Outline of JENDL-5

岩本 修

JAEA-Conf 2022-001, p.21 - 26, 2022/11

https://doi.org/10.11484/jaea-conf-2022-001

The next version of JENDL general purpose library, JENDL-5, is almost ready to be released. JENDL-5 increases variety and amount of data from the current version JENDL-4.0. Regarding the neutron induced reaction data, which is the most important for reactor applications, the number of the stored nuclides will be around 800, which is almost double of 406 as of JENDL-4.0. They cover not only all stable isotopes but also a large number of unstable isotopes that are much enough for various applications of radiation simulations. The data from light to heavy nuclides have been revised reflecting up-to-date experimental knowledge such as new measurements of cross sections by ANNRI at J-PARC. Fission yield and decay data are also revised with new experimental and theoretical knowledge. New evaluations of thermal scattering law data based on molecular dynamics are adopted for many of materials in JENDL-5 including light and heavy water. The data of other incident particles than neutron that have been developed as special-purpose files are integrated into JENDL-5. For proton, deuteron, alpha-particle and photon induced reactions, the data of JENDL-4.0/HE, JENDL/ImPACT-2018, JENDL/DEU-2020, JENDL/AN-2005, JENDL/PD-2016.1 are adopted. Since JENDL/AN-2005 contains only neutron-emission related data, date needed for radiation transportation codes are complemented. Regarding neutron induced reaction, the data of high energy reaction above 20 MeV and activation cross section are also integrated from JENDL-4.0/HE, JENDL/ImPACT-2018 and JENDL/AD-2017.

Status and future plan of JENDL

岩本 修

JAEA-Conf 2019-001, p.7 - 11, 2019/11

https://doi.org/10.11484/jaea-conf-2019-001

Nuclear Data Center of JAEA is planning to develop the next version of the general-purpose file, JENDL-5. Evaluation of nuclear data of light nuclei and structure materials are in progress. Data of minor actinides and fission products are also being updated based on the recent measurements including the TOF experiment by ANNRI at J-PARC. The first version of the test file of JENDL-51 was created in this year. It includes the updated and newly-evaluated data for more than 90 nuclides. The benchmark testing of JENDL-51 for reactor and shielding is in progress. In addition to the general-purpose file, special purpose files for photonuclear reactions and activation cross sections was recently released as JENDL/PD-2016 and JENDL/AD-2017 to meet the needs of electron accelerator application and the decommissioning of nuclear facilities, respectively. At the symposium, the recent progress and the future plan about developments of JENDL will be presented.

Status of the JENDL project

岩本 修; 柴田 恵一; 岩本 信之; 国枝 賢; 湊 太志; 市原 晃; 中山 梓介

EPJ Web of Conferences, 146, p.02005_1 - 02005_6, 2017/09

https://doi.org/10.1051/epjconf/201714602005

The latest version of the general purpose file JENDL-4.0 was released in 2010 with enhancing data of fission products and minor actinides. After that, the neutron energy range of JENDL-4.0 were extended up to 200 MeV adding proton induced reaction data. They were compiled as JENDL-4.0/HE and released in 2015. An activation cross section library for decommission of nuclear reactor, JENDL/AD-2016, is under development and will be released by 2017. It will contain neutron reaction data for approximately 300 nuclides in energy range of eV to 20 MeV including isomer production cross sections. Evaluation of nuclear data for the next version of the general purpose file is also in progress. It is planned to be released by 2022. Several new evaluations mainly for fission products that had not been updated in JENDL-4.0 were already done. Data for light nuclei and structure material will be updated. Minor actinides data are still important to develop transmutation system of nuclear waste. They will be updated using new measurements especially done in J-PARC. Status of the JENDL project in developing the general and special purpose files will be presented.

Shielding experiments with quasi-monoenergetic neutrons between 15 and 90 MeV at 90 MV AVF cyclotron facility TIARA

坂本 幸夫; 中島 宏; 中根 佳弘; 田中 俊一; 田中 進; 中村 尚司*; 馬場 護*; 中尾 憲晶*; 秦 和夫*

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.809 - 815, 1994/00

高崎研究所の90MV AVFサイクロトロン施設TIARAにおいて、加速器遮蔽に関する基礎データを入手するための中性子遮蔽実験プログラムが大学とのプロジェクト共同研究として開始された。今までに鉄とコンクリート遮蔽体についての中性子透過実験を41MeV及び65MeVのエネルギーで行った。p-Liターゲットからの入射中性子スペクトルを反跳陽子型スペクトロメータで測定するとともに、遮蔽体内部及び後方での中性子強度及びスペクトルを有機シンチレータ、各種カウンター及び線量計で測定した。実験解析では400MeVまでのHILO86及びHILO86Rの群定数を用いて2次元Sn計算コードDOT3.5及びモンテカルロ計算コードMORSEでスペクトル及び中性子反応率を算出した。その結果、核分裂計数管による中性子反応率を30%以内の精度で再現した。

新原子力エネルギー発生装置に関する研究

小川 雅生*

PNC TJ1607 91-001, 14 Pages, 1991/03

PNC-TJ1607-91-001.pdf:0.38MB

中性子の少ない核融合反応を用いてエネルギーを取り出すことを指向した研究の初期段階を行なった。本研究ではエネルギーが1020keVの重陽子分子イオンビームを入射し、解離した原子イオンをミラー磁場の中に閉じ込めるための基礎実験装置の設計を進めた。装置の設計に必要な情報を得るために、ビーム軌道のシミュレーションを行なった。

革新型原子炉開発のための核データ整備基盤の構築,6; 熱中性子散乱則および荷電粒子放出反応断面積の評価手法の検討

中山 梓介; 岩本 修

no journal, , 

溶融塩炉や小型モジュール炉(SMR)では減速材として黒鉛やCaHの使用が検討されている。減速材の熱中性子散乱則は炉心設計に大きな影響を及ぼす。また、溶融塩中のK-39やSMRのヒートパイプ中のCu-63に対する(n,p), (n,a)といった荷電粒子放出反応は廃棄物管理上問題となる核種を生成し得る。そのため、これら革新炉の炉心設計をする上では、黒鉛やCaHの熱中性子散乱則ならびにK-39やCu-63の荷電粒子放出反応断面積に関する精度良いデータが重要になる。以上を踏まえ、これらのデータの評価手法の検討を進めているところである。本発表では、現在までの進捗状況について述べる。