Japanese evaluated nuclear data library version 5: JENDL-5

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Abe, Yutaka; Tsubakihara, Kohsuke; Okumura, Shin; Ishizuka, Chikako; Yoshida, Tadashi; Chiba, Satoshi; Otuka, Naohiko; Sublet, J.‐Ch.; Iwamoto, Hiroki; Yamamoto, Kazuyoshi; Nagaya, Yasunobu; Tada, Kenichi; Konno, Chikara; Matsuda, Norihiro; Yokoyama, Kenji; Taninaka, Hiroshi; Oizumi, Akito; Fukushima, Masahiro; Okita, Shoichiro; Chiba, Go; Sato, Satoshi; Ohta, M.; Kwon, Saerom

doi:10.1080/00223131.2022.2141903

Cited by 130 publications

(29 citation statements)

References 250 publications

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“…These measurements were compared with the cross section data obtained from the literature in order to validate the method for the cross section measurements presented in this study. For the comparison, the cross section values were interpolated from previous works, namely Akagi et al (2013) Additionally, the 12 N cross section measurements were compared with data calculated using nuclear data libraries such as the TALYS-based Evaluated Nuclear Data Library: TENDL-2021 (Koning et al 2019) and the Japanese Evaluated Nuclear Data Library version 5: JENDL-5 (Iwamoto et al 2023). Both of them calculate nuclear reaction cross sections using nuclear models complemented by available measured data.…”

Section: Uncertainty Analysismentioning

confidence: 99%

Measurement of the ¹²C(p,n)¹²N reaction cross section below 150 MeV

Zapien-Campos,

Ahmadi Ganjeh,

Both

et al. 2024

Phys. Med. Biol.

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Objective: Proton therapy currently faces challenges from clinical complications on organs-at-risk due to range uncertainties, anatomical changes, and setup errors. To address this issue, Positron Emission Tomography (PET) of the proton-induced 11C and 15O activity has been used to provide feedback on the proton range. However, this approach is not instantaneous due to the long half-lives of these nuclides. An alternative nuclide, 12N (half-life 11 ms), shows promise for real-time in vivo verification of the proton range. Development of 12N imaging requires better knowledge of its production reaction cross section.Approach: The 12C(p,n)12N reaction cross section was measured by detecting positron activity of graphite targets irradiated with 66.5, 120, and 150 MeV protons. A pulsed beam delivery with 0.7-2×108 protons per pulse was used. The positron activity was measured during the beam-off periods using a dual-head Siemens Biograph mCT PET scanner. The 12N production was determined from activity time histograms.Main results: The cross section was calculated for 11 energies, ranging from 23.5 to 147 MeV, using information on the experimental setup and beam delivery. Through a comprehensive uncertainty propagation analysis, a statistical uncertainty of 2.6-5.8% and a systematic uncertainty of 3.3-4.6% were achieved. Additionally, calibration measurements showed a systematic correction factor of 1.21 (± 7.5%), which contributed the most to global uncertainty. Despite this, there was an improvement in the precision of the cross section measurement compared to values reported by the only previous study for this nuclear reaction. To obtain a continuous cross section function, a weighted spline interpolation using both datasets was performed.Significance: Our results were incorporated into the RayStation Monte Carlo (MC) engine for calculating the 12N positron annihilation distribution during treatment, with the aim of developing an MC simulation framework to predict 12N PET imaging for range verification purposes.

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Section: Uncertainty Analysismentioning

confidence: 99%

Measurement of the ¹²C(p,n)¹²N reaction cross section below 150 MeV

Zapien-Campos,

Ahmadi Ganjeh,

Both

et al. 2024

Phys. Med. Biol.

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“…In the first release of JENDL-5, the use of integral data in the nuclear data evaluation is not reflected in the covariance data. However, according to the suggestion of the working group, the use of the integral data used have been clarified [13]. In the nuclear data evaluation of JENDL-5, many integral experimental data of fast reactors, which were used to create ADJ2017R, were also utilized.…”

Section: Issues On Development Of Unified Cross-section Set Based On ...mentioning

confidence: 99%

“…In the evaluation of JENDL-5, an adjustment calculation was applied by using the generalized least squares method (GLS), in which fission, capture, and elastic scattering of U-235, U-238, and Pu-239 were adjusted [13]. In addition to the GLS-based adjustment calculation, there are several descriptions on the use of integral experimental data.…”

Section: Preliminary Adjustment Calculations Based On Jendl-5 41 Cova...mentioning

confidence: 99%

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Development of adjusted nuclear data library for fast reactor application

Yokoyama

2023

EPJ Web Conf.

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In Japan, development of adjusted nuclear data library for fast rector application based on the cross-section adjustment method has been conducted since the early 1990s. The adjusted library is called the unified cross-section set, which is an ABBN-type group constant set with 70-group energy structure. The first version was developed in 1991 and is called ADJ91. After that, ADJ98, ADJ2000, ADJ2000R, and ADJ2010 were constantly developed. For instance, ADJ2010 was developed based on JENDL-4.0, which provides covariance data needed to apply the cross-section adjustment method, by using 488 integral experimental data acquired in typical fast reactor systems. ADJ2010 has been used as the standard cross-section set for nuclear design in the fast reactor cycle technology development project (FaCT) and the succeeding fast reactor projects. In parallel, the integral experimental data were further expanded to improve the design prediction accuracy of the core loaded with MA and/or degraded Pu. Using the additional integral experimental data, development of the next version of ADJ2017 was started in 2017. In 2022, the latest unified cross-section set AJD2017R was developed based on JENDL-4.0 by using 619 integral experimental data. An overview of the latest version with a review of previous ones will be shown. On the other hand, the latest Japanese evaluated nuclear data library JENDL-5 was released at the end of 2021. In the development of JENDL-5, some of the integral experimental data used in ADJ2017R were explicitly utilized in the nuclear data evaluation. However, this is not reflected in the covariance data. This situation needs to be considered when developing a next version of the unified cross-section set based on JENDL-5. Preliminary adjustment calculation based on JENDL-5 is performed using C/E (calculation/experiment) values simply evaluated by a sensitivity analysis. The preliminary result of the JENDL-5-based adjustment will be also discussed.

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“…• generation of DDX with a physically reasonable interpolation scheme for the 9 Be(p,xn) reaction based on the function for our new nuclear data library JENDL-5 [11] which intends to provide evaluated nuclear data not only for the nuclear energy but also for the accelerator-based applications.…”

Section: Introductionmentioning

confidence: 99%

Estimation of double-differential cross-sections of 9Be(p,xn) reaction for new nuclear data library JENDL-5

Kunieda

Yamamoto

Konno

et al. 2023

JNR

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Double-differential cross-sections of the 9Be(p,xn) reaction are newly evaluated based on the Wakabayashi’s function and neutronics analysis up to 12 MeV for a new nuclear data library, JENDL-5. We devoted our efforts especially to the re-optimization of the absolute cross-sections and the interpolation of the neutron energy spectra. Through the comparisons between the thick target yield measurements and Monte-Carlo simulations at different proton energies and neutron emission angles, we conclude that JENDL-5 gives the best evaluation in the world.

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Japanese evaluated nuclear data library version 5: JENDL-5

Cited by 130 publications

References 250 publications

Measurement of the ¹²C(p,n)¹²N reaction cross section below 150 MeV

Measurement of the ¹²C(p,n)¹²N reaction cross section below 150 MeV

Development of adjusted nuclear data library for fast reactor application

Estimation of double-differential cross-sections of 9Be(p,xn) reaction for new nuclear data library JENDL-5

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Japanese evaluated nuclear data library version 5: JENDL-5

Cited by 130 publications

References 250 publications

Measurement of the 12C(p,n)12N reaction cross section below 150 MeV

Measurement of the 12C(p,n)12N reaction cross section below 150 MeV

Development of adjusted nuclear data library for fast reactor application

Estimation of double-differential cross-sections of 9Be(p,xn) reaction for new nuclear data library JENDL-5

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Measurement of the ¹²C(p,n)¹²N reaction cross section below 150 MeV

Measurement of the ¹²C(p,n)¹²N reaction cross section below 150 MeV