FY2022 (2022.4‐2023.3) NSEC
Annual Report

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

November 2023

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, 2023

FY2022 NSEC Annual Report

Table of Contents

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

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

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

Nuclear Science and Reactor Engineering Division ······················································· 11
Nuclear Data Center
Research Group for Nuclear Sensing
Research Group for Reactor Physics and Thermal-Hydraulics Technology
Research Group for Nuclear Transmutation System
Fuels and Materials Engineering Division ········································································ 15
Research Group for Corrosion Resistant Materials
Research Group for Radiation Materials Engineering
Research Group for High Temperature Science on Fuel Materials
Research Group for Nuclear Fuel Cycle Science
Chemistry, Environment, and Radiation Division ·························································· 19
Research Group for Environmental Science
Research Group for Radiation Transport Analysis
Research Group for Nuclear Chemistry

Publication List........................................................................... 22

FY2022 NSEC Annual Report

Preface

TSUJIMOTO Kazufumi
Director General, Nuclear Science and Engineering Center

The Nuclear Science and Engineering Center (NSEC) of the Japan Atomic Energy Agency (JAEA)
aims to conduct research and development to advance the science and technology that supports
the use of nuclear energy and radiation. This annual report provides research highlights and an
overview of the research groups’ activities in the NSEC for Fiscal Year 2022. 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.
It is our responsibility to provide the results of our research and development activities tosociety in ways that are transparent and have high quality and impact. We have been
disseminating our innovative technologies for resolving challenges in various fields, such asindustry, environment, and medicine. The NSEC is a key research center for supporting thenuclear energy infrastructure through our nuclear science and engineering research. We strive
to become a leading center for research collaboration, using our fundamental research anddevelopment capabilities to contribute to advances in science and technology.
We seek your understanding, support, and encouragement in our research and development
activities.

September 2023

1

FY2022 NSEC R&D Highlight

FY2022 NSEC R&D Highlights

The following 6 highlights are selected among various outcomes of the R&D
activities accomplished by the NSEC's 3 divisions in FY2022.

✓ Nuclear Science and Reactor Engineering Division:
 "Development of the state-of-the-art nuclear data library JENDL-5"
 "Spallation neutron measurement"✓ Fuels and Materials Engineering Division:
 "Electronic structure-based modeling of dislocation motion and its
application to nanoscale mechanics"
 "Improvement of model for cesium chemisorption onto stainlesssteel in severe accident analysis code SAMPSON"✓ Chemistry, Environment, and Radiation Division:
 "Predicting the radiocesium behavior on land for 30 years after the
Fukushima Daiichi nuclear power station accident"
 "Developing a system for whole whole-body dose assessment incarbon ion radiotherapy"

2

FY2022 NSEC R&D Highlight

Development of the State-of-the-art Nuclear Data Library JENDL-5
IWAMOTO Osamu
Nuclear Data Center
Nuclear data are fundamental quantities about
nuclear reactions and structures. They are requiredin computational simulations related to radiation.
These simulations are crucial for developing
technologies in various fields, including nuclear
reactors, particle accelerators, and environmental
radiation. The nuclear data library is a database of
nuclear data stored in a fixed format and applicableto radiation simulation codes. The first version of
the Japanese evaluated nuclear data library, JENDL1, was released in 1977 for fast reactor
development. Updates of the data in JENDL were
continued, and the previous version, JENDL-4.0,
was released in 2010, focusing on fission products
and minor actinides to facilitate high burn-up andmixed oxide (MOX) fuels for light water reactors.
These JENDL series (so-called general-purpose
files) primarily target neutron transport
calculations of the characteristics of nuclear
reactors and neutron shielding in materials. In
addition to those general-purpose files, 21 specialpurpose files were developed to meet the needs
not covered by the general-purpose file. They
included data on neutron activations, high-energy
reactions, and charged particle/photon-induced
reactions. However, too many independent specialpurpose files would cause data consistency
problems and confuse users with library selection.
A new library, JENDL-5, has been developed toovercome those concerns by integrating thegeneral- and special-purpose data files andupdating the data to increase reliability. JENDL-5
should satisfy the expanding needs of nuclear datain energy applications, such as innovative nuclear
reactordevelopments,
radiative
waste
management, nuclear decommissioning, andnonenergy applications with charged particle
accelerators, for which the nuclear data have been
provided in the special-purpose files.
Considering currently available experimental
data and innovative theoretical knowledge, thedata have been revised. The experimental dataobtained by the Accurate Neutron-Nucleus
Reaction Measurement Instrument (ANNRI), with
the intensive pulse neutron source at the Japan
Proton Accelerator Research Complex (J-PARC),
were widely used to update the data. On thetheoretical side, the nuclear reaction model codes,
such as CCONE, DURACS, and AMUR, weredeveloped/upgraded and extensively applied tolarge parts of evaluations. JENDL-5 comprises 11

sublibraries (Table 1), providing sufficient data forvarious applications. The neutron sublibrary is themost crucial, especially for nuclear reactors. Fig. 1
shows that the number of nuclides increases much
more than JENDL-4.0. JENDL-5 is available on thewebsite https://wwwndc.jaea.go.jp.
Table 1Sublibraries included in JENDL-5

Name
neutronDescription
neutron-induced reaction up
to 20 or 200 MeV

TSL

thermal scattering law

37 mat.

FPY

fission product yield

36 nucl.

decay data

decay data of nuclides (Z = 1–118) and neutron

4,071
nucl.

protonproton-induced reaction up
to 200 MeV

239
nucl.

deuterondeuteron-induced
up to 200 MeV

reaction

9 nucl.

alphaparticlealpha-particle reaction up to
15 MeV

18 nucl.

photonuclear

photonuclear reaction up to
140 or 200 MeV

2,684
nucl.

photoatomic

photo-atomic reaction datafrom H to Fm

100
elem.

electroatomic

electro-atomic reaction datafrom H to Fm

100
elem.

atomicrelaxation

atomic relaxation data from
H to Fm

100
elem.

Fig. 1

No.
795
nucl.

The number of nuclei for neutron reaction
data in the JENDL releases

Reference
1) O. Iwamoto, et al., J. Nucl. Sci. Technol. 60(1), 1 (2023).

3

FY2022 NSEC R&D Highlight

Spallation Neutron Measurement
IWAMOTO Hiroki1,2, MEIGO Shin-ichiro2, SATOH Daiki3, IWAMOTO Yosuke3
1 Research Group for Nuclear Transmutation System
2 Nuclear Transmutation Division, J-PARC Center
3 Research Group for Radiation Transport Analysis
Spent fuel from nuclear power plants remains
highly radioactive for tens of thousands of years.
Accelerator-driven systems (ADS) are being
investigated as a potential solution to mitigate
long-term toxicity. In the ADS design using GeVrange proton beams, accurately predicting theintensity and energy distribution of neutrons
emitted from the target in various directions is
critical.
Numerous nuclear reaction models have beendeveloped to simulate the neutron behavior inspallation reactions. While these models caneffectively predict neutron spectra at incident
proton energies above several hundred MeV, theiraccuracy declines at lower energies. However, alack of experimental data in the 100 MeV region
has hindered the validation of these nuclear
reaction models. Therefore, we conducted
experiments to obtain proton-induced reaction
data near 100 MeV.
In this experiment, a 107 MeV proton beam
generated by the fixed-field alternating gradient(FFAG) accelerator irradiated a target within avacuum chamber. The energy distribution ofneutrons emitted from the target was measured
across several emission angles relative to the beam
direction (Fig. 1). The target materials chosen forthis experiment were iron, lead, and bismuth,which are crucial in ADS design. A comparison
between the measured neutron energy
distributions and the nuclear reaction model
calculations revealed that the nuclear reaction
models could not adequately reproduce theexperimental values above 10 MeV (Fig. 2). The
data and findings from this study provides valuable
insights for enhancing the prediction accuracy of
nuclear reaction models, benefiting ADS researchand development and the design of accelerator
facilities using proton beams.
These results were obtained under the contract
research project “Experimental Study of Nuclear
Data for ADS using the FFAG Proton Accelerator,”
funded by Japan’s Ministry of Education, Culture,
Sports, Science, and Technology (MEXT), under thetitle “Research and Development of Nuclear Energy
System (JPMXD0219214562).”

Fig. 1

Experimental setup

Fig. 2Comparison of the energy distribution ofneutrons emitted from a lead target in
specific angular directions between theexperimental and analytical values fromthree nuclear reaction models

Reference
1) H. Iwamoto, et al., J. Nucl. Sci. Technol. 60(4), 435 (2023).

4

FY2022 NSEC R&D HighlightElectronic Structure-based Modeling of Dislocation Motion and Its Application
to Nanoscale Mechanics
TSURU Tomohito
Research Group for Radiation Materials Engineering
The dynamic behavior of defect structures
determines the mechanical properties of structural
materials. Especially in the deformation of metallic
materials, dislocation motions are critical for
determining mechanical functions such as thestrength and ductility of metallic materials. Alloying
is one of the most effective approaches to improvemechanical functions, but it is challenging to know
the effects of the elements to be added. Most
alloys developed in the past were discovered bytrial and error based on empirical knowledge. In
the future development of highly controlledmaterials, comprehensive material design that
does not rely on experience has been desired. This
study aimed to capture the origins of themechanical functions of alloy systems from theproperties of dislocation cores based on theelectronic structure using the large computer SGI
8600 at the JAEA. We studied the defect structure
analysis to achieve the mechanical property
prediction considering the electronic states
depending on the elements.
Figure 1 shows the energy barriers to the
motion of screw dislocations in body-centeredcubic (BCC) tungsten and the structure of thedislocation cores at various positions. Adding
alloying elements changes the interaction with thedislocations and energy barriers. Here, we consider
how the change caused by alloying elements
influences the macroscopic mechanical properties.
We consider the screw dislocation motion in BCC
alloys to be a thermally activated process that can
associate with the macroscopic mechanicalproperties via dislocation motion. The interaction
between the dislocations and alloying elements isevaluated using first-principles calculation, and theresults are shown in Fig. 2(a). We systematicallyanalyzed various transition metals from three- to
five-dimensional.
Figure 2(b) shows the relationship between thestrength and temperature predicted from theanalytical modeling based on the thermally
activated process. The strength of the W–Re alloy
varies complicatedly with concentration andtemperature, corresponding to solid solution
softening observed in the experiments. Thisphenomenon was only found by considering theelectronic state of the alloying elements. Thus,
evaluating the mechanical properties using
computer simulation can reduce the time and costof alloy design. Moreover, it is expected tocontribute to future elemental strategy alloy design
development for creating new materials1).
This study was supported by JST PRESTO (Grant No.
JPMJPR1998).

Fig. 1

Energy of dislocation motion and core
structure; the motion of screw dislocations
determines the mechanical properties ofbody-centered cubic (BCC) metals.

Fig. 2(a) Interaction between the dislocation andalloy elements, and (b) the relationshipbetween strength and temperature. The
negative sign indicates an attractive
interaction. These interactions significantly
change the macroscopic mechanicalproperties.

Reference
1) T. Tsuru, J. the Soc. Mater. Sci., Jpn. 71(8), 660 (2022) (inJapanese).

5

FY2022 NSEC R&D Highlight

Improvement of Model for Cesium Chemisorption onto Stainless Steel in
Severe Accident Analysis Code SAMPSONMIWA Shuhei1, KARASAWA Hidetoshi1, NAKAJIMA Kunihisa1, KINO Chiaki2, SUZUKI Eriko1,
IMOTO Jumpei1
1 Research Group for High Temperature Science on Fuel Materials
2 The Institute of Applied Energy
Information on the cesium (Cs) distribution
within nuclear reactor vessels and the watersolubility property of Cs deposits is essential tostrategically plan for fuel debris retrieval and waste
management at the TEPCO’s Fukushima Daiichi
Nuclear Power Station (1F). Plant equipment, suchas standpipes, steam separators, and a steam dryer
just above the core, is subject to Cs chemisorption
onto stainless steel (SS). Cs chemisorption onto SS
can form the water-insoluble compounds of Cs, andthe chemisorbed Cs compounds could remain in
the reactor as a fixed radiation source. Thus, for amore accurate estimation of Cs distribution, the
JAEA improved the Cs chemisorption model basedon the chemisorption tests onto SS over wider
concentration ranges for Cs and Si than thosereported in steam and hydrogen mixed
atmospheres. It was found that the uncertainty was
reduced by nearly one order of magnitude1).
The improved Cs chemisorption model wasincorporated into the severe accident (SA) analysis
code SAMPSON to estimate the Cs distribution andwater solubility property in the 1F. The analysis of
the experiment with the temperature gradienttube simulating SA conditions, such as temperature
decrease and aerosol formation, was performed toconfirm the availability of SAMPSON with the
improved model to the analysis of Cs
chemisorption onto SS in SA conditions. Figure 1
compares the measured and calculated deposited
Cs masses onto the flow path of the Cs vapor.
Although the existing model overestimated thedeposited Cs masses, the calculation results for the
improved one are consistent with the experimental
one within the uncertainty range of the model. This
result shows the applicability of SAMPSON with the
improved model2).
On the other hand, there is highly possibility
that the Cs redistribution could have been causedby the transportation through the aqueous phase,such as condensed water in or after the SA of the
1F. Therefore, the water solubility of Cschemisorbed compounds should be a prerequisite
for evaluating the Cs redistribution. Therefore, thechemical form of the Cs-chemisorbed compound
was investigated in the chemisorption tests, as
described above. Figure 2 shows the chemical
forms of Cs compounds chemisorbed onto SS ineach temperature condition. The water-insoluble
chemisorbed compounds have been identified as
Cs–Fe–O compounds, most likely CsFeO2, at 873–
973 K, Cs–Fe–Si–O compounds, most likely
CsFeSiO4, at 973 - 1273 K, and Cs–Si–O compounds,
most likely Cs2Si4O9, at 1073–1273 K. The watersolubility of chemisorbed compounds wasinvestigated and showed higher water solubility for
CeFeO2, and lower water solubility for Cs2Si4O9 and
CsFeSiO4.
Thus, the distribution and water solubility ofchemisorbed Cs compounds can be estimatedaccording to the SA analysis conditions oftemperature in the reactor and the Cs and Si
concentrations affecting the amount ofchemisorbed Cs.

Fig. 1

The comparison of measured and calculated
deposited Cs masses for water-insolublecompounds

Fig. 2The chemical forms of Cs compounds
chemisorbed onto SS in each temperature
condition

References
1) Development Group for LWR Advanced Technology, JAEAData/Code 2019-017 (2020).
2) S. Miwa, et al., JAEA-Data/Code 2021-022 (2023).

6

FY2022 NSEC R&D Highlight

Predicting the Radiocesium Behavior on Land for 30 Years After the
Fukushima Daiichi Nuclear Power Station Accident
IKENOUE Tsubasa
Research Group for Environmental ScienceFig. 1(a) 137Cs transport into the ocean through the river 30 years after the accident and the relative
contribution of each use to the transport and (b) the ratio of 137Cs remained after 30 years, anddecrease ratio of radioactive decay and transport by rainfall-runoff.

Most radiocesium (137Cs) deposited on land dueto the accident at Fukushima Daiichi nuclear power
station (1F) remains on land. The 137Cs depositedon land is transported into the ocean through rivers
by rainfall-runoff. Therefore, predicting the longterm behavior of 137Cs remaining on land and beingtransported into the ocean is important forunderstanding the long-term impacts on humanhealth and the environment. Since the temporal
trends of 137Cs transported by rainfall-runoff varysignificantly depending on land use, it is essential
to consider the characteristics of the 137Cs behavior
in each land use. However, no studies haveconducted a long-term prediction of 137Cs
considering these characteristics in detail.
Therefore, we developed a 137Cs prediction modelthat considers the behavior of 137Cs in soil andvegetation by land use to reflect thesecharacteristics1).
We predicted 137Cs behavior in the Abukuma
River basin, the largest basin near the 1F. According
to the prediction results, the 137Cs transported into
the ocean through the river 30 years after theaccident was estimated to be 25.3 TBq and thecontribution of total transport from urban lands
and agricultural lands corresponded to 85.3% of
the total transport (Fig. 1(a)). These results

indicated that areas with human activities (urban
lands and agricultural lands) contributed
significantly to 137Cs transport into the ocean. In the
30 years after the accident, 137Cs that was
deposited in forest areas, undisturbed agriculturallands, urban lands, and agricultural lands wasremoved by rainfall-runoff by 1.4%, 0.9%, 20.9%,
and 20.8%, respectively, and remained at 49.7%,
50.0%, 39.0%, and 36.7%, respectively (Fig. 1(b)).
Therefore, 137Cs in areas with human activities
decreased significantly faster than those without
human activities (forest areas and undisturbed
agricultural lands). These results suggested thathuman activities enhance the reduction of 137Cs
remaining on land.
The predicted results of the long-term behaviorof 137Cs on land help evaluate future radiation
exposure doses and the impacts of 137Cs onorganisms. In future studies, the long-term
prediction of 137Cs in basins near the 1F will be
conducted, considering the impact of humanactivities.
This study was conducted as part of collaborative
research with Osaka University.
Reference
1) T. Ikenoue, et al., Sci. Total Environ. 876, 162846 (2023).

7

FY2022 NSEC R&D Highlight

Developing a System for Whole-body Dose Assessment in Carbon Ion
Radiotherapy
FURUTA Takuya
Research Group for Radiation Transport Analysis
In radiation therapy, unwilling radiation doses
to normal tissues other than the target tumor
volume cannot wholly be avoided, and a risk of theside effects exists, such as cancer (secondary
cancer). It is necessary to compare the radiationdose exposure in each organ and the resulting side
effects for numerous patients to find the cause ofsuch stochastic radiation effects. It has beenreported that carbon ion radiotherapy (CIRT) has alower incidence of secondary cancers thanconventional X-ray therapy1). However, for CIRT,
there has been no system to compute dosages to
distant organs.
We developed the radiotherapy package basedon particle and heavy ion transport code system(RT-PHITS) for CIRT in collaboration with National
Institutes for Quantum Science and Technology(QST). This system enables the evaluation ofdetailed dose distribution throughout the patient’s
body, including contributions from secondary
particles not fully considered in conventional dose
evaluation (Fig. 1)2). The system extracts beam
device arrangement information and patient CT
images from the treatment planning data of CIRT
and reproduces the exact beam geometry of CIRT
during treatment.
In the future, RT-PHITS for CIRT is expected to
be used to reevaluate CIRT data compiled in QST,
which has the most significant number of CIRT
cases globally. Combining the evaluation resultswith patients’ epidemiological data, will elucidate
the correlation between side effects and radiationdose exposure after CIRT. Furthermore, throughreevaluation of data, we aim to find the reasons forthe low incidence of secondary cancers in CIRT andthe mechanisms underlying the side effects inradiotherapy. Clarifying the mechanism will lead toa new radiotherapy plan that considers the futurerisk of side effects (Fig. 2).

Fig. 1Comparison of the dose distribution
between the conventional calculation (top)and RT-PHITS for CIRT (bottom) in ananthropomorphic phantom

Fig. 2

Role of RT-PHITS for CIRT

References
1) O. Mohamad, et al., Lancet Oncol. 20, 674 (2019).
2) T. Furuta, et al., Phys. Med. Biol. 67, 145002 (2022).

8

FY2022 NSEC Group Activity

FY2022 NSEC Group Activities

The NSEC of JAEA consists of 11 Groups.

9

FY2022 NSEC Group Activity

Organization of NSEC

（as of November 2023）

URL: https://nsec.jaea.go.jp/organization/en_index.html
10

FY2022 NSEC Group Activity

Nuclear Data Center
The Nuclear Data Center provides reliable nuclear
data for various applications, such as nuclear
reactors, accelerators, and for medical use ofradiation. Therefore, we research nuclear datameasurements, theories, and data evaluation
related to nuclear reaction and structure,collaborating with nuclear data researchers andorganizations in Japan and globally. The evaluatednuclear data have been compiled into the Japanese
Evaluated Nuclear Data Library (JENDL). The data
files
are
availablefromourwebsite(http://wwwndc.jaea.go.jp).

determining the neutron energies in the highenergy region with the time-of-flight method.
Hence, a neutron filtering system has been installed
in ANNRI to overcome this disadvantage. The
system uses the valleys of the neutron resonances
in materials to create quasi-mono-energy neutron
beams. The neutron cross-sections for 241Am weresuccessfully measured at neutron energies of 23.5,
51.5, and 127.7 keV with Fe and Si filter materials.
The cross-sections were determined withuncertainties from 10% to 12%2) and were used for
JENDL-5.

Novel Approach to Recoil Nucleus
Spectrum in Nuclear Model
Calculation

Neutron Capture Cross-section
Measurements with Activation
MethodThe residual nuclei are recoiled in the nuclear
reactions that emit particles such as neutrons andprotons. The kinetic energies of the recoil nuclei
would be released into the surrounding materials.
The energy spectra of the recoil nuclei are needed
to estimate the radiation effects, such as material
damage and soft errors in semiconductors. The
particle emissions spectra in the nuclear datalibraries rely on the nuclear model calculations; for
JENDL, a nuclear reaction model code, CCONE, wasdeveloped and applied to the many libraries.
However, CCONE could not calculate the recoil
nucleus spectrum because of the difficulties in thecalculation required to trace all particle emissions.
A novel method with a Monte Carlo prescriptionthat accurately calculated the recoil spectra wasdeveloped and applied to the proton-induced
reaction on 12C at 70 MeV. The calculated results
were compared with the available experimental
data of double differential cross-sections of
produced nuclei of A = 6–12 and Li to C, showing
reasonable agreements.3) This method was applied
to the JENDL-5 evaluation.

The activation method is reliable for cross-section
measurements, especially for thermal neutrons.
However, the measured values sometimes show
contradictions. One of the reasons is uncertainties
in estimating the epithermal neutron contributions.
To obtain reliable cross-sections of 237Np, we used
the graphite thermal column at the Kyoto
University Research Reactor, which provides a wellthermalized neutron field. Five neutron flux
monitors of 45Sc, 59Co, 98Mo, 181Ta, and 197Au, withdifferent sensitivities to the epithermal neutrons,
were irradiated with 237Np samples to estimate theneutron flux properties. The irradiated results ofthe monitors showed no apparent monitor
dependencies. In other words, it was confirmedthat the neutron flux was well-thermalized, and theepithermal contribution was negligible. The
thermal neutron cross-section of 237Np was
obtained with a 3% uncertainty1) and wasconsidered in evaluating the up-to-date nuclear
data library JENDL-5.

Cross-section Measurement for
Fast Neutrons with a Filtering
System with ANNRI

References
1) S. Nakamura, et al., J. Nucl. Sci. Technol. 59(11), 1388
(2022).
2) G. Rovira, et al., J. Nucl. Sci. Technol. 60(5), 489 (2023).
3) O. Iwamoto, J. Nucl. Sci. Technol. 59(10), 1232 (2022).

The
Accurate
Neutron–Nucleus
Reaction
Measurement Instrument (ANNRI), installed in thematerials and life science facility (MLF) of the Japan
Proton Accelerator Research Complex (J-PARC), is
one of the most attractive instruments with apulsed neutron source for nuclear datameasurements globally. A remarkable point of
ANNRI is its high neutron flux, allowing it tomeasure neutron reaction cross-sections with avery small sample in a short measuring time.
However, the MLF provides a pulsed beam with adouble-peak structure that causes a problem inContact (Group Leader):IWAMOTO Osamu
iwamoto.osamu@jaea.go.jp

11

FY2022 NSEC Group Activity

Research Group for Nuclear Sensing
Effect of Sample Density in Prompt
Gamma-ray Analysis (PGA)

Nondestructive analysis (NDA) is fundamental for
nuclear safeguards, security, waste management,
and decommissioning. Despite being a mature
method, room exists for further improvements in
NDA to meet the distinctive demands ofresearchers and engineers. For instance, new andadvanced NDA techniques are required to address
nuclear material accountancy of special nuclear
materials and minor actinides in highly radioactive
nuclear materials because high radiation levels
make
their
measurements
challenging.
Developments of low-cost, accurate, and practical
NDA systems are also needed for effective
implementation. Therefore, we have developed an
NDA system and related methodologies. The
following are some of our group activities in FY2022.

PGA is a powerful analytical method with highmeasurement accuracy, enabling us to perform
NDA of bulk samples, and can be applied to lightelements that are challenging to measure by mostother analytical methods. Due to these advantages,
PGA can be applied in many fields. Although PGA
can measure light elements, such as hydrogen, themeasurement accuracy of hydrogenous materials
degrades.
We evaluated the effects of the hydrogen content
and density on PGA that uses cold and epithermal
neutrons by numerical simulations and validated
the simulation results through PGA experiments.
The results revealed the importance of the effect of
the hydrogen density on PGA and the hydrogencontent2). In the simulations and experiments, we
confirmed that the measurement sensitivities
varied by more than 30% depending on thehydrogen density. Although this effect is observedin a hydrogen sample, it can also intrinsically occur
in other nuclides. The variation is a severe problem
for PGA, requiring a few percent accuracy in mostcases. The same effect cannot be neglected inmeasurement facilities that use neutrons otherthan those in the thermal energy region. Thus, thesample density, especially hydrogen density, affects
the experiments in many fields, such as in PGA
using cold and epithermal neutrons andastrophysics and nuclear energy requiring nuclear
cross-section data.

Development of a Pulsed Neutron
Correlation Method
Measuring the amount of nuclear material
contained in wastes discharged from nuclear
facilities is crucial for nuclear material control.
Implementing nuclear material accountancy andsecurity measures requires a rapid and highsensitive nuclear material detection method.
Therefore, we have developed the pulsed neutron
correlation (PNC) method1) which uses the samemeasurement system as the fast neutron directinterrogation (FNDI) method. In other words, thePNC and FNDI methods differ only in their dataprocessing algorithms. In the FNDI method, theneutron detection signals are recorded as thenumber of counts at specific intervals (typically 10μs). The analytical results are obtained from thenumber of counts. However, the PNC method
records the time when neutrons are counted(timestamp data), and the time difference between
each count is used in the quantitative analysis.
Experiments comparing the PNC and FNDI methods
were conducted at nuclear fuel cycle safetyengineering research facility (NUCEF). The
measured object was a drum containing concreterubble weighing 232 kg. The drums were equippedwith pipes for sample loading, and a plutonium
sample was attached to the center of the drum formeasurement. The plutonium samples of 30 mg
were measured using the PNC and FNDI methods.
Detecting the 30 mg plutonium using the FNDI
method measured in 30 seconds was challenging.
However, the 30 mg plutonium was detected within
30 s using the PNC method. Hence, the PNC method
can be considered effective for nuclear material
accountancy and security measures.

References
1) M. Komeda, et al., Appl. Radiat. Isot. 188, 110391 (2022).
2) M. Maeda, et al., Sci. Rep. 12, 6287 (2022).

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

12

FY2022 NSEC Group Activity

Research Group for Reactor Physics and Thermal-Hydraulics
Technology
In FY 2022, the Research Group for Reactor Physics
and Thermal-Hydraulics Technology was launched
as a merger of the Reactor Physics and Thermal
Hydraulics Groups. The group’s mission is todevelop individual and multiphysics simulation
technologies. We are developing an advanced
neutronics/thermal-hydraulics coupling simulation
system to enhance the safety and improve thedesign of light water reactors.

JAMPANJAMPAN1) is a new multiphysics platform toaccommodate coupling simulations. The platform
has been developed to realize the advanced
neutronics/thermal-hydraulics coupling simulation.
We performed a coupling test2) of the neutronics
code MVP and the thermal-hydraulics code JUPITER.
Figure 1 shows the calculation geometry for a 4 x 4fuel bundle system where water at room
temperature and atmospheric pressure is filled. Air
was injected through some orifices from thebottom of the system; no heat transfer from thefuel pins was considered. Figure 2 shows thecalculated result of void fraction and relative powerin the axial (z) direction. It was confirmed that thedata were properly transferred between the codes
on JAMPAN. We will perform further tests forrealistic simulations.

z [mm]
1500

Fig. 2Integral Tests for JENDL-5
The fifth version of Japanese Evaluated Nuclear
Data Library, JENDL-5,3) was released in December
2021. We performed integral tests of JENDL-5 forcritical4) and shielding5) experiments. The criticalbenchmark tests were performed for experiments
listed in the International Criticality Safety
Benchmark Evaluation Project (ICSBEP) handbook6)
and conducted at the JAEA. The shielding
benchmark tests were performed for FNS andOKTAVIAN experiments conducted at the JAEA andOsaka University, respectively. We have confirmedthat JENDL-5 gives better than or the same
prediction accuracy as JENDL-4.0 in many test cases.

Snapshot at
t = 10 s

References
1) T. Kamiya, et al., Proc. ICONE29, ICONE29-91828 (2022).
2) T. Kamiya, et al., 2022 Fall Meeting of AESJ, 1F04 (2022)(in Japanese).
3) O. Iwamoto, et al., J. Nucl. Sci. Technol. 60, 1 (2023),
https://doi.org/10.1080/00223131.2022.2141903 .
4) K. Tada, et al., J. Nucl. Sci. Technol. Latest Article (2023),
https://doi.org/10.1080/00223131.2023.2197439 .
5) C. Konno, et al., J. Nucl. Sci. Technol. 60, 1046 (2023),
https://doi.org/10.1080/00223131.2022.2164372 .
6) OECD/NEA, NEA/NSC/DOC(95)03 (2014).

400 mm950

Calculation
region in MVP

Fuel
pin

550
Bubbles(browncoloredregions)

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

0Fig. 1

Calculated results of void fraction andrelative power in the axial direction

Calculation geometry for a 4 x 4 fuel bundle
system13

FY2022 NSEC Group Activity

Research Group for Nuclear Transmutation System
The Research Group for Nuclear Transmutation
System is developing an accelerator-driven system(ADS) devoted to minor actinides (MAs)transmutation into short-lived or stable nuclides.
The effects and scenarios of introducing
partitioning and transmutation technologies,
including ADS, into the nuclear fuel cycle are also
being studied.

the matrix exponential method (MEM), a typicalburnup calculation method with a small
computational cost, the calculation fails if the time
step (Δ𝑡) is longer than several hours. However, theshort step resulted in too long calculation time.
Therefore, the MEM was improved based on theconcept shown in Fig. 1.
We calculated the amount of an isotope at Δ𝑡 1
when it decays along its half-life (the blue line). The
true solution is approximately 0.3; however, thefirst-order MEM (the orange line) results in anegative value, and the calculation fails. However,using ∆𝑡 at approximately 0.6 instead of Δ𝑡 , theMEM gave the correct result (the purple dot in the
figure). ∆𝑡 can be practically estimated by anequation for a single isotope, the idea of the
Okamura explicit method (OEM). Two methods
were extended to the second order, and thesecond-order OEM transpose gave the best results2).
The OEM enabled us to extend the time step fromseveral hours to 30 days, for which the crosssection is sufficiently constant, and improve thecomputation time by a factor of approximately 100.
Consequently, approximately 200 nuclides can be
managed in the NMB code, and estimating theimpact on geological disposal was enabled.

The Attractiveness of the ADS Fuel
Cycle
Although installing the partitioning andtransmutation technology is beneficial in reducing
the disposal site scale, it is necessary to evaluate
the possible negative impact on nuclear
nonproliferation resulting from handling the uniquenuclear fuel for the ADS, primarily comprising
plutonium (Pu) and MA. By assessing the usabilityof the material as nuclear material (i.e., explosion
devices) for criticality and heat generation, an index
called material attractiveness can be obtained. The
higher the attractiveness, the stricter management
is required.
The attractiveness of Pu in the ADS fuel was
evaluated and compared with that of mixed-oxide(MOX) fuel assemblies for conventional boilingwater reactors (BWRs). All items in the ADS fuelcycle, regardless of whether fresh or spent fuel, had
the same attractiveness as Pu in the BWR–MOX
spent fuel assembly (Table 1). This result indicatesthat the management, i.e., the required
measurement accuracy and inspection frequencyof nuclear material in the ADS cycle, can be relaxed
to the same level as the spent fuel of the current
BWR spent fuel, even for the fresh fuel.

Amount1① Consider
solution at Δt = 1

0.8
0.6

True

0.4

Good

0.2
0
0
-0.2

Table 1
Material attractiveness* of Pu in theaccelerator-driven system (ADS) cycle1)
Item
ADS
MOX for BWR
Fresh fuel3
2
Spent fuel3
3
Others**3* Attractiveness is defined at four levels:
1 (high), 2 (medium), 3 (low), and 4 (very low).
** Pellet, Pin, Nitride powder, Cd cathode-0.4

Fig. 1

0.5③ What if is usedinstead of in MEM1st ? ⇒ OEM method!

1

1.5

2

② MEM(1st) fails.
(negative value)

Concept of OEM method

References
1) A. Oizumi, H. Sagara, International Symposium on ZeroCarbon Energy Systems P-03 (2023).
2) T. Okamura, R. Katano, et al., J. Nucl. Sci. Technol. 60(6),632 (2023).

Fast Depletion Calculation for
NMB

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

The NMB (Nuclear Material Balance) code is used
to evaluate material flow within the nuclear
industry for future scenarios. In this code
approximately 10,000 burnup calculations are
performed to determine changes in the isotopes
inside many reactors with reasonable accuracy. In

14

FY2022 NSEC Group Activity

Research Group for Corrosion Resistant Materials
We have been researching the corrosion
phenomena of metallic materials used in nuclear
facilities. In the event of corrosion, the componentsof the nuclear facility are prone to degradation,
which might cause holes and cracks. Thus, we focus
on the corrosion mechanism to develop corrosion
prediction and prevention methods and improve
the reliability of nuclear facilities.

be applied before immersion in the LBE to achieve
corrosion resistance through dense film formation.
An oxygen concentration of approximately 10-7 –10-5 wt.% was deemed suitable when the oxide film
had attained a specific thickness, whereas a higher
oxygen concentration was expected to benecessary when the film was thin.

Inhibition of the Crevice Corrosion
on Type 316 Stainless SteelbyIntroducing Chelated Cu2+ into theCrevice

The chelated Cu2+ complex as [Cu(EDTA)]2- wasemployed as an external means to introduce Cu2+ions into the interior of the crevice, functioning as
an inhibitor against crevice corrosion in stainlesssteels1). Crevice corrosion tests and electrochemicalmeasurements substantiated the influence of Cu2+
within the crevice through the migration of[Cu(EDTA)]2-. The initiation time of crevice
corrosion was prolonged, and the corroded area
was decreased through [Cu(EDTA)]2- migration (Fig.
1). The corrosion inhibition mechanism occurs in
the following manner:(1) The decline in pH within the crevice is mitigatedthrough the reaction of [Cu(EDTA)]2- with H+ ions.
(2) The active dissolution of stainless steel isrestrained by dissociationg Cu2+ ions from the[Cu(EDTA)]2- complex.

Fig. 1Crevice corrosion initiation time of 316
stainless steel

Fig. 2Conceptional image of the calculation modelof corrosion on 9Cr-1Mo steel in molten leadbismuth eutectic (LBE) (M: metal element)

Calculation Model of theCorrosion on 9Cr-1Mo Steel
Includes the Oxide Film Formation
Process in Molten Lead-Bismuth
Eutectic (LBE)
At the Japan Atomic Energy Agency (JAEA), we
developed an accelerator-driven system (ADS) for
minor actinide transmutation and used molten LBE,
known for its moderately low melting point, highboiling point, and scientific inertness, as ADS
medium. Adjusting the oxygen concentration to
reduce the corrosion rate of materials immersed inmolten LBE is crucial. The developed calculation
model incorporates oxide film formation,
precipitated film formation, and film dissolution2).
The developed model enables us to derive thecorrosion characteristics of 9Cr-1Mo steel in LBE
using the three parameters below: (1) the ratio
between the thickness of the oxide film and the
diffusion layer, (2) the iron concentration in the LBE(Fig. 2), and (3) the operating temperature of the
ADS. According to the developed model, a preoxidized film thickness of more than 10-7 m should

References
1) T. Aoyama, et al., Corrosion Science 210, 110850 (2023).
2) K. Komatsu, JAEA-Research 2021-019 (2022).

Contact (Group Leader):IGARASHI Takahiro
igarashi.takahiro@jaea.go.jp
15

FY2022 NSEC Group Activity

Research Group for Radiation Materials Engineering
Oxidation Behavior of Zircaloy-4
Cladding in a Mixture of Air andSteam

The mechanical properties of materials used innuclear power systems change following
microstructural evolution. We have conducted
several experimental and simulation studies to
elucidate the mechanism and behavior predictionof the property change of nuclear materials while
trying to combine experimental studies andcomputational science methods. In studying thecandidate materials for accident-tolerant fuelcladdings, basic experimental research aims at
elucidating the mechanisms of stress corrosion
cracking, oxidation processes in steam1), andirradiation damage in ceramics2). Furthermore, topredict the macroscopic mechanical properties ofactual materials through computer simulation, we
analyze the defect structures using first principle
studies3) to large-scale mechanical simulation
technology. We also experimentally research thecompatibility and irradiation effects of materials
and liquid metals used in the accelerator-driven
system (ADS), which is expected as a partitioning
and transmutation technology.

In severe accidents in the spent fuel pool and otherair ingress accidents in nuclear power plants, thecladding is likely oxidized in an air–steam mixture.
Therefore, it is crucial to understand the nature ofoxidation and its kinetics in that environment.
Oxidation tests were conducted at 800 °C on
Zircaloy-4 specimens in a mixture of air + steamwith various component ratios. Oxidation kinetics,
details of the oxide layer, and hydrogen pick-up in
the specimen were studied to investigate theoxidation mechanism in each condition. Zirconium
nitride precipitation in the oxide layer during theinitial stages of the pre-breakaway (BA) oxidation
stage and the widespread porous oxide growth on
the cladding surface in the latter post-BA oxidation
stage are related to the oxidation mechanism in theair–steam mixture (Fig. 2).
(a) (b) (c):Oxidation
consumes O2
in the pore,and ZrN forms,(d): Outer
atmospheresupplied into
the pore(e): ZrN reoxidized andpore shrinks.
(f): Lower O2
partialpressure in the
mixturepermits poreto survives.

Irradiation Influence on Material
Corrosion in the ADS
The influence of irradiation on the material
corrosion in liquid lead–bismuth eutectic (LBE) was
experimentally simulated using ion irradiation of
10.5 MeV-Fe3+ at 450 °C and ex-situ corrosion tests
at 450 °C for 330 h. For 316L steels, the thickness ofthe oxidation layers for the irradiated area
increased approximately twice as much as thenonirradiated at saturated oxygen concentration in
LBE (Fig. 1)4). The synergy effects of a high-energy
accelerator become apparent but should beverified using spallation neutrons fromexperimental irradiation facilities.

Fig. 2 Schematic illustration of pore development in
the initial oxide layer formed duringoxidation in dry air (left) and in an air–steam
mixture (right)

References
1) Y. Nemoto, et al., J. Nucl. Mater. 575, 154209 (2023).
2) N. Ishikawa, et al., Nanotechnology 33,235303 (2022).
3) I. Lobzenko, et al., Results in Materials 17, 100364 (2023).
4) N. Okubo, et al., Quantum Beam Sci. 5, 27(2021).

Fig. 1

Contact (Group Leader*):
OKUBO Nariaki
okubo.nariaki@jaea.go.jp

Oxide thickness of nonirradiated andirradiated areas after corrosion tests at low
and saturated oxygen concentrations for
316L specimens irradiated at 4 and 8 dpa*

16

since Apr. 2023

FY2022 NSEC Group Activity

Research Group for High Temperature Science on Fuel Materials
In April 2022, former Development Group for LWR
Advanced Technology joined us. We cover R&D on
advanced nuclear fuels, characteristics of fueldebris, and fission product (FP) behavior during
severe accidents (SAs) to contribute to sustainable
progress in nuclear energy. Experiments are
performed on cold and hot materials using various
high-temperature heating devices, analytical
instruments, and property measurement apparatus.
We also use computational science to reinforce theobtained experimental results using the firstprinciples, thermodynamics, and fuel performance
analysis methods and the databases we developed.

thermal insulation for valves above the CRD rail.
Thus, reaction tests of Cs with concrete and thermal
insulation at various temperatures were performed
to determine trapping mechanism to clarify thechemical interactions. The reaction results withconcrete show that the interactions of CsOH andCaCO3 in concrete occur even at room temperature
to form Cs2CO3(H2O)3, and water-insoluble CsAlSiO4
forms around 200 oC1). The results on siliceous
thermal insulation show that the thermal insulation
shrunk significantly (Fig. 2), but its weight increased
by 70 % – 80 %. Furthermore, the leaching test
results of samples after the reaction tests were
proposed to generate water-insoluble CsAlSiO4
around 600 oC2). In the future, ECUME will be
improved based on newly obtained data for
estimating water solubility as with the Cs
distribution in 1F.

Advanced Fuel Fabrication
One of the key engineering technologies for the
fabrication of nitride fuels for minor actinide (MA)transmutation is the external gelation technique toobtain MA nitride particles from MA solutions
without powder processes. Toward thedemonstration on plutonium in Nuclear fuel cycle
safety engineering research facility (NUCEF), we
assembled an external gelation system (Fig. 1) inRes. Build. No.4 to learn the techniques for making
gel particles using rare earth or uranium assurrogate elements. In this method a feed solution
comprises nitrate, nanocarbon dispersion, andpolyvinyl alcohol. The feed solution is dropped
through a vibrating fine nozzle into an ammonia
water bath, where the gel particles form. By
adjusting the feed composition, viscosity, dispenser
pressure and nozzle frequency, we successfully
obtained the sphere particles of dysprosium (Dy)(Fig. 1(c)). In the following step we optimize theabove conditions for smaller diameters and higher
metal element densities of the nitride particles
after calcination and carbothermic nitridation.

Nozzlenozzle1mm

exciter

feed
tank
100〜
150Hz

gelation
bath

(a)

(b)

(c)

Fig. 1 Appearance of external gelation system (a),dripping nozzle (b), and Dy gel particles (c)FP Behavior
Information on the distribution and water solubilityof radioactive cesium (Cs), major radiation sources
within TEPCO’s Fukushima Daiichi Nuclear Power
Station (1F), is crucial for a reasonable safetyassessment for fuel debris retrieval anddecommissioning. Thus, we investigate the Cs
chemistry in the reactor, which determines the Cs
transportation during SAs to improve the FP
chemistry database ECUME.
The internal investigation of 1F showed that thedose rates in the shield plug above the primarycontainment vessel and at the rail of the control rod
drive (CRD) mechanism are unexpectedly high.
These high dose rates indicate some trapping
effects of Cs on the concrete of shield plugs andFig. 2

Appearance of thermal insulations before(upper) and after (lower) reaction test with Cs

References
1) Vu Nhut Luu, et al., J. Nucl. Sci. Technol. 60(2), 153 (2023).
2) M. Rizaal, et al., ACS Omega 7, 29326 (2022).

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

17

FY2022 NSEC Group Activity

Research Group for Nuclear Fuel Cycle Science
Spent fuel from nuclear power plants contains
elements such as U, Pu, minor actinides (MAs: Np,
Am, and Cm), and fission products (FPs). In theseelements, U and Pu can be recycled as resources.
Some MAs have high radioactive toxicity for long
period, and thus transmuting systems, such as theaccelerator-driven system (ADS), have been
proposed to make these MAs into short-lived or
stable nuclides for mitigating environmental
impacts. Therefore, we have been studying themutual separation of U, Pu, MAs, and FPs fromspent nuclear fuels by hydrometallurgical methods.
Since the ratios of MA, which can be transmuted in
an ADS core, is limited, the residual MAs in the
spent transmutation fuels should be separated andreused to transmute MAs effectively. Therefore, wehave also been conducting research anddevelopment on the reprocessing of MA
transmutation fuel by pyrochemical methods.

Only Am was back extracted through contact with
low nitric acid concentrations. The current SELECT
process requires two extraction procedures andtwo back extraction procedures, whereas thepresent results indicate that Am could be separatedusing one extraction procedure and two backextraction procedures 1).

FP Compounds Formed in MA
Nitride Fuels
FP compounds formed in MA transmutation nitride
fuels are of concern to us because chemically stable
actinide–FP compounds can affect the conditions
and recovery yields of the pyrochemical
reprocessing of the spent fuels. The intermetallic
compounds of actinides with the platinum groupelements (Ru, Rh, and Pd), the second-mostabundant group of FPs, precipitate out in U–Pu
nitride fuels. Similar compounds are expected toform in MA nitride fuels; however, experimental
studies have not been reported.
In our studies using a surrogate element (Gd) and
Np, the formation of MPd3+x (M = Gd, Np)
compounds by reacting the nitrides with Pd wasobserved, as expected. It was also found that thesolid-state chemical reaction with CdCl2 can convert
the MPd3+x compounds to chlorides. These
chlorides are soluble in molten salts and can beprocessed in pyrochemical methods. The resulting
by-products (Pd–Cd alloys) are expected to be
separated when the chlorides dissolve in molten
salts 2)*.

Minor Actinides Separation byHydrometallurgical Method
We developed several extractants and proposed anovel hydrometallurgical process called Solvent
Extraction from Liquid waste using Extractants of
CHON-type for Transmutation (SELECT) to recycle
nuclear materials and separate actinides. This
process comprises four steps: (i) the recovery of U
and Pu from a dissolution solution of spent nuclear
fuels, (ii) the recovery of Am, Cm, and rare earth
elements (REs) from high-level liquid waste (HLW),(iii) the separation of Am and Cm from REs, and (iv)the separation of Am and Cm.
The experiments with HLW confirmed theeffectiveness of the SELECT process, and research is
ongoing for further improvement in the separation
process.
We focused on using a solvent comprising alkyl
diamide amine (ADAAM) and branched-tetraoctyl
nitriloacetic acid diamide (B-TONAADA) (Fig. 1) toseparate Am more easily.
The solvent extracted La, Ce, Pr, Nd, and Am, but
not Y, Sm, Eu, and Cm from 1.5 mol/L nitric acid.

*This study contains the results of “R&D on the
Nitride Fuel Cycle for MA Transmutation to
Enhance Safety and Economy” entrusted to theJapan Atomic Energy Agency by the Ministry of
Education, Culture, Sports, Science andTechnology of Japan (MEXT).
References
1) H. Suzuki, et al., 2023 Annual Meeting of AESJ 1H10
(2023) (in Japanese).
2) H. Hayashi, et al., J. Radioanal. Nucl. Chem. 332, 503(2023).

HO

N
O

Fig. 1N

N
O

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

O
N

N

N
O

O

Structures of ADAAM (left) and BTONAADA (right)

18

FY2022 NSEC Group Activity

Research Group for Environmental Science
We study the dynamics of radionuclide transfer in
the atmospheric, terrestrial, and oceanic
environments to improve the assessment
technology of environmental radioactivity.
Computer models are developed and validated to
predict radionuclide transfer in the environments.
We developed atmospheric prediction systems(WSPEEDI-II and WSPEEDI-DB) and an oceanic
prediction system (STEAMER). Field surveys are also
conducted to collect environmental samples,
especially in terrestrial and oceanic environments.
The samples are analyzed with advanced
technology and used to understand the dynamics ofradionuclide transfer and validate the computermodels.

monitoring data: Phase-1 (March 12-13), Phase-2(March 12-17), and Phase-3 (March 12-31). The
experiments demonstrated that an initial constantrelease rate was gradually optimized by comparing
simulated and observed air concentrations andsurface depositions. In Phase-3, the estimatedrelease rate was nearly consistent with the release
rate optimized in the previous study1) (Fig. 1).
Furthermore, the source term estimation
methodology enables us to understand theoverview
ofenvironmental
radioactive
contamination in the early stage.
We will further improve the atmospheric dispersion
prediction systems. In particular, the coupling witha local scale high-resolution atmospheric dispersion
prediction using Large-Eddy Simulation (LES) modelis an ongoing study.

Dependency of Source Term
Estimation on Environmental
Monitoring Data
When nuclear accidents occur, estimating accurate
source information on radionuclide release into theatmosphere is crucial for assessing environmental
radioactive
contamination.
Therefore,
wedeveloped a source term estimation methodology
based on Bayesian inference with an atmosphericdispersion model and environmental monitoringdata1). The methodology depends on thecharacteristics of the environmental monitoring
data, i.e., type and spatiotemporal resolution.
We examined the dependency of source term
estimation by adapting the methodology to the
Fukushima Daiichi nuclear power station (1F)
accident in 2011 with WSPEEDI-DB and various
environmental monitoring data2). WSPEEDI-DB
comprises a meteorological dynamic model and a
Lagrangian particle atmospheric dispersion model.
We used air concentrations of the dust sampling
data and suspended particulate matter data,
surface depositions of the daily fallout data, and asurface deposition map to estimate the source term.
As a result of sensitivity experiments with different
environmental monitoring data, we found that highspatiotemporal resolutions of environmental
monitoring data are crucial for accurate source
term estimation. Moreover, simultaneously using
the air concentration and surface deposition data ismore effective than using either one.
We also conducted hypothetical experiments
assuming the actual situation during the 1F
accident to validate the real-time application of thesource term estimation methodology. We created ascenario with three periods depending on the dataacquisition situation with increasing environmental

Fig. 1

Prior and estimated release rates in Phase3 in the hypothetical real-time source term
estimation experiments

References
1) H. Terada, et al., J. Environ. Radioact. 213, 106104 (2020).
2) H. Terada, et al., J. Nucl. Sci. Technol. 60(8), 980 (2023),
https://doi.org/10.1080/00223131.2022.2162139 .

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

19

FY2022 NSEC Group Activity

Research Group for Radiation Transport Analysis
Computer simulation is essential for researchingand developing nuclear and radiation sciences. The
Particle and Heavy Ion Transport code System(PHITS) is the radiation transport simulation code
being developed by our group. We conduct studies
on radiological protection and radiation effects tomeet various new societal needs. In addition tocode development, we perform experiments tovalidate newly installed functions in PHITS. This
paper summarizes our progress in FY2022.

The latest defect generation efficiency model wasincorporated into PHITS. The results show that thecalculated values correlate with the experimental
values within standard deviations.

Development of the Terrestrial
Soft Error Rate (SER) Estimation
MethodSoft errors caused by secondary cosmic-ray
neutrons are a reliability problem forsemiconductor devices in the terrestrial
environment. We developed a method to estimate
the terrestrial SER based on simulation and onetime irradiation testing using various neutron
sources. Using PHITS, this method calculates thedependence of single-event upset cross-sections on
the neutron energy and the critical charge (i.e., theminimum charge deposition required to cause
upset). The critical charge is adjusted to reproduce
the SER measured by one-time neutron irradiation.
Our proposed method provided reasonable
terrestrial SERs, regardless of the single measured
data used for terrestrial SER estimation (Fig. 1).

Upgrades of the PHITS CodeA new version of PHITS (version 3.31) was
developed and released to the public, where thecompatibility with high-energy nuclear datalibraries and the algorithm of the track-structuremodes have been improved. The number of newly
registered PHITS users in FY2022 wasapproximately 1,300, including 560 Japanese users.
The followings are the major upgraded features in
the latest version. More detailed information isavailable on the PHITS homepage1).

Generalized track structure mode
Terrestrial SER (a.u.)

ITSART (Ion Track Structure calculation model for
Arbitrary Radiation and Targets) has been upgraded
to use predefined ionization potential for more
precise treatment of compounds. It was applied tosimulate the luminescence of SiO2 substrate
exposed to protons.

Electron track-structure mode
The electron track structure theoretically predicts
the initial yield of hydrated electrons, an essential
species in the water radiolysis chemical processes.
The mode includes a nano-order electron behavior
calculation function in semiconductor silicon toextend the electron track-structure mode. Thisfunction enables a more comprehensive analysis ofradiation effects on silicon-based devices.

400

J-PARC

CYRIC

AIST

300
200
100
0

Board side
Package side
Direction of neutron irradiation
Fig. 1 Terrestrial soft error rate (SER) estimated by
PHITS with each measured data. The
differences in SER are within a factor of two.

Reference
1) T. Sato, et al., J. Nucl. Sci. Technol. 55, 684 (2018),
https://phits.jaea.go.jp/ .

Displacement Damage Experiment
Using 120 GeV Protons
The number of displacements per atom (DPA) is
used to indicate the amount of displacement
damage in accelerator structural materials. This
study measured the electrical resistance increases
due to irradiation defects related to DPA in Al, Cu,
and W at cryogenic temperatures (8 K) at the Fermi
National Accelerator Laboratory using 120 GeV
protons related to DPA. The electrical resistanceincrease in the samples during proton irradiation
was on the order of tens of nano- to micro-ohms.

Contact (Group Leader):TSUDA Shuichi
tsuda.shuichi@jaea.go.jp20

FY2022 NSEC Group Activity

Research Group for Nuclear Chemistry
Elucidating the chemical reactions and states ofradionuclides in solutions and at interfaces willsolve various problems in the nuclear field,
especially in the back-end field, for the safe
treatment and disposal of nuclear waste. Our goal
is to elucidate the complex reactions involving
nuclear materials and radiation and predict the
behavior of radionuclides in solutions and theenvironment. We are researching and developing
analytical methods using new principles andtechniques necessary.

This analytical technique will be used to detectminor U(V) species in various samples.

Development of Actinide
Chemistry by Vibrational Sum
Frequency Generation
Spectroscopy
Vibrational sum frequency generation (VSFG)
spectroscopy is nonlinear using ultrashort pulse
lasers. Although VSFG spectroscopy is a unique andpowerful technique for studying the molecular
structure of interfaces, it was not applied toactinides because of the difficulty in experimentswith alpha nuclides. Recently, we successfully
observed a uranium complex at the oil/waterinterface in solvent extraction using VSFG
spectroscopy.1) This observation revealed thaturanyl ions (UO22+) can cross the oil/water interface
by forming the uranyl-extractant complex (Fig. 1).
This is the mechanism by which uranyl ions canfreely transfer between the oil and aqueous phases.
This study is the first milestone for developing
actinide chemistry from the point of interface
chemistry using VSFG spectroscopy.

Application of High-energy
Resolution X-ray Absorption
Spectroscopy to Uranium(V)Compounds
The oxidation state of U is critical for understanding
its migration behavior in the environment. X-ray
absorption
near-edge
structure(XANES)
spectroscopy is used to assess the oxidation stateof U in various samples. However, the broadeningof core hole electrons affects the normal XANES
spectrum, making the original electronic structure
undetectable. We applied the high-energy
resolution fluorescence detection (HERFD) XANES
to access the original electronic structure of U(V) in
FeUO4.2) The HERFD-XANES spectrum of FeUO4
showed the peak splitting hidden in theconventional XANES spectra (Fig. 2). Theoreticalsimulation revealed that the splitting of the 6dorbital of U(V) in FeUO4 caused the peak splitting.

Fig. 1

Proposed model of the phase transfer ofuranyl
ions
with
the
di(2ethylhexyl)phosphoric acid extractant

Fig. 2Crystal structure of FeUO4 (left), the X-ray
absorption near-edge structure (XANES), andhigh-energy
resolution
fluorescence
detection (HERFD) XANES spectrum of FeUO4
with the theoretical calculations (right)

References
1) R. Kusaka, et al., J. Phys. Chem. Lett. 13(30), 7065 (2022).
2) T. Yomogida, et al., Inorg. Chem. 61(50), 20206 (2022).

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

21

FY2022 NSEC Publications

Publication list
* Works with underlined numbers were published before
FY2022 (not included in the lists of previous NSEC reports).

Nuclear Science and Reactor Engineering Division
Nuclear Data Center
Papers1) Measurement of the transverse asymmetry of rays in the 117Sn(n,)118Sn reaction, S. Endo, T.
Okudaira, R. Abe, H. Fujioka, K. Hirota, A. Kimura,
M. Kitaguchi, T. Oku, K. Sakai, T. Shima, H. M.
Shimizu, S. Takada, S. Takahashi, T. Yamamoto, H.
Yoshikawa & T. Yoshioka, Phys. Rev. C 106(6),064601 (2022).
2) Am‐241 Neutron Capture Cross Section in thekeV region using Si and Fe‐filtered neutron
beams, G. Rovira, A. Kimura, S. Nakamura, S.
Endo, O. Iwamoto, N. Iwamoto, T. Katabuchi, Y.
Kodama & H. Nakano, J. Nucl. Sci. Tech. 60(5),489 (2023).
3) Thermal‐Neutron capture cross‐section
measurements of Neptunium‐237 with graphite
thermal column in KUR, S. Nakamura, Y.
Shibahara, S. Endo & A. Kimura, J. Nucl. Sci. Tech.
59(11), 1388 (2022).
4) Neutron total and capture cross‐section
measurements of Gd‐155 and Gd‐157 in thethermal energy region with the Li‐glass detectors
and NaI(Tl) spectrometer installed in J‐
PARC·MLF·ANNRI, A. Kimura, S. Nakamura, S.
Endo, G. Rovira, O. Iwamoto, N. Iwamoto, H.
Harada, T. Katabuchi, K. Terada, J.‐i. Hori, Y.
Shibahara & T. Fujii, J. Nucl. Sci. Tech. 60(6), 678(2023).
5) Calculation of ‐decay half‐lives within a Skyrme‐
Hartree‐Fock‐Bogoliubov
energydensityfunctional with the proton‐neutron quasiparticle
random‐phase approximation and isoscalarpairing strengths optimized by a Bayesian
method, F. Minato, Z. Niu & H. Liang, Phys. Rev. C
106(2), 024306 (2022).
6) Japanese evaluated nuclear data library version
5: JENDL‐5, O. Iwamoto, N. Iwamoto, S. Kunieda,
F. Minato, S. Nakayama, Y. Abe, K. Tsubakihara, S.
Okumura, C. Ishizuka, T. Yoshida, S. Chiba, N.
Otuka, J.‐C. Sublet, H. Iwamoto, K. Yamamoto, Y.
Nagaya, K. Tada., C. Konno, N. Matsuda, K.
Yokoyama, H. Taninaka, A. Oizumi, M. Fukushima,

S. Okita, G. Chiba, S. Sato, M. Ohta & S. Kwon, J.
Nucl. Sci. Tech. 60(1), 1 (2023).
7) Estimation of double‐differential cross‐sectionsof 9Be(p,xn) reaction for new nuclear data library
JENDL‐5, S. Kunieda, K. Yamamoto, C. Konno, Y.
Iwamoto, O. Iwamoto, Y. Wakabayashi & Y. Ikeda,
J. Neutron Res. 24(3‐4), 329 (2022).
8) Collaboration with Dr. Efrem Sh. Soukhovitsukii:
our fortuitous experiences on optical model
analysis, his contribution to nuclear data
activities of Japan and a posthumous study onlight‐nuclei, S. Kunieda, O. Iwamoto, T. Fukahori& S. Chiba, Eur. Phys. J. A 59, 2 (2023).
9) Neutron capture cross‐section measurement by
mass spectrometry for Pb‐204 irradiated in JRR‐
3, S. Nakamura, Y. Shibahara, A. Kimura, S. Endo
& T. Shizuma, J. Nucl. Sci. Tech. 60(9), 1133 (2023).
10) Evaluation of covariance data in JENDL, O.
Iwamoto, EPJ Web of Conf. 281, 00009 (2023).
11) Updates to the AMUR code for R‐matrix
analyses on heavy nuclei, S. Kunieda, S. Endo &A. Kimura, EPJ Web of Conf. 281, 00017 (2023).
12) Uncertainty estimation in neutron TOF
measurements with ANNRI, A. Kimura, S.
Nakamura & S. Endo, EPJ Web of Conf. 281,
00025 (2023).
13) Covariance of resonance parameters ascribedto systematic uncertainties in experiments, S.
Endo, A. Kimura, S. Nakamura, O. Iwamoto, N.
Iwamoto & G. Rovira, EPJ Web of Conf. 281,
00012 (2023).
14) JENDL photonuclear data file 2016, N. Iwamoto,
K. Kosako & T. Fukahori, J. Nucl. Sci. Tech. 60(8),911 (2023).
15) EXFOR‐based simultaneous evaluation ofneutron‐induced uranium and plutonium fission
cross sections for JENDL‐5, N. Otuka & O.
Iwamoto, J. Nucl. Sci. Tech. 59(8), 1004 (2022).
16) Effect of sample density in prompt γ‐rayanalysis, M. Maeda, M. Segawa, Y. Toh, S. Endo,
S. Nakamura & A. Kimura, Sci. Rep. 12, 6287

22

FY2022 NSEC Publications(2022).
17) Development of a neutron beam monitor witha thin plastic scintillator for nuclear datameasurement using spallation neutron source, H.
Nakano, T. Katabuchi, G. Rovira, Y. Kodama, K.
Terada, A. Kimura, S. Nakamura & S. Endo, J. Nucl.
Sci. Tech. 59(12), 1499 (2022).
18) Nuclear data generation by machine learning (I)application to angular distributions for nucleon‐
nucleus scattering, S. Watanabe, F. Minato, M.
Kimura & N. Iwamoto, J. Nucl. Sci. Tech. 59(11),1399 (2022).
19) Angular distribution of  rays from the p‐wave
resonance of Sn‐118, J. Koga, S. Takada, S. Endo,
H. Fujioka, K. Hirota, K. Ishizaki, A. Kimura, M.
Kitaguchi, Y. Niinomi, T. Okudaira, K. Sakai, T.
Shima, H. M. Shimizu, Y. Tani, T. Yamamoto, H.
Yoshikawa & T. Yoshioka, Phys. Rev. C 105(5),054615 (2022).
20) Low‐lying dipole strength distribution in Pb‐204,
T. Shizuma, S. Endo, A. Kimura, R. Massarczyk, R.
Schwengner, R. Beyer, T. Hensel, H. Hoffmann, A.
Junghans, K. Römer, S. Turkat, A. Wagner & N.
Tsoneva, Phys. Rev. C 106(4), 044326 (2022).
21) Water contents in aggregates and cement
pastes determined by gravimetric analysis andprompt γ‐ray analysis, N. Kinoshita, T. Noto, H.
Nakashima, K. Kosako, T. Kato, Y. Kuroiwa, M.
Kurabe, Y. Sasaki, K. Torii, M. Maeda, Y. Toh, A.
Kimura, S. Nakamura, S. Endo & M. Segawa, J.
Radioanal. Nucl. Chem. 332, 479 (2023).
22) Fast‐neutron capture cross section datameasurement of minor actinides fordevelopment of nuclear transmutation systems,
T. Katabuchi, O. Iwamoto, J.‐i. Hori, A. Kimura, N.
Iwamoto, S. Nakamura, G. Rovira, S. Endo, Y.
Shibahara, K. Terada, Y. Kodama, H. Nakano, Y.
Sato & S. Matsuura, EPJ Web of Conf. 281, 00014(2023).
23) Application of the extended bias factor method
for highly reliable benchmark suite, M. Tokashiki,
T. Ikehara, K. Tada, T. Egawa, K. Yokoyama & O.
Iwamoto, EPJ Web of Conf. 281, 00002 (2023).
24) CO2‐2 Measurement of Thermal‐Neutron
Capture Cross‐Section of the 237Np(n,) Reaction
with TC‐Pn in KUR, S. Nakamura, S. Endo, A.
Kimura & Y. Shibahara, KURNS PROGRESSREPORT 2021, 93 (2022).
25) Release of the latest general‐purpose nuclear
data library JENDL‐5, O. Iwamoto, Isotope News
783, 2 (2022) (in Japanese).

JAEA Reports
3) Theoretical Evaluation of Neutron Thermal
Scattering Laws of Heavy Water for JENDL‐5, A.
ICHIHARA & Y. ABE, JAEA‐Conf 2022‐001, 175(2022).
4) Nuclear data processing code FRENDY version 2,
K. Tada, A. Yamamoto, S. Kunieda & Y. Nagaya,
JAEA‐Data/Code 2022‐009 (2023).

1) Outline of JENDL‐5, O. Iwamoto, JAEA‐Conf 2022‐
001, 21 (2022).
2) Am‐241 Neutron Capture Cross Section
Measurement and Resonance Analysis, G.
ROVIRA, A. KIMURA, S. NAKAMURA, S. ENDO, O.
IWAMOTO, N. IWAMOTO, T. KATABUCHI, Y.
KODAMA, H. NAKANO & Y. SATO, JAEA‐Conf2022‐001, 91 (2022).

Research Group for Nuclear Sensing
Papers769 (2023).
4) Water contents in aggregates and cement pastes
determined by gravimetric analysis and prompt
γ‐ray analysis, N. Kinoshita, T. Noto, H.
Nakashima, K. Kosako, T. Kato, Y. Kuroiwa, M.
Kurabe, Y. Sasaki, K. Torii, M. Maeda, Y. Toh, A.
Kimura, S. Nakamura, S. Endo & M. Segawa, J.
Radioanal. Nucl. Chem. 332, 479 (2023).
5) CO8‐1 Demonstration experiment of nuclear
material detection using a low‐cost assay system,
M. Komeda, Y. Toh, Y. Kitamura, T. Misawa & K.
Tanabe, KURNS PROGRESS REPORT 2021, 222(2022).

1) Effect of sample density in prompt γ‐ray analysis,
M. Maeda, M. Segawa, Y. Toh, S. Endo, S.
Nakamura & A. Kimura, Sci. Rep. 12, 6287 (2022).
2) New data processing method for nuclear
material measurement using pulsed neutrons, M.
Komeda & Y. Toh, Applied Radiat. Isotopes 188,
110391 (2022).
3) Development of a water Cherenkov neutron
detector for the active rotation method anddemonstration of nuclear material detection, K.
Tanabe, M. Komeda, Y. Toh, Y. Kitamura, T.
Misawa, K. Tsuchiya, N. Akiba, H. Kakuda, K.
Shibasaki & H. Sagara, J. Nucl. Sci. Tech. 60(7),23FY2022 NSEC Publications
Patents
3) Segawa M., Maeda M. & Toh Y., “Analyticalmethod and system for alpha emitting nuclides”,
Japanese Patent Application 2023‐016184(2023.02.06)
4) Maeda M., Toh Y. & M. Komeda, “Material
detector”, Japanese Patent Application 2023‐
047902 (2023.03.24)

1) Segawa M., Toh Y., Maeda M. & Nishinaka I.,“ANALYSIS METHOD AND ANALYSIS DEVICE OF α‐
RAY‐EMITTING NUCLIDE”, Japanese Patent
7128479 (2022.08.23)
2) Komeda M. & Toh Y., “NUCLEAR MATERIALDETECTOR”,
Japanese
Patent7219442(2023.01.31)

Research Group for Reactor Physics and Thermal‐Hydraulics Technology
Papers10) Numerical simulation method using a Cartesian
grid for oxidation of core materials under steam‐
starved conditions, S. Yamashita, T. Sato, Y.
Nagae, M. Kurata & H. Yoshida, J. Nucl. Sci. Tech.
60(9), 1029 (2023).
11) JENDL‐5 benchmark test for shielding
applications, C. Konno, M. Ohta, S. Kwon, S.
Ohnishi, N. Yamano & S. Sato, J. Nucl. Sci. Tech.
60(9), 1046 (2023).
12) Development of ACE file perturbation tool
using FRENDY, K. Tada, R. Kondo, T. Endo & A.
Yamamoto, J. Nucl. Sci. Tech. 60(6), 624 (2023).
13) Development of Particle Collection Techniqueby Using Bubble Breakup Phenomenon in
Venturi Tube, S. UESAWA, M. SHIBATA & H.
YOSHIDA, Jpn. J. Multiphase Flow 37(1), 55(2023) (in Japanese).
14) Numerical Simulation of Annular Dispersed
Flow in Simplified Subchannel of Light Water
Cooled Fast Reactor RBWR, H. Yoshida, N.
Horiguchi, A. Ono, H. Furuichi & K. Katono, Proc.
ICONE29, ICONE29‐91630 (2022).
15) Development of a Numerical Simulation
Method for Air Cooling of Fuel Debris by JUPITER,
S. Yamashita, S. Uesawa & H. Yoshida, Proc.
ICONE29, ICONE29‐ 89345 (2022).
16) Investigation of the Impact of Difference
Between FRENDY and NJOY2016 on Neutronics
Calculations, M. Ono, M. Tojo, K. Tada & A.
Yamamoto, Proc. PHYSOR 2022 (2022).
17) Applicability of Neutronics Design Calculation
Method for Axially Heterogeneous Core of RBWR
(Resource‐Renewable Boiling Water Reactor), K.
Yokoi, T. Hino, K. Ishii, J. Miwa, H. Soneda, M. A.
Kowalski, E. Shwageraus, B. Kochunas, S.y. Choi,
Y.x. Liu & Y. Nagaya, Proc. PHYSOR 2022 (2022).
18) Implementation of Resonance Upscattering
Treatment in FRENDY Nuclear Data Processing
System, A. Yamamoto, T. Endo, G. Chiba & K. Tada,

1) Experimental investigation of spray coolingbehavior in 4×4 simulated fuel bundle, T.
Nagatake, M. Shibata, H. Yoshida, Y. Nemoto & Y.
Kaji, J. Nucl. Sci. Tech. 60(3), 320 (2023).
2) Development of Nuclear Data Processing CodeFRENDY Version 2, K. Tada, A. Yamamoto, T. Endo,
G. Chiba, M. Ono & M. Tojo, Proc. PHYSOR 2022
(2022).
3) Development of JAEA Advanced Multi‐Physics
Analysis Platform for Nuclear Systems, T. Kamiya,
A. Ono, K. Tada, H. Akie, Y. Nagaya, H. Yoshida &T. Kawanishi, Proc. ICONE29, ICONE29‐91828(2022).
4) MATXS Multigroup File Problem due to NJOY
Unresolved Resonance Processing, C. Konno, K.
Tada & S. Kwon, Proc. ICRS14/RPSD22, 440(2022).
5) A Numerical simulation method to evaluate heattransfer of fuel debris in air cooling by JUPITER,
1; Project overview and the applicability to theactual reactor system, S. Yamashita, S. Uesawa,
A. Ono & H. Yoshida, Proc. NTHAS‐12 (2022).
6) A Numerical simulation method to evaluate heattransfer of fuel debris in air cooling by JUPITER,
2; Validation of porous model for naturalconvective heat transfer, S. Uesawa, S. Yamashita,
M. Shibata & H. Yoshida, Proc. NTHAS‐12 (2022).
7) Prediction of Critical Heat Flux for the Forced
Convective Boiling Based on the Mechanism, A.
Ono, H. Sakashita, S. Yamashita, T. Suzuki & H.
Yoshida, Proc. NTHAS‐12 (2022).
8) Measurement of Fragments of Wall‐impinging
Liquid Jet in a Shallow Pool, N. Horiguchi, H.
Yoshida, A. Kaneko & Y. Abe, Proc. NTHAS‐12(2022).
9) Development of the Numerical Simulation
Method for Molten Core Behavior in Lower Head
Based on MPS Method, T. Nagatake & H. Yoshida,
Proc. NTHAS‐12 (2022).

24

FY2022 NSEC Publications
Nucl. Sci. Eng. 196(11), 1267 (2022).
19) ACE‐FRENDY‐CBZ: a new neutronics analysis
sequence using multi‐group neutron transport
calculations, G. Chiba, A. Yamamoto & K. Tada, J.
Nucl. Sci. Tech. 60(2), 132 (2023).
20) Japanese evaluated nuclear data library version
5: JENDL‐5, O. Iwamoto, N. Iwamoto, S. Kunieda,
F. Minato, S. Nakayama, Y. Abe, K. Tsubakihara, S.
Okumura, C. Ishizuka, T. Yoshida, S. Chiba, N.
Otuka, J.‐C. Sublet, H. Iwamoto, K. Yamamoto, Y.
Nagaya, K. Tada., C. Konno, N. Matsuda, K.
Yokoyama, H. Taninaka, A. Oizumi, M. Fukushima,
S. Okita, G. Chiba, S. Sato, M. Ohta & S. Kwon, J.
Nucl. Sci. Tech. 60(1), 1 (2023).
21) Vibration of Cantilever by Jet Impinging in Axial
Direction, D. Tobita, H. Monji, S. Yamashita, N.
Horiguchi, H. Yoshida & T. Sugawara, Proc.
NTHAS‐12 (2022).
22) Experimental study of liquid spreading andatomization due to jet impingement in liquid–
liquid systems, S. Yamamura, K. Fujiwara, K.
Honda, H. Yoshida, N. Horiguchi, A. Kaneko & Y.
Abe, Phys. Fluids 34(8), 082110 (2022).

23) Estimation of double‐differential cross‐sectionsof 9Be(p,xn) reaction for new nuclear data library
JENDL‐5, S. Kunieda, K. Yamamoto, C. Konno, Y.
Iwamoto, O. Iwamoto, Y. Wakabayashi & Y. Ikeda,
J. Neutron Res. 24(3‐4), 329 (2022).
24) Application of the extended bias factor method
for highly reliable benchmark suite, M. Tokashiki,
T. Ikehara, K. Tada, T. Egawa, K. Yokoyama & O.
Iwamoto, EPJ Web of Conf. 281, 00002 (2023).
25) Development of the simplified boiling model
applied for the large scale simulation by thedetailed two‐phase flow analysis based on thesurface tracking, A. Ono, S. Yamashita, H.
Sakashita, T. Suzuki & H. Yoshida, Proc. the 26th
National Symposium on Power & Energy Systems(2022) (in Japanese).
26) Development of particle removal technique by
using bubble breakup phenomenon inconverging‐diverging nozzle, S. Uesawa & H.
Yoshida, 混相流シンポジウム 2022 講演論文
集 (インターネット) (2022) (in Japanese).

JAEA Reports
1) Integral Tests of Preliminary JENDL‐5 for Criticaland Shielding Experiments, Y. NAGAYA, K.
YOKOYAMA, K. TADA & C. KONNO, JAEA‐Conf2022‐001, 27 (2022).
2) Development of FRENDY Version 2, K. TADA, A.

YAMAMOTO, T. ENDO, G. CHIBA, M. ONO & M.
TOJO, JAEA‐Conf 2022‐001, 39 (2022).
3) Nuclear data processing code FRENDY version 2,
K. Tada, A. Yamamoto, S. Kunieda & Y. Nagaya,
JAEA‐Data/Code 2022‐009 (2023).

Research Group for Nuclear Transmutation System
Papers4) Cost‐reduced depletion calculation including
short half‐life nuclides for nuclear fuel cycle
simulation, T. Okamura, R. Katano, A. Oizumi, K.
Nishihara, M. Nakase, H. Asano &K. Takeshita, J.
Nucl. Sci. Tech. 60(6), 632 (2023).
5) Japanese evaluated nuclear data library version
5: JENDL‐5, O. Iwamoto, N. Iwamoto, S. Kunieda,
F. Minato, S. Nakayama, Y. Abe, K. Tsubakihara, S.
Okumura, C. Ishizuka, T. Yoshida, S. Chiba, N.
Otuka, J.‐C. Sublet, H. Iwamoto, K. Yamamoto, Y.
Nagaya, K. Tada., C. Konno, N. Matsuda, K.
Yokoyama, H. Taninaka, A. Oizumi, M. Fukushima,
S. Okita, G. Chiba, S. Sato, M. Ohta & S. Kwon, J.
Nucl. Sci. Tech. 60(1), 1 (2023).
6) Measurement of nuclide production crosssections for proton‐induced reactions on natNi
and natZr at 0.4, 1.3, 2.2, and 3.0 GeV, H. Takeshita,
S.‐i. Meigo, H. Matsuda, H. Iwamoto, K. Nakano,1)

Sensitivity Coefficient Evaluation of an
Accelerator‐Driven System Using ROM‐Lasso
Method, R. Katano, A. Yamamoto &T. Endo, Nucl.
Sci. Eng. 196(10), 1194 (2022).
2) Measurement of 107‐MeV proton‐induced
double‐differential thick target neutron yields
for Fe, Pb, and Bi using a fixed‐field alternating
gradient accelerator at Kyoto University, H.
Iwamoto, K. Nakano, S.‐I. Meigo, D. Satoh, Y.
Iwamoto, K. Sugihara, K. Nishio, Y. Ishi, T. Uesugi,
Y. Kuriyama, H. Yashima, K. Okabe, H. Makii, K.
Hirose, R. Orlandi, F. Suzaki, A. Oizumi, K.
Tsukada, F. Maekawa & Y. Mori, J. Nucl. Sci. Tech.
60(4), 435 (2023).
3) Proposal and application of ROM‐Lasso method
for sensitivity coefficient evaluation, R. Katano, A.
Yamamoto & T. Endo, Proc. PHYSOR 2022, 2032
(2022).

25

FY2022 NSEC Publications
Y. Watanabe & F. Maekawa, Nucl. Inst. &Methods in Phys. Res., B 527, 17 (2022).
7) Vibration of Cantilever by Jet Impinging in Axial
Direction, D. Tobita, H. Monji, S. Yamashita, N.
Horiguchi, H. Yoshida & T. Sugawara, Proc.
NTHAS‐12 (2022).
8) B4. NMB4.0 : Development of Integrated Nuclear
Fuel Cycle Simulation Code, T. Okamura, R.
Katano, A. Oizumi, K. Nishihara, M. Nakase, H.

Asano & K. Takeshita、BULL. LAB. ADV. NUCL.
ENERGY, Tokyo Inst. Tech., 29 (2021).
9) Non‐proliferation features in partitioning andtransmutation cycle using accelerator‐driven
system, 3; Safeguards by design by using
Material Attractiveness evaluation for TRU fuelcycle, A. Oizumi & H. Sagara, 第 43 回日本核物質管理学会年次大会会議論文集 ( インターネット) (2022) (in Japanese).

JAEA Reports
JAEA‐Conf 2022‐001, 129 (2022).
3) Present Status of R&D in JAEA on Partitioning
and Transmutation Technology, JAEA‐Review
2022‐052 (2023) (in Japanese).
4) Unified description of the fission probability for
higIly excited nuclei, H. IWAMOTO, JAEA‐Conf2021‐001, 24 (2022).
5) Nuclear data generation using machine learning,
H. IWAMOTO, JAEA‐Conf 2021‐001, 83 (2022).

1) Role of ADS and its development issues, K.
NISHIHARA, JAEA‐Conf 2022‐001, 63 (2022).
2) Measurement of 107‐MeV proton‐induced
double‐differential neutron yields for iron forresearch and development of accelerator‐driven
systems, H. IWAMOTO, K. NAKANO, S.‐i. MEIGO,
D. SATOH, Y. IWAMOTO, Y. ISHI, T. UESUGI, Y.
KURIYAMA, H. YASHIMA, K. NISHIO, K. HIROSE, H.
MAKII, K. OKABE, F. SUZAKI, A. OIZUMI, R.
ORLANDI, K. TSUKADA, F. MAEKAWA & Y. MORI,

Fuels and Materials Engineering Division
Research Group for Corrosion Resistant Materials
Papers
実験力学 Jikken‐Rikigaku 22(2), 105 (2022) (in1) Approach to elucidate corrosion mechanism on
metal surface using first‐principles calculations, T.
Igarashi, K. Otani, A. Komatsu, C. Kato & M.
Sakairi, 防 錆 管 理 Bousei‐Kanri 66(4), 141(2022) (in Japanese).
2) Effects of Potential on the Electrical Conductivityof a Solution within a Crevice of Stainless Steel in
High‐Temperature Water, Y. Soma, A. Komatsu &C. Kato, Corrosion 78(6), 503 (2022).
3) Effect of Sr‐90 Dissolved Solution on Corrosion
Potential of Type 316L Stainless Steel, T. Aoyama,
C. Kato, T. Sato, N. Sano, N. Yamashita & F. Ueno,
材料と環境 Zairyo‐to‐Kankyo 71(4), 110 (2022)(in Japanese).
4) Introduction of Cu2+ to the inside of the crevice
by chelation and its effect on crevice corrosion ofType 316L stainless steel, T. Aoyama & C. Kato,
Corrosion Sci. 210, Part 2, 110850 (2023).
5) Evaluation of thermal diffusivity of uniaxial CFRP
sheet by offset periodic laser heating method,
S. Nagata, S. Miyake, T. Igarashi, H. Ota & T. Nishi,

Japanese).
6) Effects of a Corrosion Inhibitor on the Corrosionof Steels under Thin Solution Layers, Y. Monma,
M. Sakairi, F. Ueno & K. Otani, 材 料 と 環 境
Zairyo‐to‐Kankyo 71(5), 133 (2022) (in Japanese).
7) Electrochemical Behavior of Carbon Steels Under
Thickness‐controlled Solution Layer, Y. Monma,
M. Sakairi, F. Ueno & K. Otani, 材 料 と 環 境
Zairyo‐to‐Kankyo 71(4), 121 (2022) (in Japanese).
8) Novel Methanobacterium Strain Induces Severe
Corrosion by Retrieving Electrons from Fe0 undera Freshwater Environment, S.‐i. Hirano, S. Ihara,
S. Wakai, Y. Dotsuta, K. Otani, T. Kitagaki, F. Ueno
& A. Okamoto, Microorganisms 10(2), 270(2022).
9) Investigation of the oxidation behavior of
Zircaloy‐4 cladding in a mixture of air and steam,Y. Nemoto, Y. Ishijima, K. Kondo, Y. Fujimura & Y.
Kaji, J. Nucl. Mater. 575, 154209 (2023).

26

FY2022 NSEC Publications
JAEA Report
1) Calculation of appropriate oxygen concentration
for corrosion inhibition of 9Cr‐1Mo steel inmolten lead bismuth eutectic, A. Komatsu, JAEA‐
Research 2021‐019 (2022) (in Japanese).

Research Group for Radiation Materials Engineering
Papers1) Positron annihilation study of tungsten exposed
to low‐energy deuterium plasma, T. Hirade, H.
Furuta, Y. Torikai, Y. Fujimura & K. Michishio, JJAP
Conf. Proc. JWPS2019, 011106 (2023).
2) Surface nanostructures on Nb‐doped SrTiO3
irradiated with swift heavy ions at grazing
incidence, N. Ishikawa, Y. Fujimura, K. Kondo, G.L.
Szabo, R.A. Wilhelm, H. Ogawa & T. Taguchi,
Nanotechnology 33(23), 235303 (2022).
3) Investigation of the oxidation behavior of
Zircaloy‐4 cladding in a mixture of air and steam,Y. Nemoto, Y. Ishijima, K. Kondo, Y. Fujimura & Y.
Kaji, J. Nucl. Mater. 575, 154209 (2023).
4) Electronic Structure‐Based Modeling of
Dislocation Motion and Its Application to
Nanoscale Mechanics, T. Tsuru, 材料 J. the Soc.
Mater. Sci., Jpn 71(8), 660 (2022) (in Japanese).
5) Influence of group IV element on basic
mechanical properties of BCC medium‐entropy
alloys using machine‐learning potentials, I.
Lobzenko, Y. Shiihara, H. Mori & T. Tsuru, Comp.
Mater. Sci. 219, 112010 (2023).
6) Improved mechanical properties of Co‐free high‐entropy Cantor alloy: A first‐principles study, I.
Lobzenko, D. Wei, M. Itakura, Y. Shiihara & T.
Tsuru, Results Mater. 17, 100364 (2023).
7) Identification of Hydrogen Trapping in AluminumAlloys Via Muon Spin Relaxation Method andFirst‐Principles Calculations, T. Tsuru, K.
Nishimura, K. Matsuda, N. Nunomura, T. Namiki,
S. Lee, W. Higemoto, T. Matsuzaki, M. Yamaguchi,
K. Ebihara, K. Shimizu & H. Toda, Metal. Mater.
Trans. A 54, 2374 (2023).
8) Solid‐solution strengthening by Al and Cr in
FeCrAl oxide‐dispersion‐strengthened alloys, S.
Ukai, Y. Yano, T. Inoue & T. Sowa, Mater. Sci. Eng.
A 812, 141076 (2021).
9) Characterization and corrosion behavior of Al‐
added high Mn ODS austenitic steels in oxygen‐saturated lead–bismuth eutectic, H. Wang, H. Yu,
J. Liu, S. Kondo, N. Okubo & R. Kasada, Corrosion
Sci. 209, 110818 (2022).
10) Experimental investigation of spray coolingbehavior in 4×4 simulated fuel bundle, T.

Nagatake, M. Shibata, H. Yoshida, Y. Nemoto & Y.
Kaji, J. Nucl. Sci. Tech. 60(3), 320 (2023).
11) Grain refinement in titanium prevents low
temperature oxygen embrittlement, Y. Chong, R.
Gholizadeh, T. Tsuru, R. Zhang, K. Inoue, W. Gao,
A. Godfrey, M. Mitsuhara, J.W. Morris Jr., A.M.
Minor & N. Tsuji, Nature Communications 14,404 (2023).
12) Effects of local bonding between solute atoms
and vacancy on formation of nanoclusters in Al‐
Mg‐Si alloys, K. Kurihara, I. Lobzenko, T. Tsuru &A. Serizawa, J. Jpn Inst. Light Metals 72(2), 47(2022) (in Japanese).
13) The formation mechanism of radiocesium‐
bearing microparticles derived from the
Fukushima Daiichi nuclear power plant using
electron microscopy, H. Hagiwara, K. Kondo & A.
Hidaka, J. Radioanal. Nucl. Chem. 331(12), 5905
(2022).
14) Metalloid substitution elevates simultaneously
the strength and ductility of face‐centered‐cubic
high‐entropy alloys, D. Wei, L. Wang, Y. Zhang, W.
Gong, T. Tsuru, I. Lobzenko, J. Jiang, S. Harjo, T.
Kawasaki, J. W. Bae, W. Lu, Z. Lu, Y. Hayasaka, T.
Kiguchi, N.L. Okamoto, T. Ichitsubo, H.S. Kim, T.
Furuhara, E. Ma & H. Kato, Acta Mater. 225,
117571 (2022).
15) Atomic Stress State Inside fcc and bcc Random
Alloys: A First‐Principles Approach, Y. Shiihara, Y.
Itai, I. Lobzenko & T. Tsuru, Front. Mater. 9,895626 (2022).
16) Atomistic weak interaction criterion for the
specificity of liquid metal embrittlement, M.
Yamaguchi, T. Tsuru, M. Itakura & E. Abe, Sci. Rep.
12, 10886 (2022).
17) Interaction between solute atoms andvacancies in Al‐Mg‐X (X ＝ Si, Ge) alloys, K.
Kurihara, I. Lobzenko, T. Tsuru & A. Serizawa, J.
Jpn Inst. Light Metals 72(7), 427 (2022) (inJapanese).
18) Mechanical behaviors of equiatomic and near‐equiatomic face‐centered‐cubic phase high‐entropy alloys probed using in situ neutron
diffraction, D. Wei, W. Gong, T. Tsuru, T. Kawasaki,

27

FY2022 NSEC Publications
S. Harjo, B. Cai, P.K. Liaw, H. Kato, Int. J. Plast. 158,
103417 (2022).
19) Ultrahigh yield strength and large uniform
elongation achieved in ultrafine‐grained
titanium containing nitrogen, Y. Chong, T. Tsuru,
B. Guo, R. Gholizadeh, K. Inoue & N. Tsuji, Acta
Mater. 240, 118356 (2022).
20) Cleavages along {110} in bcc iron emit
dislocations from the curved crack fronts, T.
Suzudo, K.‐i. Ebihara, T. Tsuru & H. Mori, Sci. Rep.
12, 19701 (2022).
21) Si‐addition contributes to overcoming thestrength‐ductility trade‐off in high‐entropy alloys,
D. Wei, W. Gong, T. Tsuru, I. Lobzenko, X. Li, S.
Harjo, T. Kawasaki, H.‐S. Do, J.W. Bae, C. Wagner,
G. Laplanche, Y. Koizumi, H. Adachi, K. Aoyagi, A.
Chiba, B.‐J. Lee, H.S. Kim & H. Kato, Int. J. Plast.
159, 103443 (2022).

22) Effects of Thermal Aging on the Mechanical
Properties of FeCrAl‐ODS Alloy Claddings, Y. Yano,
T. Tanno, S. Ohtsuka, T. Kaito & S. Ukai, Mater.
Trans. 62(8), 1239 (2021).
23) Damage evaluations for BWR lower head insevere accident based on multi‐physics
simulations, J. Katsuyama, Y. Yamaguchi, Y.
Nemoto, T. Furuta & Y. Kaji, Proc. PVP 2022,
84609 (2022).
24) PCMI ANALYSES OF SIC CLADDED FUEL DURING
BWR LOCA WITH FEMAXI‐ATF, Y. Nakao, A. Yamaji,
Y. Nemoto & S. Yamashita, Proc. TOPFUEL 2022
(2022).
25) Fuel Performance Analysis of Cr‐coated Fuel
During Startup and Normal Operation of LWRs
Using FEMAXI‐8, S. Dehara, A. Yamaji, Y. Nemoto& S. Yamashita, Proc. TOPFUEL 2022 (2022).

Patent1) Hirade T., “Water clusters, water cluster
production methods, water cluster usage

methods”, Japanese Patent Application 2022‐
94929 (2022.6.13)

Research Group for High Temperature Science on Fuel Materials
Papers1) Study on chemical interaction between UO2 andZr at precisely controlled high temperatures, N.
Shirasu, T. Sato, A. Suzuki, Y. Nagae & M. Kurata,
J. Nucl. Sci. Tech. 60(6), 697 (2023).
2) High‐Temperature Gaseous Reaction of Cesiumwith Siliceous Thermal Insulation: The Potential
Implication to the Provenance of Enigmatic
Fukushima Cesium‐Bearing Material, M. Rizaal, K.
Nakajima, T. Saito, M. Osaka & K. Okamoto, ACS
Omega 7(33), 29326 (2022).
3) Study on cesium compound formation bychemical interaction of CsOH and concrete atelevated temperatures, V.N. Luu & K. Nakajima,
J. Nucl. Sci. Tech. 60(2), 153 (2023).
4) Chemical interaction between Sr vapor species
and nuclear reactor core structure, A. Mohamad,
K. Nakajima, S. Miwa & M. Osaka, J. Nucl. Sci.
Tech. 60(3), 215 (2023).
5) Radio‐tellurium released into the environment
during the complete oxidation of fuel cladding,containment venting and reactor building failureof the Fukushima accident, A. Hidaka, S.
Kawashima & M. Kajino, J. Nucl. Sci. Tech. 60(7),743 (2023).
6) Origin of Cs‐bearing silicate glass microparticles
observed during Fukushima accident andrecommendations on nuclear safety, A. Hidaka, J.
Radioanal. Nucl. Chem. 332(6), 1607 (2023).
7) Modeling of the P2M Past Fuel Melting
Experiments with the FEMAXI‐8 Code, A.
Mohamad & Y. Udagawa, Nucl. Tech. Latest
Article (2023).
8) Identification of Carbon in Glassy Cesium‐
Bearing
Microparticles
Using
Electron
Microscopy and Formation Mechanisms of theMicroparticles, A. Hidaka, Nucl. Tech. 208(2), 318(2022).
9) Alteration of fuel debris simulants by Bacillus
subtilis, J. Liu, Y. Dotsuta, T. Kitagaki, N. Aoyagi, H.
Mei, M. Takano & N. Kozai, J. Nucl. Sci. Tech.
60(8), 1002 (2023).

JAEA Reports
1)

Improvement of model for cesiumchemisorption onto stainless steel in severe
accident analysis code SAMPSON (Joint

research), S. MIWA, H. KARASAWA, K. NAKAJIMA,
C. KINO, E. SUZUKI & J. IMOTO, JAEA‐Data/Code2021‐022 (2023).

28

FY2022 NSEC Publications
2) Present Status of R&D in JAEA on Partitioning
and Transmutation Technology, JAEA‐Review

2022‐052 (2023) (in Japanese).

Research Group for Nuclear Fuel Cycle Science
PapersAn using TODGA and DTBA or DTPA
accompanying pH adjustment with lactic acidand ethylenediamine, Y. Sasaki, M. Kaneko, Y.
Ban, M. Matsumiya, M. Nakase & K. Takeshita,
Separation Sci. Tech. 57(16), 2543 (2022).

1) Formation of MPd3+x (M=Gd,Np) by the reactionof MN with Pd and chlorination of MPd3+x using
cadmium chloride, H. Hayashi, H. Shibata, T. Sato
& H. Otobe, J. Radioanal. Nucl. Chem. 332(2),503 (2023).
2) Multi‐stage extraction and separation of Ln and

JAEA Report
1) Present Status of R&D in JAEA on Partitioning
and Transmutation Technology, JAEA‐Review

2022‐052 (2023) (in Japanese).

PatentACTINOID RECOVERY METHOD USING THE SAME,AND SCANDIUM OR ACTINOID SEPARATIONMETHOD USING THE SAME”, Japanese Patent
7066091 (2022.05.02)

1) MATSUMURA T., SUZUKI H., WATABE H.,
TAKEUCHI M., KOFUJI H., KUNII S. & YOSHIDA T.,“RARE EARTH ELEMENT AND/OR ACTINOIDADSORBENT, RARE EARTH ELEMENT AND/OR

Chemistry, Environment, and Radiation Division
Research Group for Environmental Science
Papers1) Dependency of the source term estimation
method for radionuclides released into theatmosphere on the available environmental
monitoring data and its applicability to real‐timesource term estimation, H. Terada, H. Nagai, M.
Kadowaki & K. Tsuduki, J. Nucl. Sci. Tech. 60(8),980 (2023).
2) Thirty‐year simulation of environmental fate ofCs‐137 in the Abukuma River basin considering
the characteristics of Cs‐137 behavior in land
uses, T. Ikenoue, H. Shimadera, T. Nakanishi & A.
Kondo, Sci. the Total Environ. 876, 162846 (2023).
3) Application of Bayesian machine learning for
estimation of uncertainty in forecasted plumedirections by atmospheric dispersion simulations,M. Kadowaki, H. Nagai, T. Yoshida, H. Terada, K.
Tsuduki & H. Sawa, J. Nucl. Sci. Tech. 60(10), 1194
(2023).
4) A new approach to extracting biofilm fromenvironmental plastics using ultrasound‐assisted
syringe treatment for isotopic analyses, B.
Battulga, M. Atarashi‐Andoh, T. Nakanishi & J.
Koarashi, Sci. the Total Environ. 849, 157758(2023).
5) Statistical analysis of simulated oceanic
dispersionofdissolved
radionuclide
hypothetically released from the Fukushima Dai‐
ichi Nuclear Power Plant using long‐term
oceanographic reanalysis data, T. Ikenoue, H.
Kawamura & Y. Kamidaira, J. Nucl. Sci. Tech. 60(1),61 (2023).
6) Transfer of Cs‐137 to web‐building spiders,
Nephila clavata, and its pathways: a preliminary
study using stable carbon and nitrogen isotope
analyses, S. Tanaka, H. Kakinuma, T. Adati, M.
Atarashi‐Andoh & J. Koarashi, J. Nucl. Sci. Tech.
58(4), 507 (2021).
7) Atmospheric ammonia deposition and its role in29

FY2022 NSEC Publications
a cool‐temperate fragmented deciduous broad‐leaved forest, G. Katata, T. Yamaguchi, M.
Watanabe, K. Fukushima, M. Nakayama, H.
Nagano, J. Koarashi, R. Tateno & T. Kubota,
Atmospheric Environ. 298, 119640 (2023).
8) Spatial variation in soil respiration rate iscontrolled by the content of particulate organic
materials in the volcanic ash soil under aCryptomeria japonica plantation, Y. Abe, N. Liang,
M. Teramoto, J. Koarashi, M. Atarashi‐Andoh, S.
Hashimoto & T. Tange, Geoderma Regional 29,
e00529 (2022).
9) A Storm‐induced flood and associated nearshore
dispersal of the river‐derived suspended Cs‐137,
Y. Uchiyama, N. Tokunaga, K. Aduma, Y.
Kamidaira, D. Tsumune, T. Iwasaki, M. Yamada, Y.
Tadeda, T. Ishimaru, Y. Ito, Y.W. Watanabe, K.
Ikehara, M. Fukuda & Y. Onda, Sci. the Total
Environ. 816, 151573 (2022).
10) Ten years of warming increased plant‐derived
carbon accumulation in an East Asian monsoon
forest, J. Zhang, L. Kuang, Z. Mou, T. Kondo, J.
Koarashi, M. Atarashi‐Andoh, Y. Li, X. Tang, Ying‐

Ping Wang, J. Peñuelas, J. Sardans, D. Hui, H.
Lambers, W. Wu, J. Kaal, J. Li, N. Liang & Z. Liu,
Plant and Soil 481, 349 (2022).
11) Dependence of column ozone on future ODSs
and GHGs in the variability of 500‐ensemble
members, H. Akiyoshi, M. Kadowaki, Y.
Yamashita & T. Nagatomo, Sci. Rep. 13, 320(2023).
12) Development of a new model simulating
contaminations of forest resources withradiocesium in Fukushima, M. Ota & J. Koarashi,
Isotope news 784, 28 (2022) (in Japanese).
13) Local‐scale high‐resolution atmosphericdispersion and dose assessment system;
Realization for the first time of dose assessment
based on detailed calculation of radioactive
material dispersion taking buildings into account,
H. Nakayama, N. Onodera & D. Satoh, Isotope
news 785, 20 (2023) (in Japanese).
14) Parameter optimization for turbulent boundary
layer generation using ensemble Kalman filter, N.
Onodera, Y. Idomura, Y. Hasegawa & H.
Nakayama, Proc. CFD36 (2022) (in Japanese).

Research Group for Radiation Transport Analysis
Papers6) CRYSTAL CONFIGURATION DEPENDENCE OF
CSI(TL)SCINTILLATION
DETECTORSONENVIRONMENTAL DOSE RATE MEASUREMENT, S.
Tsuda & K. Saito, Radiat. Protection Dosimetry
198(17), 1283 (2022).
7) Post fission time evolution calculation by
FIFRELIN coupled with PHITS and DCHAIN, T.
Ogawa, O. Litaize, D. Mancusi, A. Chebboubi & O.
Serot, Eur. Phys. J. A 58, 153 (2022).
8) Benchmark shielding calculations for fusion andaccelerator‐driven sub‐critical systems, Y.
Iwamoto, S. Tsuda & T. Ogawa, Frontiers Energy
Res. 11, 1085264 (2023).
9) Initial yield of hydrated electron production fromwater radiolysis based on first‐principles
calculation, T. Kai, T. Toigawa, Y. Matsuya, Y.
Hirata, T. Tezuka, H. Tsuchida & A. Yokoya, RSC
Adv. 13(11), 7076 (2023).
10) Features of accelerator‐based neutron sourcefor boron neutron capture therapy calculated byparticle and heavy ion transport code system(PHITS), Y. Matsuya, T. Kusumoto, Y. Yachi, Y.
Hirata, M. Miwa, M. Ishikawa, H. Date, Y.
Iwamoto, S. Matsuyama & H. Fukunaga, AIP Adv.
12(2), 025013 (2022).

1) Development of a method for calculating
effective displacement damage doses insemiconductors and applications to space field,
Y. Iwamoto & T. Sato, PLoS ONE 17(11), e0276364(2022).
2) Application of a simple DNA damage model
developed for electrons to proton irradiation, Y.
Matsuya, T. Kai, A. Parisi, Y. Yoshii & T. Sato, Phys.
Med. Biol. 67(21), 215017 (2022).
3) Implementation of the electron track‐structuremode for silicon into PHITS for investigating theradiation effects in semiconductor devices, Y.
Hirata, T. Kai, T. Ogawa, Y. Matsuya & T. Sato, Jpn
J. Applied Phys. 61(10), 106004 (2022).
4) Microdosimetric Modeling of Relative Biological
Effectiveness for Skin Reactions: Possible Linkage
Between In Vitro and In Vivo Data, T. Sato, Y.
Matsuya & N. Hamada, Int. J. Rad. Oncol. Biol.
Phys. 114(1), 153 (2022).
5) Development of the DICOM‐based Monte Carlodose reconstruction system for a retrospective
study on the secondary cancer risk in carbon ion
radiotherapy, T. Furuta, Y. Koba, S. Hashimoto, W.
Chang, S. Yonai, S. Matsumoto, A. Ishikawa & T.
Sato, Phys. Med. Biol. 67(14), 145002 (2022).

30

FY2022 NSEC Publications11) Inflammatory Signaling and DNA Damage
Responses after Local Exposure to an InsolubleRadioactive Microparticle, Y. Matsuya, N.
Hamada, Y. Yachi, Y. Satou, M. Ishikawa, H. Date
& T. Sato, Cancers 14(4), 1045 (2022).
12) Measurement of 107‐MeV proton‐induced
double‐differential thick target neutron yields
for Fe, Pb, and Bi using a fixed‐field alternating
gradient accelerator at Kyoto University, H.
Iwamoto, K. Nakano, S.‐I. Meigo, D. Satoh, Y.
Iwamoto, K. Sugihara, K. Nishio, Y. Ishi, T. Uesugi,
Y. Kuriyama, H. Yashima, K. Okabe, H. Makii, K.
Hirose, R. Orlandi, F. Suzaki, A. Oizumi, K.
Tsukada, F. Maekawa & Y. Mori, J. Nucl. Sci. Tech.
60(4), 435 (2023).
13) Direct energy conversion using Ni/SiC Schottky
junction in Np‐237 and Am‐241 gamma ray
regions, T. Fukuda, M. Kobata, T. Shobu, K. Yoshii,
J. Kamiya, Y. Iwamoto, T. Makino, Y. Yamazaki, T.
Ohshima, Y. Shirai & T. Yaita, J. Applied Phys.
132(24), 245102 (2022).
14) Impact of the Lorentz force on electron track
structure and early DNA damage yields inmagnetic resonance‐guided radiotherapy, Y.
Yachi, T. Kai, Y. Matsuya, Y. Hirata, Y. Yoshii & H.
Date, Sci. Rep. 12, 16412 (2022).
15) Local environmental effects on cosmic rayobservations at Syowa Station in the Antarctic:
PARMA‐based snow cover correction forneutrons and machine learning approach forneutrons and muons, R. Kataoka, T. Sato, C. Kato,
A. Kadokura, M. Kozai, S. Miyake, K. Murase, L.
Yoshida, Y. Tomikawa & K. Munakata, J. Space
Weather Space Climate 12, 37 (2022).
16) Comparison of the Therapeutic Effects of[211At]NaAt and [131I]NaI in an NIS‐Expressing
Thyroid Cancer Mouse Model, T. Watabe, Y. Liu,
K. Kaneda‐Nakashima, T. Sato, Y. Shirakami, K.
Ooe, A. Toyoshima, E. Shimosegawa, Y. Wang, H.
Haba, T. Nakano, A. Shinohara & J. Hatazawa, Int.
J. Molecular Sci. 23(16), 9434 (2022).
17) Modeling the Transport and Deposition of Be‐
10 Produced by the Strongest Solar Proton Event
During the Holocene, T.C. Spiegl, S. Yoden, U.
Langematz, T. Sato, R. Chhin, S. Noda, F. Miyake,
K. Kusano, K. Schaar & M. Kunze, JGR
Atmospheres 127(13), e2021JD035658 (2022).
18) Mesospheric ionization during substorm
growth phase, K. Murase, R. Kataoka, T.
Nishiyama, K. Nishimura, T. Hashimoto, Y. Tanaka,
A. Kadokura, Y. Tomikawa, M. Tsutsumi, Y.
Ogawa., H.A. Uchida, K. Sato, S. Kasahara, T.

Mitani, S. Yokota, T. Hori, K. Keika, T. Takashima,
Y. Kasahara, S. Matsuda, M. Shoji, A. Matsuoka, I.
Shinohara, Y. Miyoshi, T. Sato, Y. Ebihara & T.
Tanaka, J. Space Weather Space Climate 12, 18(2022).
19) Microdosimetry Study of Proton Quality Factor
Using Analytic Model Calculations, A.
Papadopoulos, I. Kyriakou, Y. Matsuya, S. Incerti,
I.A. Daglis & D. Emfietzoglou, Applied Sci. 12(18),8950 (2022).
20) Translational study for stereotactic bodyradiotherapy against non‐small cell lung cancer,
including oligometastases, considering cancer
stem‐like cells enable predicting clinical outcome
from in vitro data, R. Saga, Y. Matsuya, H. Sato, K.
Hasegawa, H. Obara, F. Komai, H. Yoshino, M.
Aoki & Y. Hosokawa, Radiotherapy Oncol. 181,
109444 (2023).
21) An Analytical Method for Quantifying the Yields
of DNA Double‐Strand Breaks Coupled with
Strand Breaks by γ‐H2AX Focus Formation Assay
Based on Track‐Structure Simulation, Y. Yachi, Y.
Matsuya, Y. Yoshii, H. Fukunaga, H. Date & T. Kai,
Int. J. Molecular Sci. 24(2), 1386 (2023).
22) Coulomb Spike Modelling of Ion Sputtering of
Amorphous Water Ice, J.‐M. Costantini & T.
Ogawa, Quantum Beam Sci. 7(1), 7 (2023).
23) Estimation of double‐differential cross‐sectionsof 9Be(p,xn) reaction for new nuclear data library
JENDL‐5, S. Kunieda, K. Yamamoto, C. Konno, Y.
Iwamoto, O. Iwamoto, Y. Wakabayashi & Y. Ikeda,
J. Neutron Res. 24(3‐4), 329 (2022).
24) Photon dose rate distribution inside andoutside a brachytherapy room, A.H.A. Sabri, S.M.
Tajudin, M.Z.A. Aziz & T. Furuta, Radiol. Phys.
Tech. 16, 109 (2023).
25) Elucidation of the mechanism of biomoleculardamage in liquid water that occurs on ananoscale by ion beams, H. TSUCHIDA, T.
MAJIMA & T. KAI, 応用物理 Oyo‐Butsuri 91(9),553 (2022) (in Japanese).
26) Damage evaluations for BWR lower head insevere accident based on multi‐physics
simulations, J. Katsuyama, Y. Yamaguchi, Y.
Nemoto, T. Furuta & Y. Kaji, Proc. PVP 2022,
84609 (2022).
27) New feature of PHITS dedicated to calculate theatomic‐size transport of radiation, T. Ogawa, Y.
Hirata, Y. Matsuya & T. Kai, Isotope News 784, 13(2022) (in Japanese).

31

FY2022 NSEC Publications
JAEA Report
1) Calculation of displacement damage dose of
semiconductors using PHITS code, Y. IWAMOTO,

JAEA‐Conf 2022‐001, 97 (2022).

Research Group for Nuclear Chemistry
Papers1) Multi‐stage extraction and separation of Ln and
An using TODGA and DTBA or DTPA
accompanying pH adjustment with lactic acidand ethylenediamine, Y. Sasaki, M. Kaneko, Y.
Ban, M. Matsumiya, M. Nakase & K. Takeshita,
Separation Sci. Tech. 57(16), 2543 (2022).
2) Detection limit of electron spin resonance forJapanese deciduous tooth enamel and density
separation method for enamel–dentine
separation, T. Oka, A. Takahashi, K. Koarai, Y. Kino,
T. Sekine, Y. Shimizu, M. Chiba, T. Suzuki, K. Osaka,
K. Sasaki & H. Shinoda, J. Radiation Res. 63(4),609 (2022).
3) Raman identification and characterization ofchemical components included in simulated
nuclear fuel debris synthesized from uranium,
stainless steel, and zirconium, R. Kusaka, Y.
Kumagai, M. Watanabe, T. Sasaki, D. Akiyama, N.
Sato & A. Kirishima, J. Nucl. Sci. Tech. 60(5), 603(2023).
4) Application of High‐Energy‐Resolution X‐ray
Absorption Spectroscopy at the U L3‐Edge toAssess the U(V) Electronic Structure in FeUO4, T.
Yomogida, D. Akiyama, K. Ouchi, Y. Kumagai, K.
Higashi, Y. Kitatsuji, A. Kirishima, N. Kawamura &Y. Takahashi, Inorg. Chem. 61(50), 20206 (2022).
5) Development of Heavy Element Chemistry atInterfaces: Observing Actinide Complexes at the
Oil/Water Interface in Solvent Extraction by
Nonlinear Vibrational Spectroscopy, R. Kusaka &M. Watanabe, J. Phys. Chem. Lett. 13(30), 7065
(2022).
6) Unusually Kinetically Inert Monocationic
Neptunyl Complex with a Fluorescein‐Modified
1,10‐Phenanthroline‐2,9‐dicarboxylate Ligand:Specific Separation and Detection in Gel
Electrophoresis, K. Yamagata, K. Ouchi, K.
Marumo, Y. Tasaki‐Handa, T. Haraga & S. Saito,
Inorg. Chem. 62(2), 730 (2023).
7) Analysis of particles containing alpha‐emitters instagnant water at torus room of Fukushima Dai‐
ichi Nuclear Power Station’s Unit 2 reactor, T.
Yomogida, K. Ouchi, T. Oka, Y. Kitatsuji, Y. Koma &K. Konno, Sci. Rep. 12, 7191 (2022).
8) Complex formation of light and heavy

lanthanides with DGA and DOODA, and its
application to mutual separation in DGA–DOODA extraction system, D. Nomizu, Y. Sasaki,
M. Kaneko, M. Matsumiya & S. Katsuta, J.
Radioanal. Nucl. Chem. 331, 1483 (2022).
9) Fully Chelating N3O2‐Pentadentate Planar
Ligands Designed for the Strongest and Selective
Capture of Uranium from Seawater, T.
Mizumachi, M. Sato, M. Kaneko, T. Takeyama, S.
Tsushima & K. Takao, Inorg. Chem. 61(16), 6175
(2022).
10) Phase analysis of simulated nuclear fuel debris
synthesized using UO2, Zr, and stainless steel andleaching behavior of the fission products andmatrix elements, R. Tonna, T. Sasaki, Y. Kodama,
T. Kobayashi, D. Akiyama, A. Kirishima, N. Sato, Y.
Kumagai, R. Kusaka & M. Watanabe, Nucl. Eng.
Tech. 55(4), 1300 (2023).
11) Energy dissipation of para‐positronium inpolymers and silica glass, Y. Kobayashi, K. Sato, M.
Yamawaki, K. Michishio, T. Oka & M. Washio,
Applied Phys. Express 15(7), 076001 (2022).
12) Positrons and positronium in macromolecules:
Consequences of different charge states, Y.
Kobayashi, K. Sato, M. Yamawaki, K. Michishio, T.
Oka & M. Washio, Radiat. Phys. Chem. 202,
110590 (2023).
13) Lanthanide and Actinide Ion Complexes
Containing Organic Ligands Investigated by
Surface‐Enhanced
Infrared
Absorption
Spectroscopy, S. Hirata, R. Kusaka, S. Meiji, S.
Tamekuni, K. Okudera, S. Hamada, C. Sakamoto,T. Honda, K. Matsushita, S. Muramatsu, T. Ebata,
D. Kajiya, K.‐i. Saitow, T. Ikeda, T. Hirao, T. Haino,
M. Watanabe & Y. Inokuchi, Inorg. Chem. 62(1),474 (2023).
14) High‐sensitive XANES analysis at Ce L2‐edge for
Ce in bauxites using transition‐edge sensors:
Implications for Ti‐rich geological samples, W. Li,
S. Yamada, T. Hashimoto, T. Okumura, R.
Hayakawa, K. Nitta, O. Sekizawa, H. Suga, T.
Uruga, Y. Ichinohe, T. Sato, Y. Toyama, H. Noda, T.
Isobe, S. Takatori, T. Hiraki, H. Tatsuno, N.
Kominato, M.i Ito, Y. Sakai, H. Omamiuda, A.
Yamaguchi, T. Yomogida, H. Miura, M. Nagasawa,

32

FY2022 NSEC Publications
S. Okada & Y. Takahashi, Anal. Chim. Acta 1240,
340755 (2023).
15) Study on the relation between the crystal
structure and thermal stability of FeUO4 andCrUO4, D. Akiyama, R. Kusaka, Y. Kumagai, M.
Nakada, M. Watanabe, Y. Okamoto, T. Nagai, N.
Sato & A. Kirishima, J. Nucl. Mater. 568, 153847(2022).
16) Structure, stability, and actinide leaching ofsimulated nuclear fuel debris synthesized from
UO2, Zr, and stainless‐steel, A. Kirishima, D.
Akiyama, Y. Kumagai, R. Kusaka, M. Nakada, M.
Watanabe, T. Sasaki & N. Sato, J. Nucl. Mater. 567,
153842 (2022).
17) Radiation exposure and oxidative stress statusof wild Japanese macaques in the ex‐evacuation
zone of the Fukushima Daiichi Nuclear Power
Plant accident, R. Ishikawa, M. Suzuki, Y. Kino, S.
Endo, H. Nakajima, T. Oka, A. Takahashi, Y.
Shimizu, T. Suzuki, H. Shinoda, T. Yamashita, K.
Okutsu, M. Fukumoto & K. Chida, Proc. the 23rd
Workshop on Environmental Radioactivity KEK
Proc. 2022‐2, 61 (2022) (in Japanese).
18) A study on accuracy of analysis of the radiation‐induced component in the ESR spectra of teeth,
Y. Mitsuyasu, T. Oka, A. Takahashi, Y. Kino, K.
Okutsu, T. Sekine, T. Yamashita, Y. Shimizu, M.

Chiba, T. Suzuki, K. Osaka, K. Sasaki, M. Suzuki, M.
Fukumoto & H. Shinoda, Proc. the 23rd
Workshop on Environmental Radioactivity KEK
Proc. 2022‐2, 120 (2022) (in Japanese).
19) Variation of crystallinity and secondary ion
quantity of uranium particles with heating
temperature of Sample preparation, R. Tomita, J.
Tomita, T. Yomogida, D. Suzuki, K. Yasuda, F.
Esaka & Y. Miyamoto, Proc. the 23rd Workshop
on Environmental Radioactivity KEK Proc. 2022‐
2, 108 (2022) (in Japanese).
20) Chemical state analysis of uranium dioxide
particles by micro‐Raman mapping, T. Yomogida,
Y. Kitatsuji & Y. Miyamoto, Proc. the 23rd
Workshop on Environmental Radioactivity KEK
Proc. 2022‐2, 148 (2022) (in Japanese).
21) Production of Ac‐225 for Targeted Alpha
Therapy (TAT) using the experimental fast
reactor Joyo, S. Maeda & Y. Kitatsuji, エネルギ
ーレビュー 42(10), 19 (2022) (in Japanese).
22) A study of H2O2‐induced oxidative degradationof simulated fuel debris, Y. Kumagai, R. Kusaka,
M. Nakada, M. Watanabe, D. Akiyama, A.
Kirishima, N. Sato & T. Sasaki, Biannual J. Jpn Soc.
Radiation Chem. 113, 61 (2022) (in Japanese).

33

Reviewers
ABE Yosuke, ATARASHI‐ANDOH Mariko, BAN Yasutoshi,
HIRADE Tetsuya, IGARASHI Takahiro, ISHIKAWA Norito,
KAWAMURA Hideyuki, KITATSUJI Yoshihiro,
KUMAGAI Yuta, MATSUMURA Tatsuro, MIWA Shuhei,
NAGATAKE Taku, NAKANISHI Takahiro, OKA Toshitaka,
OKUBO Nariaki, SATOH Daiki, SHIBATA Hiroki,
TAKANO Masahide, TERADA Hiroaki, TSUDA Shuichi,
TSURU Tomohito, and the other anonymous one

Editorial Board‐ Chief Editor:
HAYASHI Hirokazu‐ Editors:
NAGATAKE Taku, TOIGAWA Tomohiro, IKENOUE Tsubasa,
KATO Chiaki, NAKAHARA Yukio

Nuclear Science and Engineering Center (NSEC)Japan Atomic Energy Agency (JAEA)
2‐4 Shirakata, Tokai‐mura, Naka‐gun, Ibaraki
319‐1195. JapanE‐mail : nsed‐web@jaea.go.jp
U R L : https://nsec.jaea.go.jp/