Symposium on Nuclear Data
2020

Report of Contributions

https://indico2.riken.jp/e/3789

Symposium on N … / Report of Contributions
Contribution ID: 1

Nuclear Data Activities in Nishina …
Type: not specified

Nuclear Data Activities in Nishina Center
Thursday, 26 November 2020 10:40 (40 minutes)
Nuclear Data Activities in Nishina Center

Primary author:

SAKURAI, Hiroyoshi (RIKEN Nishina Center for Accelerator-Based Science)

Presenter: SAKURAI, Hiroyoshi (RIKEN Nishina Center for Accelerator-Based Science)
Session Classification: Facility

September 8, 2024

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Contribution ID: 2

Proposal of 1 A class deuteron sin …
Type: not specified

Proposal of 1 A class deuteron single cell linac
Thursday, 26 November 2020 11:50 (30 minutes)

Presenter: OKUNO, Hiroki (RIKEN Nishina center for accelerator-based science)
Session Classification: Facility

September 8, 2024

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Development of energy-degraded …

Contribution ID: 3

Type: not specified

Development of energy-degraded RI beam andexpansion of nuclear reaction studies
Friday, 27 November 2020 09:30 (30 minutes)
Development of energy-degraded RI beam and expansion of nuclear reaction studies

Presenter: MICHIMASA, Shin’ichiro (CNS, Univ. of Tokyo)
Session Classification: NuclearPhysics2

September 8, 2024

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Nuclear spectroscopy at KISS

Contribution ID: 4

Type: not specified

Nuclear spectroscopy at KISS
Thursday, 26 November 2020 14:00 (30 minutes)
Nuclear spectroscopy at KISS

Presenter: HIRAYAMA, Yoshikazu (IPNS, KEK)
Session Classification: NuclearPhysics1

September 8, 2024

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Contribution ID: 5

Fission experiment with Es at JAE …
Type: not specified

Fission experiment with Es at JAEA tandem
accelerator facility
Thursday, 26 November 2020 14:30 (30 minutes)

Presenter: HIROSE, Kentaro (JAEA)
Session Classification: NuclearPhysics1

September 8, 2024

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Contribution ID: 6

Theoretical analysis of deuteron- …
Type: not specified

Theoretical analysis of deuteron-induced reactions
and development of deuteron nuclear database
Friday, 27 November 2020 10:00 (30 minutes)
Theoretical analysis of deuteron-induced reactions and development of deuteron nuclear database

Presenter: NAKAYAMA, Shinsuke (JAEA)
Session Classification: NuclearPhysics2

September 8, 2024

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Nuclear data study for Accelerator …

Contribution ID: 7

Type: not specified

Nuclear data study for Accelerator Driven System at
J-PARC
Thursday, 26 November 2020 11:20 (30 minutes)
Nuclear data study for Accelerator Driven System at J-PARC

Presenter: MEIGO, Shin-ichiro (J-PARC/JAEA)
Session Classification: Facility

September 8, 2024

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Contribution ID: 8

Production and Applications of Ra …
Type: not specified

Production and Applications of Radioisotopes at
RIKEN RI Beam Factory - Search for New Elements
through Diagnosis and Therapy of Cancer Thursday, 26 November 2020 15:20 (30 minutes)
Production and Applications of Radioisotopes at RIKEN RI Beam Factory - Search for New Elements through Diagnosis and Therapy of Cancer -Presenter: HABA, Hiromitsu (Nishina Center for Accelerator-Based Science, RIKEN)
Session Classification: NuclearMedicine

September 8, 2024

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Measurements of production cross …

Contribution ID: 9

Type: not specified

Measurements of production cross sections of
medical radioisotopes via charged-particle induced
reactionsThursday, 26 November 2020 15:50 (30 minutes)
Measurements of production cross sections of medical radioisotopes via charged-particle induced
reactions

Presenter: AIKAWA, Masayuki (Hokkaido University)
Session Classification: NuclearMedicine

September 8, 2024

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Development of Radioisotopes Pro …

Contribution ID: 10

Type: not specified

Development of Radioisotopes Production Methodby Accelerator-based Neutron: Activity at Kyushu
University 2020
Thursday, 26 November 2020 16:20 (30 minutes)
Development of Radioisotopes Production Method by Accelerator-based Neutron: Activity at Kyushu
University 2020

Presenter: KIN, Tadahiro (Kyushu University)
Session Classification: NuclearMedicine

September 8, 2024

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Contribution ID: 11

Deep Learning for Basic Science
Type: not specified

Deep Learning for Basic Science
Friday, 27 November 2020 13:30 (30 minutes)
Deep Learning for Basic Science

Presenter: TAKI, Masato (Rikkyo University)
Session Classification: DeepLearning

September 8, 2024

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Contribution ID: 12

Nuclear data generation using ma …
Type: not specified

Nuclear data generation using machine learning
Friday, 27 November 2020 14:30 (30 minutes)
Nuclear data generation using machine learning

Presenter: IWAMOTO, Hiroki (JAEA)
Session Classification: DeepLearning

September 8, 2024

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Data-driven approaches for nuclea …

Contribution ID: 13

Type: not specified

Data-driven approaches for nuclear shell-model
calculations
Friday, 27 November 2020 14:00 (30 minutes)
Data-driven approaches for nuclear shell-model calculations

Presenter: SHIMIZU, Noritaka (Center for Nuclear Study, University of Tokyo)
Session Classification: DeepLearning

September 8, 2024

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Exploration of automated data pro …

Contribution ID: 14

Type: not specified

Exploration of automated data processing for mass
production of nuclear data at RIBF
Friday, 27 November 2020 15:00 (30 minutes)
Exploration of automated data processing for mass production of nuclear data at RIBF

Presenter: KAWASE, Shoichiro (Kyushu University)
Session Classification: DeepLearning

September 8, 2024

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Unified description of the fission p …

Contribution ID: 15

Type: not specified

Unified description of the fission probability forhighly excited nuclei
Thursday, 26 November 2020 13:30 (30 minutes)
Unified description of the fission probability for highly excited nuclei

Presenters: IWAMOTO, Hiroki (JAEA); MEIGO, Shin-ichiro (J-PARC/JAEA)
Session Classification: NuclearPhysics1

September 8, 2024

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Contribution ID: 16

Isotope production in spallation re …
Type: not specified

Isotope production in spallation reaction of 93Zr and93Nb induced by proton and deuteronFriday, 27 November 2020 09:00 (30 minutes)
Isotope production in spallation reaction of 93Zr and 93Nb induced by proton and deuteron

Presenter: NAKANO, Keita (JAEA)
Session Classification: NuclearPhysics2

September 8, 2024

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Introduction to Nuclear Reactor T …

Contribution ID: 17

Type: not specified

Introduction to Nuclear Reactor Theory
Friday, 27 November 2020 10:50 (50 minutes)

Presenter: ENDO, Tomohiro (Nagoya University)
Session Classification: Tutorial

September 8, 2024

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Roles and current status of reactor …

Contribution ID: 18

Type: not specified

Roles and current status of reactor physics
experiment in research reactors
Friday, 27 November 2020 11:40 (40 minutes)
Roles and current status of reactor physics experiment in research reactors

Presenter: PYEON, Cheol Ho (Kyoto University)
Session Classification: Tutorial

September 8, 2024

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Opening/Welcome

Contribution ID: 19

Type: not specified

Opening/Welcome
Thursday, 26 November 2020 10:30 (10 minutes)

Presenter: SANAMI, Toshiya (KEK)

September 8, 2024

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Closing Remarks

Contribution ID: 20

Type: not specified

Closing Remarks
Friday, 27 November 2020 15:30 (30 minutes)

Presenters: SANAMI, Toshiya (KEK); WATANABE, Yukinobu (Kyushu University)

September 8, 2024

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Detection of Gamma Ray from …

Contribution ID: 23

Type: Poster Presentation

Detection of Gamma Ray from Sort-Lived Fission
Products at KUCA and KURNS-LINAC
Thursday, 26 November 2020 17:15 (1h 35m)
Quantification of radioactivity of fission products (FP) is very important for assessment of decay
heat after shutdown of a core, etc. For such assessments, comprehensive data sets of fission yieldand decay chain, such as JENDL/FPY&FPD-2011, have been developed. However, validation ofeach nuclide in such data sets has still been cumbersome. In this work, two detection techniquesof FPs are studied to give data for such validation.
In order to characterize reactions occurred in nuclear fuel, gamma ray spectroscopy was conducted
at Kyoto university critical facility assembly (KUCA). At KUCA, uranium (U)fuel of 93 wt% 235U
enrichment was loaded in C-core. They were moderated and shielded by light water. The core
power during the critical operation was 4.6 mW. Outside the tank of the core, a HP-Ge detectorof 30 % relative efficiency was set and the gamma ray was measured. As the results, peak spectraof fission products such as 90, 95, 97Y, 90,90m,91Rb, 87,88Br, 136Te, etc. were detected although
they were overwrapped by prompt gamma ray components. Due to the prompt components, therelative statistical accuracy was from 2 to 20 %. Thanks to the measurements during the criticaloperation, gamma rays of half-life shorter than 4 s was achieved.
Contrarily, 238U(n,g) gamma ray spectroscopy was conducted with the same HP-Ge for neutronsof thermal and resonance energy at the KU-LINAC-pulsed neutron source facility. The time offlight (TOF) of neutron was measured associated with beam pulse to identify the incident neutronenergy. The repetition rate of the pulse was 50 Hz. In the TOF spectrum after the so called “thermal
neutron peak”, time-background region was identified. The gamma ray in the region out of phaseof the beam pulse was considered emitted by decay of radioactive material of which half-life islonger than 20 ms. The measured peak structure was found fairly resemble to that of measured at
KUCA.
The detection efficiency of the gamma rays at KUCA was calculated with MCNP-5. That at LINAC
was experimentally determined. With the measured count rate and the efficiency, the gamma ray
emission rate was deduced and compared against that calculated based on JENDL/FPY&FPD-2011.
The ratio of the measured to the calculated value against each gamma ray by the two experiments
show fairly resemble trend. That indicates the both experiments are promising to give reference
data for validation of FP yield and decay data sets such as JENDL/FPY&FPD-2011.

Primary author: NAUCHI , yasushi (Central Research Institute of Electric Power Industry )Co-authors: Prof. HORI , Junichi (Institute for Integrated Radiation and Nuclear Science, Kyoto
University ); Prof. SANO , Tadafumi (Kindai University); Dr TAKAHASHI , Yoshiyuki (Institute forIntegrated Radiation and Nuclear Science, Kyoto University ); Dr KUSUMI , Koji (Central ResearchInstitute of Electric Power Industry ); Prof. UNESAKI , Hironobu (Institute for Integrated Radiation
and Nuclear Science, Kyoto University)

Presenter: NAUCHI , yasushi (Central Research Institute of Electric Power Industry )Session Classification: Poster

September 8, 2024

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Evaluation of Neutron Nuclear Da …

Contribution ID: 24

Type: Poster Presentation

Evaluation of Neutron Nuclear Data on Cobalt-59 for
JENDL-5
Thursday, 26 November 2020 16:56 (1h 54m)
Cobalt (Co) is one of the structural materials in nuclear and accelerator facilities. It is contained incarbon steel and concrete as well as SUS304. 59 Co is only stable isotope of Cobalt. The nuclear dataof 59 Co are considered to be important specifically for radioactivity estimation of 58,60 Co related
to decommissioning of the facilities. JENDL-4.0 includes the nuclear data of 59 Co, which based theevaluation in 1988. Major revision was carried out at the JENDL-3.3 evaluation in 2001, followedby the covariance estimation in 2002. After the release of JENDL-3.3, many measured data for
capture, (n,2n), (n,p), and (n,α) reactions have been published. Therefore, the reconsideration of
nuclear data is required for JENDL-5.
The evaluation of 59 Co was divided into three energy regions: resolved resonance region, unresolved resonance region, and fast neutron energy region. In the resolved resonance region, theresonance parameters and scattering radius were taken from de Saussure et al. (1992). In the unresolved resonance region, the data of thick sample of de Saussure et al. were adopted, supplemented
with the data of thin sample for large resonances. In the fast neutron energy region, the nuclear
reaction model code CCONE was used to calculate cross sections, angular distributions and double
differential cross sections. The evaluation was performed based on many types of measured data.
The obtained results are in good agreement with the measured data and will be shown in the poster
presentation.

Primary author: Dr NOBUYUKI, Iwamoto (JAEA)
Presenter: Dr NOBUYUKI, Iwamoto (JAEA)
Session Classification: Poster

September 8, 2024

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Nuclear data generation using ma …

Contribution ID: 25

Type: Oral Presentation

Nuclear data generation using machine learning
We have developed a method to generate nuclear data using Gaussian process regression (GPR)[1], which is one of the machine learning techniques. This method generates nuclear data bytreating measured data as the training data in machine learning. GPR is based on nonparametric
Bayesian inference, the generated nuclear data are expressed as a predictive distribution including
uncertainty information. In this presentation, the basics of the Gaussian process model, someexamples of the application to nuclear data generation, and other related topics will be presented.
[1] H. Iwamoto, “Generation of nuclear data using Gaussian process regression”, Journal of Nuclear
Science and Technology, 50:8, 932-938 (2020).

Primary author: IWAMOTO, Hiroki (Japan Atomic Energy Agency)
Presenter: IWAMOTO, Hiroki (Japan Atomic Energy Agency)
Session Classification: DeepLearning

September 8, 2024

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Contribution ID: 26

Theoretical analysis of deuteron- …
Type: Oral Presentation

Theoretical analysis of deuteron-induced reactions
and development of deuteron nuclear database
Since deuteron is a weakly bound system consisting of a proton and a neutron, it easily breaks
up and emits a neutron through interaction with a target nucleus. Utilizing this property, intensive neutron sources using deuteron accelerators have been proposed for not only science andengineering fields but also medical applications. For design studies of such facilities, accurate andcomprehensive nuclear data of deuteron-induced reactions are indispensable.
Toward evaluation of deuteron nuclear data, we have developed a code system dedicated for
deuteron-induced reactions, called DEURACS. In DEURACS, breakup processes of incident deuteronare taken into account. DEURACS was so far successfully applied to analyses of production of nucleons, composite particles up to A = 4, and residual nuclei. In this talk, we will present the resultsof these analyses and discuss how important it is to consider the breakup processes for accurate
prediction of deuteron-induced reactions.
Moreover, we have recently developed JENDL/DEU-2020, a deuteron nuclear database for Li-6,7,
Be-9, and C-12,13 up to 200 MeV. DEURACS was employed for evaluation of JENDL/DEU-2020.
Validation of JENDL/DEU-2020 was carried out by simulation with the Monte Carlo transport
codes. As a result, the simulation using JENDL/DEU-2020 reproduced the measured thick-target
neutron yields better than both simulations using the deuteron sub-library of TENDL and the reaction models implemented in the PHITS code. These validation results will also be presented.

Primary author: NAKAYAMA, Shinsuke (Japan Atomic Energy Agency)
Presenter: NAKAYAMA, Shinsuke (Japan Atomic Energy Agency)
Session Classification: NuclearPhysics2

September 8, 2024

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Experimental plan for displacemen …

Contribution ID: 27

Type: Poster Presentation

Experimental plan for displacement damage crosssections using 120-GeV protons at FNAL
Thursday, 26 November 2020 16:58 (1h 52m)
To predict the operating lifetime of materials in high-energy radiation environments at accelerator
facilities, Monte Carlo codes such as PHITS, MARS, and FLUKA are used to calculate the numberof displacements per atom (dpa) related to the number of Frenkel pairs. The Norgertt–Robinson–
Torrens (NRT) model has been widely used to predict the number of “initial”Frenkel pairs (NRTdpa). For more accurate estimation of the actual damage production, athermal-recombinationcorrected displacement damage (arc-dpa) was proposed, recently. For the validation of codes, itis necessary to measure displacement cross-sections of metals in relation to changes in electricalresistivity at cryogenic temperature (around 4 K) where the recombination of Frenkel pairs by
thermal motion is well suppressed. The comparison between the experimental data and calculated
results for proton irradiation with energies from 0.1 to 30 GeV indicates that the arc-dpa results
are good agreements with the experimental data and the NRT-dpa results are larger than the databy a factor of around three.
In this presentation, we introduce our experimental plan for displacement cross sections with
120-GeV protons at Fermilab Test Beam Facility (FTBF) in Fermi National Accelerator Laboratory(FNAL). Experiments will be performed at the M03 beam line high rate tracking area in FTBF for
the US fiscal year 2022 (October 2021 –September 2022). For the preparation of experiments, wedeveloped the sample assembly with four wire sample of Al, Cu, Nb and W with 250-µm diameterand 4-cm length. Annealing under vacuum condition (~10−4 Pa) was performed by heating an
Al sample at 840 K for 30 minutes, a Cu sample at 1289 K for 30 minutes, a Nb sample at 1923
K for 15 minutes, and a W sample at 2473 K for 15 minutes, respectively. The sample assembly
will be maintained at around 4 K by using a Gifford–McMahon (GM) cryocooler in a vacuum
chamber. Then, changes in the electrical resistivity of samples will be obtained under 120-GeV
proton irradiation. Recovery of the accumulated defects through isochronal annealing, whichis related to the defect concentration in the sample, will also be measured after the cryogenic
irradiation.
This work was supported by JSPS KAKENHI Grant Number JP19H02652.

Primary authors: Dr IWAMOTO, Yosuke (Nuclear Science and Engineering Center, Japan Atomic
Energy Agency (JAEA) ); Dr YOSHIDA , Makoto (J-PARC Center, High Energy Accelerator Research
Organization (KEK) / 高エネルギー加速器研究機構 J-PARC センター); Dr MEIGO , Shin-ichiro(J-PARC Center, Japan Atomic Energy Agency (JAEA) / 日本原子力研究開発機構 J-PARC センター); Dr NAKANO, Keita (J-PARC Center, Japan Atomic Energy Agency (JAEA) / J-PARC Center, Japan
Atomic Energy Agency (JAEA) / 日本原子力研究開発機構 J-PARC センター); Dr ABE, Shin-ichiro(Nuclear Science and Engineering Center, Japan Atomic Energy Agency (JAEA) / 日本原子力研究開発
機構原子力基礎工学研究センター); Prof. ISHIDA, Taku (J-PARC Center, High Energy Accelerator
Research Organization (KEK) / 高エネルギー加速器研究機構 J-PARC センター); Prof. YABUUCHI,
Atsushi (Institute for Integrated Radiation and Nuclear Science, Kyoto University / 京都大学複合原子力科学研究所); Prof. KINOMURA, Atsushi (Institute for Integrated Radiation and Nuclear Science,
Kyoto University / 京都大学複合原子力科学研究所); Prof. YOSHIIE, Toshimasa (Institute for Integrated Radiation and Nuclear Science, Kyoto University / 京都大学複合原子力科学研究所); Dr
YONEHARA, Katsuya (Fermi National Accelerator Laboratory (FNAL) / 米国フェルミ国立加速器研

September 8, 2024

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Experimental plan for displacemen …

究所); Dr SPINA, T. (Fermi National Accelerator Laboratory (FNAL) / 米国フェルミ国立加速器研究所); Dr AMMIGAN, K. (Fermi National Accelerator Laboratory (FNAL) / 米国フェルミ国立加速器研究所); Dr MOKHOV, N. (Fermi National Accelerator Laboratory (FNAL) / 米国フェルミ国立加速器研究所)

Presenter: Dr IWAMOTO, Yosuke (Nuclear Science and Engineering Center, Japan Atomic Energy
Agency (JAEA) )Session Classification: Poster

September 8, 2024

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Theoritical analysis of the fission p …

Contribution ID: 28

Type: Poster Presentation

Theoritical analysis of the fission process by 258Md
Thursday, 26 November 2020 16:51 (1h 59m)
It has been shown that fission has multiple modes, characterized by mass asymmetric fission andmass symmetric fission[1]. In neutron-rich heavy element region,it is argued that several fission
modes coexist, with a significant change of their yields in accordance with the number of neutronscontained in the fissionig nucleus. A typical example is found in the isotope dependence of fission
for fermium isotopes.
For Fm, the dominant mode transitions from the asymmetric splitting for 257 Fm to the symmetricfor 258 Fm[2].
This transitions was interpreted as due to the lowering of the fission barrier for symmetric fission,and the becoming energy advantage fission path of symmetric fission then asymmetric fission.
It’s important to know of the potential energy surface structure and nuclear’s deformation process
to understand fission mechanism in neutron-rich heavy element region[3].
258Md, which is the target of this work, is located near the boundary line where the transition
from mass asymmetric fission to mass symmetric fission is expected to occur, and in recent years,
the Japan Atomic Energy Agency has obtained the world’s first fission data. As a result of data
analysis, it shown that the mode of mass symmetric fission (superlong-mode) and the mode ofasymmetric fission (standard-mode) coexist.
In this work, we compared the calculation using the fluctuation dissipation model(Langevin calculation)[4] with the experimental data, and considered the characteristics of the fission mode shownby the experimental data.
Reference[1] U. Brosa, S. Grossmann, and A. Muller, Phys. Rep. 197,167 (1990).
[2] D.C. Hoffman et al., Phys. Rev. C, 21, 1980 (637)[3] Y. Miyamoto et al., Phys. Rev. C, 99, 051601(R) (2019).
[4] S. Tanaka, Y. Aritomo, Y. Miyamoto, K. Hirose, and K. Nishio PRC 100, 064605 (2019).

Primary author: ISHIZAKI, Shoma (Kindai University)
Co-authors:

OKUBAYASHI/奥林, Mizuki/瑞貴 (Kindai University/近畿大学); ARITOMO/有友,Yoshihiro/嘉浩 (Kindai University/近畿大学); NISHIO/西尾, Katsuhisa/勝久 (JAEA/日本原子力研究開発機構); HIROSE/廣瀬, Kentaro/健太郎 (JAEA/日本原子力研究開発機構)

Presenter: ISHIZAKI, Shoma (Kindai University)
Session Classification: Poster

September 8, 2024

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Unified description of the fission p …

Contribution ID: 29

Type: Oral Presentation

Unified description of the fission probability forhighly excited nuclei
Various spallation reaction models have been developed for the use of neutronic and shielding
design of high-energy accelerator facilities such as J-PARC and ADS. However, their complicatedtheory for the de-excitation process has made improving their prediction accuracy difficult. In
particular, it has been pointed out that the conventional models underestimate the yield of thespallation products produced from the fission reaction. This work has thus aimed to model the
probability was described using a simpler, systematic expression, and then confirmed to predictfission cross sections for various incident energies and target nuclei with improved accuracy [1].
In this presentation, we will present a description of our model and research results.
[1] H. Iwamoto, S. Meigo, “Unified description of the fission probability for highly excited nuclei”, Journal of Nuclear Science and Technology, 56:2, 160-171 (2020).

Primary authors:

IWAMOTO, Hiroki (Japan Atomic Energy Agency); MEIGO, Shin-ichiro (J--

PARC/JAEA)

Presenter: IWAMOTO, Hiroki (Japan Atomic Energy Agency)
Session Classification: NuclearPhysics1

September 8, 2024

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Contribution ID: 30

Nuclear spectroscopy at KISS / KIS …
Type: Oral Presentation

Nuclear spectroscopy at KISS / KISS での核分光実験
For nuclear spectroscopy in the vicinity of N=126 and U-238, we have developed KEK Isotope Separation System (KISS), which is an argon-gas-cell-based laser ion source combined with an on-line
isotope separator, installed in the RIKEN Nishina center [1]. The nuclei around N = 126 are produced by multi-nucleon transfer reactions (MNT) [2] of Xe-136 beam (10.75 MeV/A) impinging
upon a Pt-198 target. The KISS facility has a detector station for beta-gamma spectroscopy anda MRTOF system for precise mass measurement. By using these devices, we have successfully
performed beta-gamma spectroscopy of Os, Ta [3], and Re isotopes for the half-life measurements
and study of beta-decay schemes, and in-gas-cell laser ionization spectroscopy of Pt, Ir, and Os
isotopes for evaluating the magnetic moments and the trend of the charge-radii (deformation parameters).
In the presentation, we will report the present status of KISS, experimental results of nuclear spectroscopy in the heavy region, and future plan of KISS activities.
[1] Y. Hirayama et al., Nucl. Instrum. Methods B 353 (2015) 4.; B 463 (2020) 425.
[2] Y.X. Watanabe et al., Phys. Rev. Lett. 115 (2015) 172503.
[3] P. Walker et al., Phys. Rev. Lett 125 (2020) 192505.

Primary author: Dr HIRAYAMA/平山, Yoshikazu/賀一 (KEK/KEK)
Presenter: Dr HIRAYAMA/平山, Yoshikazu/賀一 (KEK/KEK)
Session Classification: NuclearPhysics1

September 8, 2024

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SCALE6.2 ORIGEN library produc …

Contribution ID: 31

Type: Poster Presentation

SCALE6.2 ORIGEN library produced fromJENDL/AD-2017
Thursday, 26 November 2020 16:55 (1h 53m)
Oak Ridge National Laboratory released the SCALE6.2 code [1] in 2016 (the latest version is SCALE6.2.4).
The ORIGEN code [1] in SCALE6.2 is completely different from the ORIGEN-S code [2] until
SCALE6.0 [2].
1) ORIGEN uses one group cross section data generated from a specified neutron spectrum and amultigroup activation library with the COUPLE code [1], not three group cross section data witha typical neutron spectrum.
2) The input format of ORIGEN is easy to use and understand.
3) It is expected that the calculation accuracy improves because ORIGEN uses one group crosssection data generated from neutron spectra in all calculation points.
4) The calculation time of ORIGEN including COUPLE is at most about twice of that of ORIGEN-S
even for 200 groups.
We expect that ORIGEN in SCALE6.2 will be mainly used for activation calculations in nuclear
facility decommissioning. Thus we produced a SCALE6.2 ORIGEN library from JENDL Activation
Cross Section File for Nuclear Decommissioning 2017 (JENDL/AD-2017) [3] with the AMPX-6 [4]in order to popularize JENDL/AD-2017 widely. The processing conditions are as follows.
- Temperature : 300 K- Group structure : 200 groups (the same as one of libraries attached in SCALE6.2)- Weight function : Maxwell+1/E+Fission spectrum + 1/E (above 10 MeV)
- Infinite dilution
We tested the SCALE6.2 ORIGEN library of JENDL/AD-2017 with the JPDR decommissioning data[5], which demonstrated the library had no problem.
References[1] ORNL, “SCALE: A Modular Code System for Performing Standardized Computer Analyses forLicensing Evaluation,”ORNL/TM-2005/39 Version 6, Oak Ridge National Laboratory (2009).
[2] (Ed.) W.A. Wieselquist, R.A. Lefebvre, M.A. Jessee, “SCALE Code System,”ORNL/TM-2005/39
Version 6.2.4, Oak Ridge National Laboratory (2020).
[3] https://wwwndc.jaea.go.jp/ftpnd/jendl/jendl-ad-2017.html[4] D. Wiarda, M.E. Dunn, N.M. Greene, M.L. Williams, C. Celik, L.M. Petrie, “AMPX-6: A Modular
Code System for Processing ENDF/B,”ORNL/TM-2016/43, Oak Ridge National Laboratory (2016).
[5] T. Sukegawa, N. Sasamoto, K. Fujiki, “ACCURACY VERIFICATION FOR CALCULATION OF
INVENTORY IN JPDR DUE TO NEUTRON ACTIVATION,”INDC(JPN)-164, International Atomic
Energy Agency (1993).

Primary author: Dr KONNO , Chikara (Japan Atomic Energy Agency )Co-authors: Ms KOCHIYAMA / 河内山, Mami / 真美 (Japan Atomic Energy Agency / 日本原子力
研究開発機構); Mr HAYASHI / 林, Hirokazu / 宏一 (Japan Atomic Energy Agency / 日本原子力研究
開発機構)

Presenter: Dr KONNO , Chikara (Japan Atomic Energy Agency )Session Classification: Poster

September 8, 2024

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Nondestructive Determination of …

Contribution ID: 32

Type: Poster Presentation

Nondestructive Determination of Water Content inConcrete Using Am-Be Neutron Source Experimental Verification Thursday, 26 November 2020 17:05 (1h 44m)
A new nondestructive measurement technique has been developed to evaluate the amount of water in concrete. A concrete wall is irradiated with fast neutrons to activate a gold foil set on theconcrete. By evaluating in advance the relation of the gold activity and water content by calculations, we can determine the water content in the concrete, the water content of which is notknown. In this study, to validate the present technique experiments were performed with concrete samples having different water contents, which were made from only cement and water. It
was confirmed from the experiments that water content could be estimated by the present nondestructive measurement technique though the system is still simple with cement and water. Now
we are examining the validity for concretes made from cement, water and sand.

Primary author: Mr MIYAJI , Yoshihiro (Graduate School of Engineering Osaka University Osaka)

Co-authors: Prof. MURATA , Isao (Graduate School of Engineering Osaka University / 大阪大学大学院工学研究科); Prof. SATO, Fuminobu (Graduate School of Engineering Osaka University / 大阪大学大学院工学研究科); Dr TAMAKI, Shingo (Graduate School of Engineering Osaka University / 大
阪大学大学院工学研究科); Ms KUSAKA , Sachie (Graduate School of Engineering Osaka University/ 大阪大学大学院工学研究科)

Presenter: Mr MIYAJI , Yoshihiro (Graduate School of Engineering Osaka University Osaka )Session Classification: Poster

September 8, 2024

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Development of Absolute Epi- …

Contribution ID: 33

Type: Poster Presentation

Development of Absolute Epi-thermal and Fast
Neutron Flux Intensity Detectors for BNCT
Thursday, 26 November 2020 17:04 (1h 46m)
BNCT is a promising cancer therapy which kills tumor cells while suppressing exposure dose tonormal tissues. Normally, the neutron field of BNCT, which is produced by a nuclear reactor oran accelerator-based neutron source, has an energy distribution spreading within thermal, epithermal and fast neutron regions. Because epi-thermal neutrons are generally used for BNCT, wemust measure the epi-thermal neutron flux intensity to evaluate the therapeutic effect and patient’s exposure dose. In addition, we also have to measure the fast neutron flux intensity to evaluate theexposure dose that may be harmful to the human body. However, it is quite difficult to measuresuch intensities directly and accurately because there is no suitable neutron spectrometer and noactivation material covering epi-thermal or fast neutrons separately. The objective of this work
is hence to develop new detectors to precisely measure the absolute integral flux intensities of
epi-thermal and fast neutrons.
An epi-thermal neutron detector we develop controls its sensitivity by using cadmium and polyethylene. A fast neutron detector controls by using cadmium, B4C and polyethylene. The shape of the
epi-thermal neutron detector is a cube, each side of which is 5.52 cm covered with a cadmium
sheet. However, the epi-thermal neutron detector is a little sensitive to fast neutrons. To clarify
the fast neutron contribution, we develop the fast neutron detector. To extract only fast neutrons,
the fast neutron detector consists of two sub-detectors, and the fast neutron intensity is estimatedby making difference of the two sub-detectors. The shape of one of them is a cube covered with
polyethylene with a side of 4.4 cm and that of the other is a cube covered with B4C with a side of
4.6 cm. Moderated neutrons are measured by activation reaction of 71Ga (n, γ) 72Ga of a GaN foil
positioned at the center of the detector. Design calculations were carried out by MCNP5.
After fabricating the detectors, in order to test the performance of the epi-thermal and fast neutron
detectors, verification experiments were conducted at KUR, Kyoto University and FNL facility, Tohoku University, respectively.
As the result, the epi-thermal neutron flux intensity could be measured with an error of 3.9 % bycorrecting the high energy neutron contribution with the calculated value. The fast neutron flux
intensity could be measured accurately, that is, the experimental and calculated values agree wellwithin the error range.

Primary author: Mr AOKI, Kazushi (Graduate School of Engineering, Osaka Univ.)
Co-authors:

Mr TAMAKI, Shingo (Graduate School of Engineering, Osaka Univ.); Mrs KUSAKA,
Sachie (Graduate School of Engineering, Osaka Univ.); Mr SATO, Fuminobu (Graduate School of Engineering, Osaka Univ.); Mr MURATA, Isao (Graduate School of Engineering, Osaka Univ.)

Presenter: Mr AOKI, Kazushi (Graduate School of Engineering, Osaka Univ.)
Session Classification: Poster

September 8, 2024

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Study on characteristics of neutron …

Contribution ID: 34

Type: Poster Presentation

Study on characteristics of neutron and γ-ray fields
at compact neutron source RANS-II facility bysimulation by the PHITS code
Thursday, 26 November 2020 17:10 (1h 41m)
RIKEN Accelerator driven compact Neutron Source-II (RANS-II) based on the 7 Li(p, n)7 Be reaction for neutron production with 2.49 MeV proton beam, has been under beam commissioning todemonstrate specific performance of the system. RIKEN has a prospect of realizing novel nondestructive neutron inspection for infrastructures with the use of RANS. As prominent characteristics, RANS-II has the maximum neutron energy of 0.8 MeV, which is lower than that of 5 MeV
at RANS based on the 9 Be(p, n)9 B reaction with 7 MeV proton injection, and gives extremely forward favored angular distribution with respect to the proton beam direction. Also, it should beemphasized that RANS-II system is installed in a relatively small space isolated by concrete shieldwith boron containment. Accordingly, there should be quite large differences in neutronic performances between RANS-II and RANS in terms of neutron spectrum and angular distributions. In
preparation of experiments at RANS-II, the simulation of radiation fields for neutron and γ-ray in
RANS-II experimental hall plays a critical important role for designing experimental set-up in low
background.
Then, we have performed simulations to characterize radiation fields of RANS-II The cross section
libraries implemented in PHITS are utilized in neutron and γ-ray transportations. Several important conditions of RANS-II modeling are as follows:
・The lithium (Li) target is made by depositing thin Li layer of about 100 µm on a 5 mm thick Cu
substrate cooled by water in the target station.
・The target station with about 90 cm side cubic shape, configures five layers; polyethylene, lead,borated polyethylene, lead and iron, to reduce the radiation leakage.
・There is a hole with a 15 × 15 cm2 cross section in the forward direction.
・The experimental hall has dimensions of 14 × 5.5 × 3.0 m3 surrounded by floor and wall madeof concrete (partly the borated concrete) and polyethylene ceiling.
As a result, the neutron and γ-ray distribution spreads widely in the experimental hall due to thewide openings in the target station. The scattered radiation could be the major contributor to
the background of experiments. On the other hand, primary neutrons produced at the target areshielded reasonably by the target station. To design effective collimators for high quality beam
extraction, we have calculated neutron beam profiles with parameters of collimator diameters andmaterials. It is shown that there is an optimized collimator configuration to extract suitable beam.

Primary author: Mr SUGIHARA , Kenta (RIKEN Nishina Center, Department of Applied Quantum
Physics and Nuclear Engineering, Kyushu University)
Co-authors: Dr IKEDA , Yujiro (RIKEN Center for Advanced Photonics, RIKEN, 2-1 Hirosawa, Wako,
Saitama 351-0198, Japan / 理化学研究所光量子工学研究センター中性子ビーム技術開発チーム,
J-PARC Center, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195,
Japan / 日本原子力研究開発機構 J-PARC センター); Dr KOBAYASHI , Tomohiro (RIKEN Center
for Advanced Photonics, RIKEN, 2-1 Hirosawa, Wako, Saitama 351-0198, Japan / 理化学研究所光量子工学研究センター中性子ビーム技術開発チーム); Dr FUJITA , Kunihiro (RIKEN Center for

September 8, 2024

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Study on characteristics of neutron …

Advanced Photonics, RIKEN, 2-1 Hirosawa, Wako, Saitama 351-0198, Japan / 理化学研究所光量子工学研究センター中性子ビーム技術開発チーム); Dr SHIGYO, Nobuhiro (Department of Applied
Quantum Physics and Nuclear Engineering, Kyushu University, Motooka, Nishi-ku, Fukuoka 819-0395,
Japan / 九州大学大学院工学研究院エネルギー量子工学部門); Dr TANAKA , Kanenobu (RIKEN
Nishina Center); Dr OTAKE , Yoshie (RIKEN Center for Advanced Photonics, RIKEN, 2-1 Hirosawa,
Wako, Saitama 351-0198, Japan / 理化学研究所光量子工学研究センター中性子ビーム技術開発チーム)

Presenter: Mr SUGIHARA , Kenta (RIKEN Nishina Center, Department of Applied Quantum Physics
and Nuclear Engineering, Kyushu University)

Session Classification: Poster

September 8, 2024

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Neutron Filtering System for Fast …

Contribution ID: 35

Type: Poster Presentation

Neutron Filtering System for Fast Neutron
Cross-Section Measurement at ANNRI
Thursday, 26 November 2020 17:00 (1h 49m)
The Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) experimental facility of the Japan Proton Accelerator Research Complex (J-PARC) provides the most intense neutron beam available in the world and was carefully
designed to precisely measure neutron-induced reactions using the time-of-flight (TOF) method.
Currently, the J-PARC accelerator is operated in double-bunch mode in which two 0.1 μs wide
protonbunches are shot into a spallation target with a time difference of 0.6 μs. Because of this, events
detected with a specific time-of-flight (TOF) have two different energies as they could have beenoriginated from each of the two different proton pulses. This is particularly important in the continuum
region (keV region) where the cross section can be expressed as a smooth averaged function. In
this region, it is impossible to separate the contribution from each proton pulse and, hence, thismode introduces serious ambiguities into the cross-section measurements.
A neutron filtering system has been designed in order to bypass the double-bunched structureof the neutron beam as part of the “Study on accuracy improvement of fast-neutron capture reaction data of long-lived MAs for development of nuclear transmutation systems”project. Filter
materials were introduced into the ANNRI beamline in order to produce quasi-monoenergetic
neutron filtered beams. The materials suitable to be used as filters present sharp minima in the
total cross-section due to the interference between the potential and s-wave resonance scattering. Neutrons having that energy can be transmitted through the filters and, therefore, produce
a quasi-monoenergetic beam. Filter assemblies consisting of Fe with a thickness of 20 cm, and Si
with thicknesses of 20 cm and 30 cm of Si were used separately to produce filtered neutron peaks
with energies of 24 keV (Fe) and of 54 and 144 keV (Si).
In this study, the characteristics and performance of the neutron filtering system at ANNRI using Fe
and Si determined from both measurements and simulations are presented. The incident neutron
flux was analyzed by means of transmission experiments using Li-glass detectors and captureexperiments using a boron sample which was measured with a NaI(Tl) spectrometer. Moreover,simulations using the PHITS code were performed in order to determine the energy distribution of
the integrated filtered peaks and assess the reliability of experimental results. Finally, preliminary
results of the capture cross section of 197 Au are presented using the NaI(Tl) spectrometer alongside
the neutron filtering system.

Primary author: ROVIRA LEVERONI, Gerard (JAEA)
Co-authors: IWAMOTO, Nobuyuki (JAEA); Dr ENDO, Shunsuke (JAEA); Dr NAKAMURA, Shoji(JAEA); Dr KIMURA, Atsushi (JAEA); Dr IWAMOTO, Osamu (JAEA); Prof. KATABUCHI, Tatsuya(Tokyo Institute of Technology); Dr TERADA, Kazushi (JAEA); Mr KODAMA, Yu (Tokyo Institute ofTechnology); Prof. SHIBAHARA, Yuji (Kyoto University); Prof. HORI, Jun-ichi (Kyoto University); Mr
NAKANO, Hideto (Tokyo Institute of Technology)
Presenter: ROVIRA LEVERONI, Gerard (JAEA)
Session Classification: Poster
September 8, 2024

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The origin of correlation between …

Contribution ID: 36

Type: Poster Presentation

The origin of correlation between mass and angle inquasi-fission
Thursday, 26 November 2020 16:50 (1h 58m)
Mass-angle distribution (MAD) measurement of heavy and superheavy element fragmentation reactions is one of the powerful tools for investigating the mechanism of fission and fusion process.
MAD shows a strong correlation between mass and angle when the quasi-fission event is dominant. It has characteristic that appears diagonal correlation as long as the quasi-fission event isdominant. This diagonal correlation could not be reproduced in previous our model before theintroduction of the parameters.
In this study, we systematically evaluate the uncertainty model parameters contained in our modeland clarify those model parameters to reproduce the diagonal correlation that appears in MAD. Using a dynamical model based on the fluctuation diffraction theorem that employs Langevin equations, we calculate the mass angle distribution and mass distribution of the four reaction systems
48Ti + 186W, 34S + 232Th, 48Ti + 208Pb, and 28S + 238U, which are dominated by quasi-fission.
We were able to clarify the effects of uncertain model parameters on the mass angle distribution
and mass distribution. In addition, we identified the values of model parameters that can reproduce the correlation between mass and angle. As a result, it found that the balance of tangential
friction and moment of inertia values is important for the correlation between mass and angle.

Primary author: AMANO, Shota (Kindai University)
Co-authors: ARITOMO, Yoshihiro (Kindai University); ISHIZAKI, Shoma (Kindai university); OKUBAYASHI,
Mizuki (Kindai University); OKUGAWA, Seiya (Kindai university)
Presenter: AMANO, Shota (Kindai University)
Session Classification: Poster

September 8, 2024

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Contribution ID: 37

Isotope production in spallation re …
Type: Oral Presentation

Isotope production in spallation reaction of 93Zr and93Nb induced by proton and deuteron / 93Zr 及び93Nb に対する陽子・重陽子入射核破砕反応からの同位体生成
Nuclear transmutation technology has been attracting attention as a method for treating high-level
radioactive waste. One of the candidates is the spallation reaction using high-energy particles, especially for the nuclides with relatively small neutron-capture cross sections such as long-lived
fission product (LLFP) 93 Zr. The accumulation of nuclear reaction data and the development of nuclear reaction models based on the data are indispensable for the accurate prediction of the amountof conversion of 93 Zr to stable nuclides and/or short-lived nuclides and residual long-lived nuclides
after the transmutation. Therefore, under the ImPACT program (Period: 2014 –2018), we have measured isotope-production cross sections in proton- and deuteron-induced spallation reactions on
LLFP 93 Zr and adjacent nuclide 93 Nb at RIKEN RIBF.
In the experiment, a 93 Zr beam at 50 MeV/nucleon and a 93 Nb beam at 113 MeV/nucleon
were produced by inflight-fission of 238 U. These beams were irradiated to secondary targets containing hydrogen and deuterium to induce spallation reactions, and the product yields were analyzed by ZeroDegree Spectrometer to determine the product cross sections. The results are compared with the nuclear reaction models.

Primary author: Dr NAKANO / 中野, Kieta / 敬太 (JAEA / JAEA)
Presenter: Dr NAKANO / 中野, Kieta / 敬太 (JAEA / JAEA)
Session Classification: NuclearPhysics2

September 8, 2024

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Experimental program of nuclear d …

Contribution ID: 38

Type: Poster Presentation

Experimental program of nuclear data for
accelerator-driven nuclear transmutation systemusing FFAG accelerator –First subprogram: spallation
neutron measurement
Thursday, 26 November 2020 17:00 (1h 50m)
For accurate prediction of neutronic characteristics for accelerator-driven system (ADS) and asource term of spallation neutrons for reactor physics experiments for the ADS at Kyoto University Critical Assembly (KUCA), we have launched an experimental program to measure nuclear
data on ADS using the Fixed Field Alternating Gradient (FFAG) accelerator at Kyoto University(Period: October 2019 –March 2023). This program is composed of two subprograms, focusing on
two nuclear reaction mechanisms, (1) spallation reactions and (2) high-energy fission, for incident
proton energies from several tens of MeV to 100 MeV. In the first subprogram, we will measure neutron energy spectra of double-differential cross-sections (DDXs) and thick-target neutron-yields(TTNYs) for several targets (i.e. Pb, Bi, Fe, etc.); in the second subprogram, fission fragment mass
number induced from heavy targets (i.e. Pb, Bi) will be measured. In this poster session, thepresent status of the first subprogram will be presented.

Primary author: Dr NAKANO , Keita (JAEA )Co-authors: Dr IWAMOTO , Hiroki (JAEA ); Dr MEIGO, Shin-ichiro (J-PARC Center, Japan Atomic
Energy Agency (JAEA), Japan); Dr NISHIO, Katsuhisa (JAEA); Dr ISHI, Yoshihiro (Kyoto University); Dr HIROSE , Kentaro (JAEA ); Dr IWAMOTO, Yosuke (JAEA ); Dr KURIYAMA, Yasutoshi(Kyoto University); Dr MAEKAWA, Fujio (JAEA ); Dr MAKII, Hiroyuki (JAEA); Dr OKABE, Kota
(JAEA ); Dr RICCARDO, Orlandi (JAEA / JAEA); Dr OIZUMI, Akito (JAEA); Dr SATO, Daiki (JAEA); Dr SUZAKI, Fumi (JAEA ); Dr TSUKADA, Kazuaki (JAEA ); Dr UESUGI, Tomonori (Kyoto University); Dr YASHIMA, Hiroshi (Kyoto University )Presenter: Dr NAKANO , Keita (JAEA )Session Classification: Poster

September 8, 2024

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Estimation of Flux and Residual Ra …

Contribution ID: 39

Type: Poster Presentation

Estimation of Flux and Residual Radioactivity for the
COMET Phase-I ExperimentThursday, 26 November 2020 17:11 (1h 39m)
COherent Muon to Electron Transition (COMET) is an experiment at J-PARC, which will searchfor coherent neutrino-less conversion of a muon to an electron in muonic atoms. The experimentwill be carried out in two steps: Phase-I and Phase-II. In the Phase-I experiment, 3.2 kW 8 GeV
proton beam irradiates a 70-cm long graphite target to produce negative pions. The negative pions are captured in the magnetic field and delivered to pion-decay and muon-transport sections.
The Phase-I experiment aims to detect the µ− e conversion events and measure the beam-related
background events for the Phase-II experiment. Now, it has been planned that the maintenanceby radiation workers would be conducted after the 150-day operation and the following 180-day
cooling. It is necessary to evaluate the residual radiation dose for the safety of the workers during
the maintenance. On this study, we calculated fluxes of neutron, photon, proton and other charged
particles in the beam room during the beam operation and the residual activity after the coolingtime by using Monte Carlo simulation code PHITS version 3.22 and DCHAIN-PHITS version 3.21.
The calculation results show that the design of components around the target and beam dump
needs to be improved to reduce the radioactivities after the cooling time.

Primary author: TOKUNAGA , Naoki (Kyushu University )Co-authors: SHIGYO, Nobuhiro (Kyushu University ); MAKIMURA, Shunsuke (Institute of Particle
and Nuclear Studies J-PARC Center Particle and Nuclear Physics Division Hadron Section Tokai campus/ 素粒子原子核研究所Ｊ－ＰＡＲＣセンター素粒子原子核ディビジョンハドロンセクション東海キャンパス); FUKAO, Yoshinori (Institute of Particle and Nuclear Studies J-PARC Center Particle
and Nuclear Physics Division Hadron Section Tokai campus / 素粒子原子核研究所Ｊ－ＰＡＲＣセン
ター素粒子原子核ディビジョンハドロンセクション東海キャンパス); KAMEI , Naoya (Instituteof Particle and Nuclear Studies J-PARC Center Particle and Nuclear Physics Division Hadron Section
Tokai campus / 素粒子原子核研究所Ｊ－ＰＡＲＣセンター素粒子原子核ディビジョンハドロン
セクション東海キャンパス); YOSHIDA , Makoto (J-PARC Center, High Energy Accelerator Research
Organization (KEK) / 高エネルギー加速器研究機構 J-PARC センター)

Presenter: TOKUNAGA , Naoki (Kyushu University )Session Classification: Poster

September 8, 2024

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Neutron emission during fission p …

Contribution ID: 40

Type: Poster Presentation

Neutron emission during fission process bydynamical model/
Thursday, 26 November 2020 16:55 (1h 57m)
Through joint research by the Japan Atomic Energy Agency (JAEA) and Kindai University, it has
become clear that the yield distribution of fission products (fission fragments) changes significantly
depending on the neutrons emitted from the compound nucleus. In the so-called multichancefission (MCF) concept, fission takes place after emitting several neutrons. This revives the shellstructure of a nucleus responsible for mass-asymmetric fission, thus change the fission-fragment
mass distribution. The effect of MCF is particularly important to treat high energy fissions, suchas ADS system which transmute long lived minor actinide nucleus by fission. Until now, thecalculation was performed by combining the fission model calculation (Langevin equation) and astatistical model using a code such as GEF [1,2]. However, this method does not introduce neutron
emission during the fission process.
In the present work, we have introduced the neutron evaporation during fission process in theLangevin model. For this, a change of potential energy in each neutron evaporation step is treated.
Fission fragment mass distribution of 236−238 U,238−240 Np, and 240−242 Pu were calculated in theinitial excitation energy range of E*=15-55MeV. The results show that the double-peak structure ismaintained even at the highest excitation energies, and successfully reproduced the experimental
data taken at the JAEA tandem facility [3-5].
Reference[1] K, H, Schmidt, B. Jurado, C. Amouroux, and C. Schmitt, Nucl.Data Sheets 131, 107(2016).
[2] S.Tanaka, Y.Aritomo et al., Phys. Rev. C 100, 064605(2019).
[3] R. Leguillon, K. Nishio et al., Phys. Lett. B 761, 125(2016).
[4] K. Hirose, K. Nishio et al., Phys. Rev. Lett. 119, 222501(2017).
[5] M. Vermeulen, K. Nishio et al., Phys. Rev. C, in print.

Primary author: YAMASAKI, Ryota (Kindai University)
Co-authors: TANAKA, Shoya (kindai University); ARITOMO, Yoshihiro (Kindai University); NISHIO,
Katuhisa (Advanced Science Research Center, Japan Atomic Energy Agency/日本原子力研究開発機
構先端基礎研究センター)
Presenter: YAMASAKI, Ryota (Kindai University)
Session Classification: Poster

September 8, 2024

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Contribution ID: 41

Production and Applications of Ra …
Type: Oral Presentation

Production and Applications of Radioisotopes at
RIKEN RI Beam Factory - Search for New Elements
through Diagnosis and Therapy of Cancer At RIKEN RI Beam Factory (RIBF), we have been developing production technologies of radioisotopes (RIs) and conducting RI application studies in the fields of physics, chemistry, biology, engineering, medicine, pharmaceutical and environmental sciences [1]. With light- to heavy-ion
beams from the AVF cyclotron, we produce more than 100 RIs from 7Be (atomic number Z = 4) to262Db (Z = 105). Recently, we often produce 211At in the 209Bi(α,2n)211At reaction for nuclear
medicine [2]. RIs of a large number of elements (multitracer) are simultaneously produced frommetallic targets such as natAg, 197Au, and 232Th irradiated with a 135-MeV nucl.–1 14N beamfrom RIKEN Ring Cyclotron [3]. The multitracer is useful to trace the behavior of many elements
simultaneously under an identical experimental condition. We installed a gas-jet transport system to the GAs-filled Recoil Ion Separator (GARIS) as a novel technique for superheavy element
chemistry [4]. Long-lived isotopes of 261Rfa,b, 262Db, 265Sga,b (Z = 106), and 266Bh (Z = 107)
useful for chemistry studies were produced in the heavy-ion induced reactions on a 248Cm target
and their decay properties were investigated in detail using a rotating wheel apparatus for α andspontaneous fission spectrometry [5–8]. Thanks to the pre-separation of Sg atoms with GARIS,
chemical synthesis and gas-chromatographic analysis of the first organometallic compound of
SHEs, Sg(CO)6 were conducted under a large international collaboration lead by the Univ. Mainz
and GSI groups [9].
[1] H. Haba et al., in Handbook of Nuclear Chemistry (2nd ed.), edited by A. Vértes, S. Nagy, Z.
Klencsár, R. G. Lovas, and F. Roesch, Vol. 3, Springer, (2010) 1761–1792.
[2] K. Fujiki et al., Chem. Sci. 10 (2019) 1936.
[3] H. Haba et al., Radiochim. Acta 93 (2005) 539.
[4] H. Haba et al., Chem. Lett. 38 (2009) 426.
[5] H. Haba et al., Phys. Rev. C 83 (2011) 034602.
[6] H. Haba et al., Phys. Rev. C 85 (2012) 024611.
[7] H. Haba et al., Phys. Rev. C 89 (2014) 024618.
[8] H. Haba et al., Phys. Rev. C 102 (2020) 024625.
[9] J. Even et al., Science 345 (2014) 1491.

Primary author: HABA, Hiromitsu (Nishina Center for Accelerator-Based Science, RIKEN)
Presenter: HABA, Hiromitsu (Nishina Center for Accelerator-Based Science, RIKEN)
Session Classification: NuclearMedicine

September 8, 2024

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Optimization of Activation Detect …

Contribution ID: 42

Type: Poster Presentation

Optimization of Activation Detector for Benchmark
Experiment of Large-angle Elastic Scattering
Reaction Cross Section by 14MeV Neutrons
Thursday, 26 November 2020 17:05 (1h 45m)
<span> The elastic scattering reaction cross section data commonly show smaller in backward
angles compared to those of forward angles when the energy of the incident neutron is high. However, in high neutron flux field, such as fusion reactor, the back-scattering reaction cross section is
becoming not negligible on the calculation result. Until now, there were differences reported between experimental and calculated values of neutron benchmark experiments using a DT neutron
source, which focused on back-scattering phenomena like a gap streaming experiment. For thisproblem, the author’s group developed a benchmark method for large-angle scattering cross sections and has carried out experiments with an iron sample for the last few years. The benchmark
method was successfully established based on the activation of Nb foil having a large activation
cross section at around 14 MeV.
<span>We are now planning to carry out benchmark experiments for other fusion structural
materials such as tungsten, lead, F82H and so on. And in the next step, we aim to consider benchmark experiments for lighter materials like Li, Be, B, C, N and O. In this case, the energy of neutrons
generated by backscattering is low. Especially for Li, being one of the most important materials in
fusion reactor, back-scattering neutrons cannot be captured by Nb foil due to the high thresholdenergy of <sup>93</sup>Nb(n,2n) reaction.
<span>In this study, to solve this problem, we examined possible nuclides having a low activation reaction threshold energy, so that it can react with low energy neutrons generated by thebackscattering of Li, and simultaneously having not too low threshold energy, so that the influenceof room-return neutrons can be eliminated properly. The optimization was achieved by calculating and comparing the number of counts for all the possible reactions of all the existing stable
nuclides considering appropriate irradiation and measuring times. The activation reaction crosssection data were taken from JENDL/AD-2017.
<span> As a result, we have found that <sup>181</sup>Ta(n,2n) was the most suitable reaction
giving us the largest number of counts in an acceptable short experimental time. Then experiments
were carried out to confirm whether <sup>181</sup>Ta(n,2n)<sup> cross section was consistent
with the nuclear data.

Primary author: RYOHEI, Takehara (Graduate school of Engineering, Osaka University)
Co-authors: Mr FUKUI, Kazuki (Graduate school of Engineering, Osaka University); Mr ARAKI,
Sota (Graduate school of Engineering, Osaka University); Dr TAMAKI, Shingo (Osaka University); Ms
KUSAKA , Sachie (osaka University); Prof. MURATA , Isao (Osaka University)
Presenter: RYOHEI, Takehara (Graduate school of Engineering, Osaka University)
Session Classification: Poster

September 8, 2024

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Production cross sections of 175Hf …

Contribution ID: 43

Type: Poster Presentation

Production cross sections of 175Hf in the natLu(p,xn)
and natLu(d,xn) reactions
Thursday, 26 November 2020 17:14 (1h 36m)
A long-lived isotope of Hf, 175Hf (T1/2 = 70 d), is useful for basic studies for rutherfordium(Rf, Z = 104). This isotope is producible in no-carrier-added form in the proton- and deuteroninduced reactions on natLu. However, excitation functions of these nuclear reactions have been
scarcely studied. In this work, we measured the excitation functions of the natLu(p,xn)175Hf andnatLu(d,xn)175Hf reactions up to 18-MeV proton and 24-MeV deuteron energies using a stack-foil
technique and a γ-ray spectrometry. We performed these experiments at RIKEN and Institute for
Nuclear Research (ATOMKI). The target stacks of Ta/Lu/Ti and Lu/Ti foils were irradiated for 2 hwith proton or deuteron beams of approximately 180‒240 nA. After the irradiation, each foil was
subjected to γ-ray spectrometry with Ge detectors. We noticed that the half-life of 173Hf is slightly
longer than that adopted in the current nuclear database. Therefore, we measured a precision halflife of 173Hf in a separate experiment. In this work, we could measure the excitation functionsof the natLu(p,xn)173,175Hf and natLu(d,x)173,175Hf, 173,174m,174g,176m,177m,177gLu reactions.
Thick-target yields of 175Hf were also deduced from the measured excitation functions. The yields
are 0.47 MBq/µA·h at 17.2-MeV proton and 2.0 MBq/µA·h at 24.0 MeV deuteron. We determined
the half-life of 173Hf to be 24.176 ± 0.012 h which is 0.58 ± 0.10 h longer than that in the database.

Primary author: Dr KOMORI, Yukiko (RIKEN Nishina Center)
Co-authors:

Dr HABA, Hiromitsu (RIKEN bNishina Center); Prof. AIKAWA, Masayuki (Grad.
School of Biomed. Sci. and Eng., Hokkaido Univ./北大院医理工); Dr SAITO, Moemi (Hokkaido
Univ.); Dr TAKACS, Sandor (ATOMKI); Dr DITROI, Ferenc (ATOMKI)

Presenter: Dr KOMORI, Yukiko (RIKEN Nishina Center)
Session Classification: Poster

September 8, 2024

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Contribution ID: 44

Introduction to Nuclear Reactor T …
Type: Oral Presentation

Introduction to Nuclear Reactor Theory
In this tutorial, I would like to briefly introduce the nuclear reactor theory.
Please keep in mind that the whole nuclear fission power plant is a too complicated system, thus
it is not easy to understand the multi-physics in the nuclear power plant. From the overall view of
the nuclear power plant, thermal energy via fission in the nuclear reactor core is utilized to finallygenerate electricity.
To appropriately design and control the nuclear reactor, we must understand and predict the behavior of neutrons and nuclear reactions. For this purpose, reactor physics has been developing
as an engineering science to systematize the relevant knowledge.
The effective neutron multiplication factor keff is an important core-characteristics parameter tojudge whether the nuclear reactor core is subcritical, critical, or supercritical. The keff value indicates the ratio of fission-induced neutron-production to neutron loss (absorption or leakage). In
the nuclear reactor, fission power is constantly maintained at the “critical state”of the fission chain
reaction.
To roughly predict the neutron multiplicity by the fission chain reaction, the point kinetics equation is simple and useful. If we think of a point kinetic equation without delayed neutrons, thisequation is similar to that of the Susceptible-Infected-Removed (SIR) model, which is used in theepidemiology. However, if there were no delayed neutrons in the fission event, we could nevercontrol the fission chain power reaction. In other words, the delayed neutron plays an importantrole to control the fission power in the actual nuclear reactor core by humans.
In order to predict the macroscopic and average behavior of neutrons, the Boltzmann neutrontransport equation is utilized as the master equation. Note that the rigorous Boltzmann equation
is too complicated to obtain the solution. At the dawn of the nuclear age, scientists and engineers
simplified the prediction model based on ingenious approximations such as diffusion and Fermiage theories. Recently, as computing performance and computational science improve, we canaccurately solve the numerical solution of the Boltzmann equations as much as possible. At theend of this tutorial, I will briefly explain unique numerical analysis methods, which have beendeveloped and utilized in the field of reactor physics. Through this tutorial, I would like to promote
understanding that the nuclear data such as microscopic nuclear cross section are essential input
data for the reactor physics analysis.

Primary author: ENDO, Tomohiro (Nagoya University)
Presenter: ENDO, Tomohiro (Nagoya University)
Session Classification: Tutorial

September 8, 2024

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Development of Evaluation Metho …

Contribution ID: 45

Type: Poster Presentation

Development of Evaluation Method of Uncertaintyof Radioactivity by Propagating Nuclear Data
Covariance for Clearance Verification in
Decommissioning of Nuclear Power Plants
Thursday, 26 November 2020 17:05 (1h 42m)
To optimize disposal of low-level radioactive waste originating from decommissioning of nuclear
facilities, required are 1) reliable assessment of radioactivity level by calculation and measurementand 2) a good estimate of the uncertainty of those results for the classification of radioactive waste.
In order to improve the reliability of the calculations in clearance verification, we established aprocedure of estimating the uncertainty of radioactivity concentration due to that of nuclear data.
For that, we estimated covariance of neutron cross sections of important nuclides that account forover 90 % in ΣD/C of concrete material and carbon steel by employing a propagation of uncertainties in the resonance parameters and statistical model parameters with nuclear data code group
T6. Here, D stands for radioactivity concentration, and C stands for clearance level. Then, we developed a new method to calculate uncertainty of radioactivity with Total Monte Carlo method byconnecting randomly perturbed endf-format files generated by the T6 calculation to a cross section
processing code NJOY and an activation calculation code ORIGEN2 using ORLIBJ40, a set of crosssection library based on JENDL-4.0. It was concluded that the uncertainty of the radioactivity due
to that of nuclear data for nuclides which dominate the ΣD/C is sufficiently small, and the main
factor of uncertainty of radioactivity comes from that of the neutron flux.

Primary author: AMITANI , Tatsuki (Tokyo Institute of Technology )Co-authors:

Dr INAKURA , Tsunenori (Tokyo Institute of Technology ); Dr YAMANO , Naoki(Tokyo Institute of Technology); Dr TANAKA , Ken-ichi (The Institute of Applied Energy ); Dr ISHIZUKA, Chikako (Tokyo Institute of Technology ); Mr WATANABE, Masato (Chubu Electric Power Co., Inc.
); Mr MIZUNO, Ryoji (Chuden CTI Co., Ltd. ); Prof. CHIBA , Satoshi (Tokyo Institute of Technology)

Presenter: AMITANI , Tatsuki (Tokyo Institute of Technology )Session Classification: Poster

September 8, 2024

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Development of a neutron detector …

Contribution ID: 47

Type: Poster Presentation

Development of a neutron detector for nuclear datameasurement using high-intensity neutron beamThursday, 26 November 2020 17:00 (1h 47m)
Highly precise neutron nuclear data is required in nuclear transmutation research of long-lived minor actinides (MA) in nuclear waste. In neutron capture cross section measurement, monitoring
the number of the incident neutrons is necessary. However, in measurement with J-PARC/ANNRI,
direct neutron monitoring system has not been employed. To make measurement with ANNRI
more robust, an additional neutron beam monitor is required. Conventional neutron detectors cannot be used as a beam monitor at ANNRI because of two reasons, high counting rate environmentand gamma-flash. The neutron flux at ANNRI is one of the highest in the world. Gamma-flash, anintense gamma-ray burst produced when the proton beam pulse bombards the spallation target,
can paralyze a detector generally used in nuclear data measurement. In general, a semiconductor
detector or an inorganic scintillator, which is adopted for a neutron detector, has relatively longer
response time and is unsuitable for beam monitoring at ANNRI.
Therefore, a combination of a thin plastic scintillator and a 6 LiF foil was selected as a detection
system, whose fast response enabled detecting neutrons at a high counting rate. Low gamma raysensitivity of a thin plastic scintillator allows measuring fast TOF region without count loss ordetector paralysis. The geometry of the 6 LiF foil, the plastic scintillator, and photomultiplier tube
(PMT) was designed. The optimal thickness of the 6 LiF foil was determined with simulation codes,
SRIM and PHITS. A 6 LiF foil was made by vacuum deposition method. A test detector system wasbuilt to study the feasibility of the method.
The detector system was tested under the high neutron irradiation condition at J-PARC /ANNRI. A
neutron TOF spectrum was successfully measured without significant count loss or detector paralysis. A neutron energy spectrum was driven from difference of TOF spectrum with and without
6
LiF. The neutron spectrum was compared with a past neutron spectrum and good agreement was
obtained. Statistic error was 0.68 % at 6.0 meV even though measurement times in this study waspretty short (~11 min).

Primary author: NAKANO, Hideto (Tokyo Institute of Technology )Co-authors:

Prof. KATABUCHI, Tatsuya (Tokyo Institute of Technology); ROVIRA LEVERONI,
Gerard (JAEA); KODAMA, Yu (Tokyo Tech); TERADA, Kazushi (Kyoto University); Dr KIMURA,
Atsushi (JAEA); Dr NAKAMURA, Shoji (JAEA); Dr ENDO, Shunsuke (JAEA)

Presenter: NAKANO, Hideto (Tokyo Institute of Technology )Session Classification: Poster

September 8, 2024

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Study of the fission path energy of …

Contribution ID: 48

Type: Poster Presentation

Study of the fission path energy of U-236 using
microscopic mean-field model
Thursday, 26 November 2020 16:50 (2 hours)
Microscopic mean-field model is one of strong methods for providing and improving fission-related
nuclear data.
It needs appropriate effective interaction, but there is no effective interaction designed for fissionpath.
In order to tackle this problem, we calculate the U-236 potential energy surface with respect to theelongation of a nucleus and the mass asymmetry with existing Skyrme effective interactions.
We report the energy characteristics of potential energy surface and important parts for correcting
the fission barrier.

Primary author: FUJIO , Kazuki (Tokyo Institute of Technology)
Co-authors: Prof. CHIBA , Satoshi (Tokyo Institute of Technology); Dr EBATA , Shuichiro (Saitama
university); Dr INAKURA, Tsunenori (Tokyo Institute of Technology)
Presenter: FUJIO , Kazuki (Tokyo Institute of Technology)
Session Classification: Poster

September 8, 2024

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Contribution ID: 49

Roles and Current Status on React …
Type: Oral Presentation

Roles and Current Status on Reactor Physics
Experiment in Research Reactors
Nuclear reactors are mainly categorized as two parts: a commercial power reactor; a test andresearch reactor for generating electric power and conducting research of radiation utilization, respectively. Of two reactors, main roles of the test and research reactor are to conduct the researchand development of nuclear engineering and radiation detection fields with the use of radiation,
including neutron, alpha-ray, beta-ray, gamma-ray, and so on, and to contribute to the educationof young generation. Many research reactors are importantly equipped with experimental facilities to research objectives, including irradiation holes, neutron beams and spectrum shift changers,
although the commercial reactors insufficiently meet the items. An index of classification of research reactors is to provide a wide range of neutron spectrum and thermal reactor power, with the
combined use of nuclear fuel, moderators, reflectors and coolant materials by varying the kinds,
the geometries, the configurations and the utilization purposes.
Another part of the presentation is to contain the feasibility study on the accelerator-driven system(ADS) conducted for nuclear transmutation analyses with the combined use of the solid-moderated
and solid-reflected core and the fixed-field alternating gradient (FFAG) accelerator, in the Institutefor Integrated Radiation and Nuclear Science, Kyoto University. Through the experimental analyses by MCNP with major nuclear data libraries (JENDL-4.0. ENDF/B-VII.1, JENDL/HE-2007 andJENDL/D-99), static and kinetic parameters of reactor physics are interestingly revealed for nuclear transmutation of minor actinides (Np-237 and Am-241) and uncertainty quantification of acoolant material (lead and bismuth), with respect to ADS. Additionally, experimental education
programs for domestic and overseas students conducted at the Kyoto University Critical Assembly
are introduced in the presentation.

Primary author: Prof. PYEON, Cheol Ho (Kyoto University)
Presenter: Prof. PYEON, Cheol Ho (Kyoto University)
Session Classification: Tutorial

September 8, 2024

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The fission fragments of neutron- …

Contribution ID: 50

Type: Poster Presentation

The fission fragments of neutron-rich nuclei by theLangevin method toward application to r-process
calculations
Thursday, 26 November 2020 16:55 (1h 56m)
Nuclear fission plays an essential role in nucleosynthesis by the rapid-neutron-capture process(r-process), which is a cosmic origin of heavy elements beyond iron. For very neutron-rich environments in neutron star mergers, the strong r-process can be achieved, and the nucleosynthesis
path goes into the trans-uranium region. In such conditions, fission is important to shape the rprocess abundances due to fission recycling, which determined the termination of the r-process
in the heavy nuclei region. Besides abundance prediction, fission is also a key role as the main
heating source of kilonovae, which are electromagnetic transients of neutron star mergers. A signof fission heating may have been observed in the light curve of the kilonova associated with thegravitational wave, GW170817. The precise understanding of fission becomes much crucial in theera of gravitational astronomy.
In this study, we calculate the fission-fragment mass distributions of very neutron-rich nuclei,
which are important for the nucleosynthesis calculations of the r-process, but experimental nuclear data is not available. We adopt the Langevin method [1], widely adopted in the study of
low-energy fission in the past few years. We found that the calculated mass distributions for uranium, of which Z distribution is calculated with UCD (unchanged charge distribution assumption),well reproduce experimental data in JENDL (232 U to 238 U) [2]. We also found that the fission distribution changes from the two peak feature (asymmetric fission) to the one-peak (symmetric fission)as the neutron number increases. The confirmation by future experiments would be desirable forthese theoretical predictions to develop a complete theory set of fission distributions applicable tor-process nucleosynthesis simulations.
[1] S. Tanaka, Y. Aritomo, Y. Miyamoto, K. Hirose, and K. Nishio PRC 100, 064605 (2019).
[2] K. Shibata, O. Iwamoto et al.: “JENDL-4.0: A New Library for Nuclear Science and Engineering,”
J. Nucl. Sci. Technol. 48(1), 1-30 (2011).

Primary author: Mr OKUBAYASH, Mizuki (Kindai University)
Co-authors: Prof. ARITOMO, Yoshihiro (Kindai University); Dr TANAKA, Shoya (Kindai University,
Japan Atomic Energy Agency); Mr ISHIZAKI, Shoma (Kindai university); Mr AMANO, Shota (Kindai
University); Dr NISHIMURA, Nobuya (Riken)
Presenter: Mr OKUBAYASH, Mizuki (Kindai University)
Session Classification: Poster

September 8, 2024

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Comparison of photon spectra emi …

Contribution ID: 51

Type: Poster Presentation

Comparison of photon spectra emitted from fueldebris using different decay data libraries
Thursday, 26 November 2020 16:55 (1h 51m)
We require reliable nuclear data that can appropriately evaluate the radiation characteristics offuel debris for the purpose such as development of new sensors, non-destructive assay technologies and optimization of radiation shielding. In the past, even if different results were obtained
depending on calculation codes, it was difficult to clarify what caused the differences. To overcome it, we have developed a new reliable code to calculate radiation decay and radioactive source
spectra that can accurately treats with large amounts of nuclides and all decay modes in the decay
data file.
As the first step, we compared the photon spectra of fuel debris by using the recent decay data files:
JENDL/DDF-2015, decay sub-libraries of ENDF/B-VIII.0 and JEFF-3.3. As shown in Fig.1, the resultof JENDL/DDF-2015 is smaller than those of ENDF/B-VIII.0 and JEFF-3.3. This is mainly caused by
the following reasons:(1) X-ray data of 137mBa (T1/2 =2.6 min.) in JENDL/DDF-2015 is missing. The 137mBa is generated from β- decay from large amount of 137Cs (T1/2 = 30 years) and it will remain for a long timeby radiation equilibrium.
(2) Gamma ray data of 241Am in 60 keV is missing in JENDL/DDF-2015.
(3) Gamma ray data of 106Rh (T1/2 = 2 hour) is missing in JENDL/DDF-2015 in the energy range
from 3.0 to 3.4 MeV. The 106Rh is in the radiation equilibrium with 106Ru (T1/2=1.0 year)
In the presentation, we will report requests for the modifications on the decay schemes and branching ratios of decay modes for the next JENDL decay data file.

Primary authors: MATSUMURA, Taichi (Japan Atomic Energy Agency ); FUJITA, Manabu (Japan
Atomic Energy Agency); OKUMURA, Keisuke (Japan Atomic Energy Agency)
Presenter: MATSUMURA, Taichi (Japan Atomic Energy Agency )Session Classification: Poster

September 8, 2024

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Nuclide production cross sections …

Contribution ID: 52

Type: Poster Presentation

Nuclide production cross sections of natLu target
irradiated with 0.4-, 1.3-, 2.2-, 3.0-GeV protons
Thursday, 26 November 2020 17:10 (1h 40m)
Reliable assessment of radioactivity in target and structural materials for high-energy accelerator
facilities such as accelerator-driven systems and spallation neutron sources requires detailed information on nuclide production cross sections by spallation reactions. To obtain the systematiccross section data for nuclide productions by spallation reactions, we have conducted irradiation
experiments at Japan Proton Accelerator Research Complex (J-PARC). So far, we have measured
nuclide production cross sections for light to medium-heavy target elements (Z≤47) with protonenergies ranging from 0.4 to 3.0 GeV. To investigate heavier target elements, we conducted anexperiment for target elements with atomic number around Z=70, including nat Lu (Z=71) target.
Four sets of Ho (90mg/cm2 ), Lu (100mg/cm2 ), and Re (210mg/cm2 ) foils were packed in aluminum containers together with 0.1-mm-thick aluminum catchers to avoid recoil contamination.
Each set of targets was irradiated with 0.4-, 1.3-, 2.2-, and 3.0-GeV protons accelerated by 3-GeV
Rapid Cycling Synchrotron (RCS). The beam current was monitored by a current transformer installed in front of the irradiation position. After the irradiation, gamma-rays emitted from thesamples were detected by two high-purity Germanium detectors (relative efficiency 20%, CanberraCo., Ltd.).
The measured cross sections were compared with theoretical predictions by Particle and Heavy Ion
Transport code System (PHITS) [1], and INCL++/ABLA[2,3]. The figure shows experimental andcalculated nat Lu(p, X)nat Be reaction cross sections. INCL/GEM model implemented in PHITS
underestimated the experimental cross sections by a factor of about 2.
In the presentation, we will report our experimental results for the natLu target, and more detailed
discussion on reaction mechanics will be given.
References[1] T. Sato, et al., J. Nucl. Sci. Technol. 55, pp.684 (2018).
[2] D. Mancusi et al., Phys. Rev. C 91:034602 (2015).
[3] A. Kelic et al., Proceedings of Joint ICTP-IAEA Advanced Workshop on Model Codes for Spallation Reactions, ICTP Trieste, Italy pp.181 (2008).

Primary authors: Mr TAKESHITA, Hayato (Kyushu University); MEIGO, Shin-ichiro (J-PARC/JAEA); Dr
MATSUDA, Hiroki (J-PARC Center, JAEA); IWAMOTO, Hiroki (Japan Atomic Energy Agency); NAKANO,
Keita (JAEA); Prof. WATANABE, Yukinobu (Kyushu University); Dr MAEKAWA, Fujio (JAEA )Presenter: Mr TAKESHITA, Hayato (Kyushu University)
Session Classification: Poster

September 8, 2024

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A New Method to Reduce Systema …

Contribution ID: 53

Type: Poster Presentation

A New Method to Reduce Systematic Uncertainties
of Capture Cross Section Measurement Using a
Sample Rotation System
Thursday, 26 November 2020 17:02 (1h 48m)
Precise nuclear data for neutron-induced reactions are necessary for the design of nuclear transmutation system. Nevertheless, current uncertainties of nuclear data for minor actinide (MA) does notachieve requirements for the design of transmutation facilities. Measurements of the neutron capture cross section are ongoing at the Accurate Neutron Nucleus Reaction measurement Instrument(ANNRI) in the Materials and Life science experiment Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC). The determination of an incident neutron flux for measurementsof neutron capture cross section is one of the main causes that affect the final uncertainty of thecross section results.
In the present work, we suggest a new method to reduce systematic uncertainties of capture crosssection measurements. The method employs change of the self-shielding effect with sample rotation angle. In the new technique, a sample area density of a boron sample which is used formeasurements of the incident neutron spectrum. In capture cross section measurements in ANNRI, a boron sample is placed to determine the incident neutron spectrum by counting 478 keV
γ-ray from the 10 B(n,αγ)7 Li reaction. The uncertainty of the boron sample area density that is
usually calculated from the mass and the area introduces the uncertainty of the incident neutron
spectrum. In this method, the boron sample is tilted with respect to the neutron beam direction,
thereby changing the effective area. The neutron self-shielding effect increases with the effective
area density. This results in change of the shapes of time-of-flight(TOF) spectrum of 478 keV γray counts form the 10 B(n,αγ)7 Li reaction with the tilted angle. Comparing the difference of the
TOF spectra at different angles and assuming the 1/v energy dependence of cross section of the10
B(n,αγ)7 Li reaction, the area density of the boron sample can be determined without using thesample mass and area.
Theoretical and experimental studies on the new method are ongoing. Calculation using Monte
Carlo simulation code PHITS were carried out to study the feasibility of the present method. Test
experiments using a sample rotation system at ANNRI were also performed. Preliminary results
will be given in this poster session.

Primary author: Mr KODAMA, Yu (Tokyo Institute of Technology)
Co-authors:

Prof. KATABUCHI, Tatsuya (Tokyo Institute of Technology); Dr ROVIRA, Gerard(Japan Atomic Energy Agency/日本原子力研究開発機構); Mr NAKANO, Hideto (Tokyo Institute ofTechnology); Dr TERADA, Kazushi (Kyoto University); Dr KIMURA, Atsushi (Japan Atomic Energy
Agency); Dr NAKAMURA, Shoji (Japan Atomic Energy Agency); Mr ENDO, Shunsuke (Japan Atomic
Energy Agency)

Presenter: Mr KODAMA, Yu (Tokyo Institute of Technology)
Session Classification: Poster

September 8, 2024

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Measurement of neutron total cros …

Contribution ID: 54

Type: Poster Presentation

Measurement of neutron total cross sections of
Sn-Pb alloys in solid and liquid statesThursday, 26 November 2020 17:12 (1h 38m)
Recently, a small modular reactor (SMR) with inherent and passive safety has been receiving attention all over the world. In Japan, a very small modular reactor, namely, MoveluX<sup>TM</sup>(MobileVery-Small reactor for Local Utility in X-mark) has been developing by Toshiba Energy Systems ＆Solutions Corporation. MoveluX<sup>TM</sup> is a thermal reactor that uses a calcium hydride
as a neutron moderator. The use of a Sn-Pb alloy as an in-core heat transport medium is being
considered. The Sn-Pb alloy is in a solid state when the reactor is started, and becomes liquid since
the core temperature reaches 660℃ during operation. Therefore, the total cross section data of the
Sn-Pb alloy is important for evaluating the effect of the change in the total cross section dependingon the state of Sn-Pb alloy on the reactor characteristics. However, there are no reports on experimental data for total cross section of Sn-Pb alloys in both solid and liquid states in spite of the factthat it is important data for nuclear engineering. In the present study, the neutron total cross section was obtained from neutron transmission measurements by the time-of-flight (TOF) method
using the Kyoto University Institute for Institute for Integrated Radiation and Nuclear Science –Linear Accelerator (KURNS-LINAC). The sample temperature was changed from room temperature (solid) up to 300℃ (liquid). The total cross sections of solid and liquid states were comparedand the change in Bragg edge due to the difference of crystal structure was observed in the energy
region below 0.01 eV. Comparing the total cross sections of the solid and the solid resolidificatedafter melting, it was confirmed that some Bragg edges, which are thought to be due to the crystal
structure of Pb, disappeared by the resolidification. At the poster presentation, the detail of thetotal cross section measurement experiment and the results obtained so far will be discussed.

Primary author: Mr UEMURA , Takuya (Kyoto University)
Co-authors: Prof. HORI, Jun-ichi (Kyoto University); Dr TERADA , Kazushi (Kyoto University); Prof. SANO, Tadafumi (Kindai University ); Dr NISHIYAMA, Jun (Tokyo Institute of Technology); Dr KIMURA , Rei (Toshiba Energy Systems ＆ Solutions Corporation / 東芝エネルギーシステムズ); Prof. NAKAJIMA, Ken (Kyoto University )Presenter: Mr UEMURA , Takuya (Kyoto University)
Session Classification: Poster

September 8, 2024

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Comparison of double-differential …

Contribution ID: 55

Type: Poster Presentation

Comparison of double-differential cross sections
between JENDL/PD-2016.1 and experimental data forphoto-neutron production of medium-heavy nuclei
at 16.6 MeV
Thursday, 26 November 2020 17:05 (1h 43m)
The double differential cross-section (DDX) of the photoneutron is an important quantity for radiation shielding and shielding calculation of the electron accelerator design. Shielding calculation
is usually carried out by Monte Carlo simulation codes, which use the nuclear data library in thecalculation. We measured the DDXs of the (γ, xn) reaction using 16.6 MeV polarized photon onnat.
Pb, 197 Au, nat. Sn, nat. Cu, nat. Fe, and nat. Ti targets [1], and showed the neutron spectra including the evaporation and direct components. In this presentation, we compared the DDXs fromthe photonuclear data JENDL/PD-2016.1 and the experiment to check their consistency. The DDXs
were extracted from the JENDL/PD-2016.1 library by our python-based software. The abundancesof each target’s isotopes were considered in calculating the DDXs from the JENDL/PD-2016.1 library. This comparison showed the differences in the photoneutron’s energy distributions, andthe differences were mostly in the direct component. The evaporation components were found inboth JENDL/PD-2016.1 and the experimental data; however, they were not totally consistent. This
result can be the first comparison of the DDXs from JENDL/PD-2016.1 and the experiment. The
quantitative comparison and discussion will be presented at the symposium.
Keywords: differential double cross-section photoneutron, 16.6 MeV polarized photon, JENDL/PS2016.1.
[1] T.K. Tuyet et al., “Double differential cross section of the (γ, xn) reaction on medium-heavy
nuclei for 16.6 MeV polarized photons. 2020 Fall meeting of AESJ, Sep. 16th –18th.

Primary author: Ms TRAN, Kim Tuyet (SOKENDAI/KEK)Dr SAKAKI, Yasuhito (KEK); Prof. SANAMI, Toshiya (KEK/SOKENDAI); Prof. YAMAZAKI, Hirohito (KEK/SOKENDAI); Dr ITOGA , Toshiro (JASRI); Dr TAKEUCHI , Akihiro (QST); Prof.
SHUJI, Miyamoto (University of Hyogo); Prof. ASANO, Yoshihiro (University of Hyogo)

Co-authors:

Presenter: Ms TRAN, Kim Tuyet (SOKENDAI/KEK)
Session Classification: Poster

September 8, 2024

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Contribution ID: 56

Nuclear data study for Accelerator …
Type: Oral Presentation

Nuclear data study for Accelerator Driven System at
J-PARCIn order to decrease the toxic waste produced at the nuclear reactor, a study of the Accelerator
Driven System (ADS) is going around the world. Since the neutron production target at ADS
is designed to be irradiated by protons in the kinetic energy of several GeV, a study with thehigh-energy particles in the kinetic energy region around GeV is essential for the research anddevelopment of ADS. However, many accelerator facilities using several GeV-protons, which werebuilt 1970’s, are going to shut down due to their lifetime. Eventually, the facilities to be able to use
protons with several GeV are scarce in the world. In Japan, J-PARC can only apply for the sake of
ADS using the hadron including proton. At the 3-GeV proton synchrotron (RCS) facility and thebeam transport line, some studies are going at J-PARC aimed for nuclear data of ADS.
In this session, some results of the experiment related to nuclear data for ADS are introduced, suchas nuclide production cross-section induced by proton and displacement cross-section.

Primary author: MEIGO, Shin-ichiro (J-PARC/JAEA)
Presenter: MEIGO, Shin-ichiro (J-PARC/JAEA)
Session Classification: Facility

September 8, 2024

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Contribution ID: 57

Development of Radioisotopes Pro …
Type: Oral Presentation

Development of Radioisotopes Production Methodby Accelerator-based Neutron: Activity at Kyushu
University 2020
Radioisotopes (RIs) production using deuteron accelerator-based neutrons has been studying at
Kyushu University. We especially focus on neutrons generated via the C or Be(d, n) reactions
in a target whose thickness is thicker than the deuteron range. These reactions are selected because, (1) high intense neutrons having high kinetic energy are possible to be generated by theelastic and non-elastic break-up reaction of deuterons, and (2) neutron energy spectrum has maximum around a half incident deuteron energy, i.e. the spectrum shape can be adjusted by varying
deuteron energy. The study has been conducted by the two approaches: proposal of new production routes or new RIs with the accelerator-based neutron method and systematic measurementsof double-differential thick-target neutron yields (DDTTNYs) up to 40 MeV. Present paper showssome example of past works (high purity 64Cu production starting from
Zn which includes
multiple stable isotopes), present status (chemistry, systematic DDTTNY measurement results),
and future prospects (covariance application for neutron spectrum unfolding to take nuclear data
uncertainty into account) of our project.

Primary author: KIN, Tadahiro (Kyushu Unversity)
Presenter: KIN, Tadahiro (Kyushu Unversity)
Session Classification: NuclearMedicine

September 8, 2024

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Contribution ID: 58

Measurements of production cross …
Type: Oral Presentation

Measurements of production cross sections of
medical radioisotopes via charged-particle induced
reactions / 荷電粒子入射反応による医療用 RI 生成断
面積測定実験
Radioisotopes can be used for a variety of applications, e.g., radiotherapy and diagnostics in nuclear medicine. There are basically several reactions to produce each radioisotope. Investigationsof such reactions are necessary to find better reactions with less byproducts and with higher costeffectiveness. Production cross sections of the radioisotopes are thus important nuclear data. However, there still exist a lack of data and data with large errors. It is necessary to obtain more accurate
and reliable data for the application. Recent technical development of accelerators and detectors
enables us to reach such data.
We focus on charged-particle-induced reactions among the possible reactions for the production.
The charged-particle-induced reactions have an advantage to be able to produce radioisotopes withatomic numbers different from those of targets. We can expect to chemically separate the reaction
products from the targets and to obtain the radioisotopes with high specific activity.
Experiments to measure the production cross sections are performed at RIKEN, Japan and ATOMKI,
Hungary. The well-developed methods, stacked foil activation technique and high-resolution
gamma-ray spectrometry, are adopted. The targets consisted of thin foils were irradiated withthe charged-particles beams. Gamma-rays emitted from the irradiated foils without chemical separation were measured by HPGe detectors. Nuclear data required for deduction of cross sections
were obtained from online databases. The cross sections of the monitor reactions were comparedwith the IAEA recommended values to assess the beam parameters and target thicknesses.
The production cross sections can be derived and compared with previous studies and theoreticalmodel calculation in the TENDL-2019 library. Thick target yields of the products for practical use
can also be derived from the measured cross sections. The results are expected to contribute nuclear medicine.
We report our research activity on the experiments for the production cross sections of several
medical radioisotopes.

Primary author: AIKAWA / 合川, Masayuki / 正幸 (Hokkaido University / 北海道大学)
Presenter: AIKAWA / 合川, Masayuki / 正幸 (Hokkaido University / 北海道大学)
Session Classification: NuclearMedicine

September 8, 2024

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Research for nuclear transmutatio …

Contribution ID: 60

Type: Poster Presentation

Research for nuclear transmutation ofhigh-radiotoxic nuclide 90Sr via proton- anddeuteron-induced reactions
Thursday, 26 November 2020 17:13 (1h 37m)
Processing of spent fuel from nuclear power plants is a worldwide problem. The high-level radioactive waste is the product after the reprocessing of spent fuel, which includes minor actinides andfission products of radioactive waste. Especially, 90 Sr (T1/2 = 28.8 years) is the highest radiotoxic
nuclide in the fission products. It is highly desired to develop nuclear transmutation technology
using accelerator facilities to reduce these harmful nuclides. The simplest way can be to irradiate aneutron beam on the radioactive waste. However, it is not well known that 90 Sr is transmuted into
how much and which nuclide in this reaction. Therefore, it is essential to study, in advance, thereaction-cross-sections to each nuclide from 90 Sr. From this point of view, the inverse kinematics,
i.e. including the 90 Sr beam incident on light-particle targets, is an effective method the reaction
products can be identified at the forward directions.
To realize this purpose, we have planned the proton- and deuteron-induced reaction-cross-section
measurements in inverse kinematics and performed the experiment using the BigRIPS separator[1] and the ZeroDegree spectrometer [1] at the RIKEN Radioactive Isotope Beam Factory. The
radioactive 90 Sr beam with 104 MeV/u, produced and separated in the BigRIPS, incident on theC, CH2 , and CD2 targets. The reaction products in the forward directions were transferred to the
ZeroDegree and identified using the detectors at the focal plane. The reaction-cross-sections wereobtained from the measured yields of each reaction channel. At this time, the contributions fromcarbon and beam-line materials were subtracted as a background. The obtained reaction-crosssections were compared to the PHITS calculation [2] and the data with different energy of 185
MeV/u [3].
[1] T. Kubo, et al., Progr. Theor. Exp. Phys. 2012, 03C003 (2012).
[2] T. Sato, et al., J. Nucl. Sci. Technol. 50, 913 (2013).
[3] H. Wang, et al., Phys. Lett. B 754, 104 (2016).

Primary author: Mr MATSUMURA , Riku (Saitama University )Presenter: Mr MATSUMURA , Riku (Saitama University )Session Classification: Poster

September 8, 2024

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Theoretical evaluation of non- …

Contribution ID: 61

Type: Poster Presentation

Theoretical evaluation of non-resonant backgroundstrength in binary breakup reaction
Thursday, 26 November 2020 16:55 (1h 55m)
Inelastic scattering is useful tool to explore the nuclear structure in the excited states. In particular,
the inelastic excitation to the continuum energy states above the particle decay threshold, which
is often called breakup reaction, is very important because we can pin down a specific nuclear
structure by controlling the exit channels, which are the combination of the emitted fragments.
A typical and good example about the inelastic scattering to the continuum can be seen in the
breakup reaction of 12 Be into the α + 8 He and 6 He + 6 He channels. In this experiment, the carefulmulti-pole decomposition analysis (MDA) was performed, and the MDA analysis elucidates thatmany resonant states with a sharp width exist in the spins from J π = 0+ to 8+ . The 0+ resonancesin the α + 8 He channel appear in a close energy spacing of 0.5 MeV in the lower energy region
below Ee.x. ≤ 15 MeV, which is quite consistent to the energy scheme expected from the cluster
resonances.
Basic and important quantities in the analysis of the resonance enhancement embedded in the continuum strength are the resonance parameters, such as the resonance energy and the decay width.
In determining the resonance parameters, the evaluation of the non-resonant background strength
is indispensable because the resonant enhancement, which has the strong energy dependence, areembedded in the non-resonant background contribution with a broad structure. Since the background strength is structure-less and must have the weak energy dependence, the shape of the
non-resonant background strength is often assumed by the simple analytic function or evaluatedfrom the simple reaction mechanism, such as the direct breakup without the final state interaction
between the decaying fragments.
In this report, we investigate the structure of the non-resonant background continuum, which is
generated by the binary breakup reaction, and explore the prescription to evaluate the backgroundcontribution by extending the Migdal-Watson formula for the s-wave breakup in the charge neutral
system. In the calculation of the strength function for the binary breakup, we employ the complex
scaling method (CSM), which is a powerful tool to describe the few-body continuum states. We
handle the breakup reaction of 20 Ne into α + 16 O and 12 Be into α + 8 He. From the CSM calculation and the Migdal-Watoson theory, we propose the analytic function, which is appropriate toevaluate the background contribution for the binary breakup.

Primary authors: Mr NAKAMOTO, Riu (Department of Pure and Applied physics, Kansai University); Dr ITO, Makoto (Department of Pure and Applied physics, Kansai University/関西大学システ
ム理工学部物理・応用物理学科); Dr AKITO, Saito (Department of Radiation Oncology, ); Prof.
SUSUMU, Shimoura (Center for Nuclear Study, School of Science, University of Tokyo)

Presenter:

Mr NAKAMOTO, Riu (Department of Pure and Applied physics, Kansai University)

Session Classification: Poster

September 8, 2024

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Contribution ID: 62

Proposal of 1 A class deuteron sin …
Type: Oral Presentation

Proposal of 1 A class deuteron single cell linac / 大強度重陽子加速器 ImPACT2017 の提案
A 1-ampere-class high-intensity deuteron linac (ImPACT2017 model) is proposed for mitigating
long-lived fission products (LLFPs) by nuclear transmutation. This accelerator consists of singlecell rf cavities with magnetic focusing elements to accelerate deuterons beyond 1A up to 200MeV/u.

Primary author: OKUNO, Hiroki (RIKEN Nishina center for accelerator-based science)
Presenter: OKUNO, Hiroki (RIKEN Nishina center for accelerator-based science)
Session Classification: Facility

September 8, 2024

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Conference PhotoContribution ID: 63

Type: not specified

Conference Photo
Thursday, 26 November 2020 15:00 (10 minutes)

September 8, 2024

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