusumoto, Y. Matsuya, K.
Baba, R. Ogawara, M.S. Akselrod, J. Harrison, V.
Fomenko, T. Kai, M. Ishikawa, S. Hasegawa & S.
Kodaira, Rad. Meas. 132, 106256 (2020).
22) Implications of radiation microdosimetry foraccelerator‐based boron neutron capture
therapy: a radiobiological perspective, H.
Fukunaga, Y. Matsuya, K. Tokuuye & M. Omura,Brit. J. Radiol. 93(1111), 20200311 (2020).
23) Japanese population dose from naturalradiation, Y. Omori, M. Hosoda, F. Takahashi, T.
Sanada, S. Hirao, K. Ono & M. Furukawa, J.
Radiol. Prot. 40(3), R99 (2020).

code with new features and updated datalibraries, H.N. Ratliff, N. Matsuda, S.‐i. Abe, T.
Miura, T. Furuta, Y. Iwamoto & T. Sato, Nucl. Inst.
& Methods in Phys. Res., B 484, 29 (2020).
11) Simulation code for estimating external
gamma‐ray doses from a radioactive plume andcontaminated ground using a local‐scaleatmospheric dispersion model, D. Satoh, H.
Nakayama, T. Furuta, T. Yoshihiro & K. Sakamoto,
PLoS ONE 16(1), e0245932 (2021).
12) Evaluation of RBE‐weighted doses for various
radiotherapy beams based on a microdosimetricfunction implemented in PHITS, K. Takada, T.
Sato, H. Kumada, H. Sakurai & T. Sakae, J. Phys.:Conf. Ser. 1662, 012004 (2020).
13) 208,207,206,natPb(p,x)207Bi and 209Bi (p,x)207Bi
excitation functions in the energy range of 0.04 ‐2.6 GeV, Yu.E. Titarenko, V.F. Batyaev, K.V. Pavlov,
A.Yu. Titarenko, S.V. Malinovskiy, V.I. Rogov, V.M.
Zhivun, T.V. Kulevoy, M.V. Chauzova, S.V. Lushin,
A.S. Busygin, A.V. Ignatyuk, P.N. Alekseev, V.Yu.
Blandinskiy, A.A. Kovalishin, S.I. Tyutyunnikov,
A.A. Baldin, A.N. Sosnin, M.I. Baznat, A.Yu.
Stankovskiy, A.I. Dubrouski, H.I. Kiyavitskaya, T.
Xue, Y. Tian, M. Zeng, Z. Zeng & T. Sato, Nucl. Inst.
& Methods in Phys. Res., A 984, 164635 (2020).
14) Real‐time in vivo dosimetry system based on an
opticalfiber‐coupledmicrosized
photostimulable phosphor for stereotactic bodyradiation therapy, R. Yada, K. Maenaka, S.
Miyamoto, G. Okada, A. Sasakura, M. Ashida, M.
Adachi, T. Sato, T.y. Wang, H. Akasaka, N.
Mukumoto, Y. Shimizu & R. Sasaki, Med. Phys.
47(10), 5235 (2020).
15) Investigation of using a long‐life electronic
personal dosimeter for monitoring aviation
doses of frequent flyers, H. Yasuda, K. Yajima & T.
Sato, Rad. Meas. 134, 106309 (2020).
16) Development of a new microdosimetricbiological weighting function for the RBE10
assessment in case of the V79 cell line exposed
to ions from H‐1 to U‐238, A. Parisi, T. Sato, Y.
Matsuya, Y. Kase, G. Magrin, C. Verona, L. Tran, A.

Partitioning and Transmutation Technology Division
Research Group for Partitioning
Papers1) Radiation‐induced effects on the extraction
properties of hexa‐n‐octylnitrilo‐triacetamide(HONTA) complexes of americium and europium,
T. Toigawa, D.R. Peterman, D.S. Meeker, T.S.

37

FY2020 NSEC Publications
Grimes, P.R. Zalupski, S.P. Mezyk, A.R. Cook, S.
Yamashita, Y. Kumagai, T. Matsumura & G.P.
Horne, Phys. Chem. Chem. Phys. 23(2), 1343
(2021).
2) Re‐evaluation of Radiation‐Energy Transfer to an
Extraction Solvent in a Minor‐Actinide‐
Separation Process Based on Consideration ofRadiation Permeability, T. Toigawa, Y. Tsubata, T.
Kai, T. Furuta, Y. Kumagai & T. Matsumura,
Solvent Extr. Ion Exch. 39(1), 74 (2021).
3) 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).
4) Simultaneous separation of Am and Cm from Nd
and Sm by multi‐step extraction using the
TODGA‐DTPA‐BA‐HNO3 system, Y. Sasaki, K.
Morita, M. Matsumiya & M. Nakase, Radiochim.
Acta 108(9), 689 (2020).
5) Fundamental Study on Multistage Extraction
Using TDdDGA for Separation of Lanthanides
Present in Nd Magnets, Y. Sasaki, K. Morita, M.
Matsumiya, R. Ono & H. Shiroishi, JOM 73(4),1037 (2021).

JAEA Reports
1) Production of the Minor Actinide Sources using
the Electrodeposition Method, S. Nakamura, T.
Kimura, Y. Ban, Y. Tsubata & T. Matsumura, JAEA‐
Technology 2020‐009 (2020) (in Japanese).
2) Critical Mass Evaluation of Minor Actinides in

Aqueous Solution ‐Data for Criticality Safety
Assessment of Separation Process‐, Y. Morita, M.
Fukushima, T. Kashima & Y. Tsubata, JAEA‐
Data/Code 2020‐013 (2020) (in Japanese).

Research Group for Nuclear Transmutation System
Papers1) Neutronics design for molten salt accelerator‐
driven system as TRU burner, T. Sugawara, Annals
Nucl. Energy 149, 107818 (2020).
2) Generation of nuclear data using Gaussian
process regression, H. Iwamoto, J. Nucl. Sci. Tech.
57(8), 932 (2021).
3) Academic award of nuclear data subcommittee
in 2020; Unified description of the fission
probability for highly excited nuclei, H. Iwamoto,核 デ ー タ ニ ュ ー ス 128, 13 (2021) (inJapanese).
4) Non‐proliferation features in partitioning andtransmutation cycle using accelerator‐driven
system; Evaluation of Material Attractiveness offuel assembly in early period of burnup cycle, A.
Oizumi, T. Sugawara & H. Sagara, Proc. INMMJ‐
41, P4160 (2020) (in Japanese).
5) Measurement of thick target neutron yield at
180° for a mercury target induced by 3‐GeV

protons, H. Matsuda, H. Iwamoto, S.‐i. Meigo, H.
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6) Measurement of displacement cross‐sections ofcopper and iron for proton with kinetic energies
in the range 0.4 – 3 GeV, H. Matsuda, S.‐I. Meigo,
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Maekawa, H. Iwamoto, T. Nakamoto, T. Ishida &S. Makimura, J. Nucl. Sci. Tech. 57(10), 1141
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7) PR2‐3 Measurement of Am‐243 Fission Rates in
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core of KUCA for ADS, M. Fukushima, A. Oizumi,
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JAEA Reports
1) Selection of nuclides for mass‐balance analysis
of fission products, T. Okamura, A. Oizumi, K.
2) Manufacturing Miniature Beam Window for
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N. Watanabe, T. Sugawara, N. Okubo & K.
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Data/Code 2020‐023 (2021) (in Japanese).
Japanese).
3) Material Balance Analysis for Wide Range of
Nuclear Power Generation Scenarios, K.
Nishihara, JAEA‐Data/Code 2020‐005 (2020) (in38

FY2020 NSEC Publications
Japanese).
4) Estimation of Oxygen Consumption Amount in
LBE‐cooled Accelerator‐Driven System, T.

Sugawara & A. Komatsu, JAEA‐Research 2020‐016 (2021) (in Japanese).

39Editorial Board‐ Chief Editor:
TAKAHASHI Fumiaki‐ Editors:
NAKAYAMA Shinsuke, KOMATSU Atsushi,
KUSAKA Ryoji, OTA Masakazu, OIZUMI Akito,
KATO Chiaki, NAKAHARA Yukio

Nuclear Science and Engineering Center (NSEC)Japan Atomic Energy Agency (JAEA)
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319‐1195. JapanE‐mail : nsed‐web@jaea.go.jp
U R L : https://nsec.jaea.go.jp/