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Journal Articles

Report of 31st Meeting of the Working Party on International Nuclear Data Evaluation Co-operation (WPEC)

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kimura, Atsushi; Yokoyama, Kenji; Tada, Kenichi

Kaku Deta Nyusu (Internet), (124), p.23 - 34, 2019/10

The 31st annual meeting and the subgroup meeting of the Working Party on International Nuclear Data Evaluation Co-operation (WPEC) under the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) was held at the head quarter of OECD/NEA located at Boulogne-Billancourt near Paris from 24 to 28 in June in 2019. The activities about nuclear data measurement and evaluation of each region or country were reported at the annual meeting, and the SG activities were discussed at the subgroup meetings. The summary of these meetings are reported.

Journal Articles

23rd Technical Meeting of the International Network of Nuclear Structure and Decay Data Evaluators

Koura, Hiroyuki

Kaku Deta Nyusu (Internet), (124), p.1 - 13, 2019/10

no abstracts in English

Journal Articles

Frontier of nuclear data researches on fission product nuclides, 1; Progress in nuclear data evaluation

Iwamoto, Nobuyuki

Kaku Deta Nyusu (Internet), (123), p.12 - 21, 2019/06

no abstracts in English

Journal Articles

International Conference on Nuclear Data for Science and Technology (ND2019), 3; Evaluation and theory

Nakayama, Shinsuke; Iwamoto, Osamu; Iwamoto, Nobuyuki; Hashimoto, Shintaro

Kaku Deta Nyusu (Internet), (123), p.53 - 59, 2019/06

The 2019 International Conference on Nuclear Data for Science and Technology (ND2019) was held at the China National Convention Center on May 19-24, 2019. The series of the ND conferences are the largest conferences in nuclear data research field that are held every three years. In this paper, as a part of the conference reports of ND2019, the authors gave summaries of the presentations on nuclear data evaluation and theory conducted at the conference.

Journal Articles

Report on "Joint IAEA-ICTP Workshop on Nuclear Structure and Decay Data; Experiment, Theory and Evaluation"

Koura, Hiroyuki

Kaku Deta Nyusu (Internet), (123), p.1 - 11, 2019/06

no abstracts in English

Journal Articles

Report on the IAEA Technical Meeting "Nuclear Data Processing"

Tada, Kenichi

Kaku Deta Nyusu (Internet), (122), p.9 - 21, 2019/02

This paper reports the overview of the technical meeting of nuclear data processing in IAEA to Japanese researchers. In this technical meeting, the current status of nuclear data processing codes and verification of them are described.

Journal Articles

Impulsing paradigm change through disruptive technologies program, ImPACT; Reduction and resource recycling of high-level radioactive waste through nuclear transmutation

Iwamoto, Osamu; Fujita, Reiko*; Niita, Koji*; Watanabe, Yukinobu*

Kaku Deta Nyusu (Internet), (122), p.33 - 43, 2019/02

A program related to the transmutation of long-lived fission products (LLFPs) entitled "Reduction and Resource Recycling of High-level Radioactive Wastes through Nuclear Transmutation" has been conducted under the Impulsing Paradigm Change through Disruptive Technologies Program (ImPACT) organized by the Cabinet Office since 2014 and it will be finished in FY 2018. Various activities from acquisition of basic data to examination of transmutation scenario are being carried out as the five separated projects. R&Ds related to nuclear data are also conducted and many outcomes are being produced. This article describes results of the two projects related nuclear data with a short introduction of the whole project.

Journal Articles

Summary report on Consultants' Meeting of INDEN on the Evaluated Nuclear Data of the Structural Materials

Iwamoto, Nobuyuki

Kaku Deta Nyusu (Internet), (122), p.5 - 8, 2019/02

This is a summary report on Consultants' Meeting of INDEN on the Evaluated Nuclear Data of the Structural Materials hosted by IAEA.

Journal Articles

3rd RCM on Updating the Photonuclear Data Library and Generating a Reference Database for Photon Strength Functions

Utsunomiya, Hiroaki*; Iwamoto, Nobuyuki; Kawano, Toshihiko*

Kaku Deta Nyusu (Internet), (122), p.26 - 32, 2019/02

no abstracts in English

Journal Articles

Joint Session of Nuclear Data Subcommittee and Sigma Special Advisory Committee; Present status and future of nuclear data evaluation code in Japan, 3; Development of DEURACS for prediction of deuteron-induced reaction cross section

Nakayama, Shinsuke

Kaku Deta Nyusu (Internet), (120), p.19 - 25, 2018/06

Toward development of accurate deuteron nuclear data, we have been developing a computational code dedicated for the deuteron-induced reaction, called DEURACS. The author presented the developmental status and the future outlook of DEURACS in the joint session of nuclear data subcommittee and sigma special advisory committee, and contributed the outline of the presentation to Nuclear Data News. From our preceding work, it has become possible to predict the $$(d,xn)$$ reactions on light nuclei and the $$(d,xt)$$ reactions. These reactions are important in relation to evaluation of neutron sources and tritium production, respectively. In the future, we plan to improve theoretical models implemented in DEURACS for accurate prediction of nuclide production cross-section on medium-heavy nuclei.

Journal Articles

2018 Annual Meeting of Japan Atomic Energy Society, Joint Session of Nuclear Data Subcommittee and Sigma Special Advisory Committee; Present status and future of nuclear data evaluation code in Japan, 4; Role and improvement of nuclear reaction models in the PHITS code

Hashimoto, Shintaro; Sato, Tatsuhiko; Iwamoto, Yosuke; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Niita, Koji*

Kaku Deta Nyusu (Internet), (120), p.26 - 34, 2018/06

Particle and heavy-ion transport code system PHITS has been used for calculations of radiation shielding in accelerator facilities. PHITS describes physical phenomena induced by radiation as combination of transport and collision processes. The collision process including nuclear reactions is simulated by the three-step calculation: a generation of a reaction, pre-equilibrium, and compound processes. In the simulation, many physics models are used. This report explains roles of the models in PHITS and shows their developments we recently performed.

Journal Articles

2018 Annual Meeting of Japan Atomic Energy Society, Session of Subcommittees and Liaison Meetings, Nuclear Subcommittee [co-sponsor of Sigma Advisory Committee], Present status and future of nuclear data evaluation code in Japan, 2; Progress of a nuclear model code CCONE

Iwamoto, Osamu

Kaku Deta Nyusu (Internet), (120), p.11 - 18, 2018/06

Progress of the nuclear reaction model code CCONE is shown based on the presentation at the session titled "Present status and future of nuclear data evaluation code in Japan" at the session of Nuclear Data subcommittee at 2018 Annual Meeting of Japan Atomic Energy Society. The CCONE code is developed for the nuclear data evaluation calculation for JENDL. It was applied to the nuclear data evaluation for actinides at first, and extension for the higher energies reactions was performed. At present it is applied to various data evaluations such as photonuclear reaction and decay data.

Journal Articles

Report on the 30th Meeting of Working Party on International Nuclear Data Evaluation Co-operation

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kimura, Atsushi; Yokoyama, Kenji; Tada, Kenichi

Kaku Deta Nyusu (Internet), (120), p.35 - 46, 2018/06

We report 30th WPEC meeting, expert group meeting, and subgroup meeting in Paris, May 14-18, 2018.

Journal Articles

Another important piece; One point burnup calculation code as a Killer Application

Suyama, Kenya; Yokoyama, Kenji

Kaku Deta Nyusu (Internet), (119), p.38 - 47, 2018/02

We have developed numerous neutronics calculation codes in Japan. However, development of the one-point burnup calculation code which replaces the still widely used ORIGEN2 code has not been successful. The one point burnup code is indispensable to evaluate the characteristics of the used nuclear fuel increasing in Japan, and it uses all evaluated nuclear data including the fission yield and decay data as well as cross section data. It means that it could be the Killer Application in the field of the nuclear data and neutronics code. This report describes the necessity of the one point burnup calculation code development in Japan and required function and performance which have been considered by authors.

Journal Articles

Report on the 16th International Symposium on Capture Gamma-Ray Spectroscopy and Related Topics

Iwamoto, Nobuyuki

Kaku Deta Nyusu (Internet), (119), p.1 - 5, 2018/02

no abstracts in English

Journal Articles

Small talk about experiments at n_TOF in CERN

Kimura, Atsushi

Kaku Deta Nyusu (Internet), (118), p.36 - 42, 2017/10

no abstracts in English

Journal Articles

Atomic Energy Society of Japan 2017 Annual Meeting, joint session of "sigma advisory committee", "subcommittee on nuclear data" and "subcommittee on reactor physics"; Current status and future perspective of the Verification and Validation (V&V) of JENDL and neutronics calculation codes by use of the benchmark problems and integral experiments, 2; International benchmarks of OECD/NEA in the field of the neutronics calculation

Suyama, Kenya

Kaku Deta Nyusu (Internet), (117), p.5 - 14, 2017/06

The benchmark calculation is one of the main activities of the Nuclear Science Committee under the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA/NSC). The international benchmark relatively frequently means the benchmark activity carried out by the NEA. In this manuscript, the author discusses the significance of the international benchmark by describing (i) the current status of the benchmark in the field of the reactor physics conducted by the OECD/NEA/NSC, (ii) revision of the neutronics calculation code system to reflect the results of the benchmark, (iii) the benchmark calculation as the asset for the future research and development, (iv) examples of the benchmark calculation based on the experimental data, and (v) how to propose the benchmark in the OECD/NEA/NSC.

Journal Articles

Atomic Energy Society of Japan 2017 Annual Meeting, joint session of "sigma advisory committee", "subcommittee on nuclear data" and "subcommittee on reactor physics"; Current status and future perspective of the Verification and Validation (V&V) of JENDL and neutronics calculation codes by use of the benchmark problems and integral experiments, 4, Development of an automatic nuclear data validation system VACANCE

Tada, Kenichi

Kaku Deta Nyusu (Internet), (117), p.23 - 29, 2017/06

Validation of the nuclear data library using the criticality experiments and nuclear reactor experiments, i.e., integral experiments, is one of the most important process. The analyses of the integral experiments become the more important along with the accuracy improvement of the library. This validation procedure is mainly carried out by the specialists of the reactor physics because it is complicated for the nuclear data evaluators. Furthermore, it takes a long time and much effort even if the specialists carry it out. To realize the efficient nuclear data validation cycle for the next version of JENDL, the automatic nuclear data validation system VACANCE (Validation Environment for Comprehensive and Automatic Neutronics Calculation Execution) is developed. In this presentation, the outline and functions of VACANCE are demonstrated in detail and examples of the new nuclear data evaluation and subsequent integral experiment analyses will be shown.

Journal Articles

Report on the 29th Meeting of Working Party on International Nuclear Data Evaluation Co-operation (WPEC)

Harada, Hideo; Iwamoto, Osamu; Kimura, Atsushi; Yokoyama, Kenji; Tada, Kenichi

Kaku Deta Nyusu (Internet), (117), p.36 - 51, 2017/06

no abstracts in English

Journal Articles

Joint Session of Sigma Special Advisory Committee, Nuclear Data Subcommittee, and Reactor Physics Subcommittee; Current status and future perspective of the verification and validation (V&V) of JENDL and neutronics calculation codes by use of the benchmark problems and integral experiments, 5; Status of JENDL development and requests to V&V

Iwamoto, Osamu

Kaku Deta Nyusu (Internet), (117), p.30 - 35, 2017/06

This report is a summary of the Status of JENDL development and requests to V&V presented at Joint Session of Sigma Special Advisory Committee, Nuclear Data Subcommittee, and Reactor Physics Subcommittee, Current Status and Future Perspective of the Verification and Validation (V&V) of JENDL and Neutronics Calculation Codes by use of the Benchmark Problems and Integral Experiments, at 2018 Annual Meeting of Atomic Energy Society of Japan. It describes present status of JENDL development including update file JENDL-4.0u, next version of general purpose file JENDL-5, and special purpose file together with request to V&V for development of JENDL.

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