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Journal Articles

CIELO collaboration summary results; International evaluations of neutron reactions on uranium, plutonium, iron, oxygen and hydrogen

Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Kahler, A. C.*; Talou, P.*; Plompen, A. J.*; Schillebeeckx, P.*; et al.

Nuclear Data Sheets, 148, p.189 - 213, 2018/02

 Times Cited Count:72 Percentile:98.15(Physics, Nuclear)

The CIELO collaboration has studied neutron cross sections on nuclides that significantly impact criticality in nuclear facilities - $$^{235}$$U, $$^{238}$$U, $$^{239}$$Pu, $$^{56}$$Fe, $$^{16}$$O and $$^{1}$$H - with the aim of improving the accuracy of the data and resolving previous discrepancies in our understanding. This multi-laboratory pilot project, coordinated via the OECD/NEA Working Party on Evaluation Cooperation (WPEC) Subgroup 40 with support also from the IAEA, has motivated experimental and theoretical work and led to suites of new evaluated libraries that accurately reflect measured data and also perform well in integral simulations of criticality. This report summarizes our results and outlines plans for the next phase of this collaboration.

Journal Articles

Summary report on the joint session entitled by "Decommissioning of reactor and accelerator facilities and present status of activation nuclear data libraries"

Nakamura, Shoji

Kaku Deta Nyusu (Internet), (115), p.18 - 23, 2016/10

This is a summary report on the planning joint session entitled by "Decommissioning of reactor and accelerator facilities and present status of activation nuclear data libraries".

JAEA Reports

Report on research and development of nuclear forensics technologies

Okubo, Ayako; Kimura, Yoshiki; Shinohara, Nobuo; Toda, Nobufumi; Funatake, Yoshio; Watahiki, Masaru; Sakurai, Satoshi; Kuno, Yusuke

JAEA-Technology 2015-001, 185 Pages, 2015/03

JAEA-Technology-2015-001.pdf:56.65MB

Nuclear forensics is the analysis of intercepted illicit nuclear or radioactive material and any associated material to provide evidence for nuclear attribution by determining origin, history, transit routes and purpose involving such material. Nuclear forensics activity includes sampling of the illicit material, analysis of the samples and evaluation of the attribution by comparing the analyzed data with database or numerical simulation. Because the nuclear forensics technologies specify the origin of the nuclear materials used illegal dealings or nuclear terrorism, it becomes possible to identify and indict offenders, hence to enhance deterrent effect against such terrorism. Worldwide network on nuclear forensics can contribute to strengthen global nuclear security regime. In this paper, the results of research and development of fundamental nuclear forensics technologies performed in Japan Atomic Energy Agency during the fiscal term of 2011-2013 were reported.

JAEA Reports

MVP/GMVP 2; General purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods

Nagaya, Yasunobu; Okumura, Keisuke; Mori, Takamasa; Nakagawa, Masayuki

JAERI 1348, 388 Pages, 2005/06

JAERI-1348.pdf:2.02MB

To realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two vectorized Monte Carlo codes MVP and GMVP have been developed at JAERI. MVP is based on the continuous energy model and GMVP is on the multigroup model. Compared with conventional scalar codes, these codes achieve higher computation speed by a factor of 10 or more on vector supercomputers. Both codes have sufficient functions for production use by adopting accurate physics model, geometry description capability and variance reduction techniques. The first version of the codes was released in 1994. They have been extensively improved and new functions have been implemented. The major improvements and new functions are (1) capability to treat the scattering model expressed with File 6 of the ENDF-6 format, (2) time-dependent tallies, (3) reaction rate calculation with the pointwise response function, (4) flexible source specification, etc. This report describes the physical model, geometry description method used in the codes, new functions and how to use them.

Journal Articles

A Conceptual design study for active nondestructive assay technique by photon interrogation for uranium-bearing waste

Sakurai, Takeshi; Kosako, Kazuaki*; Mori, Takamasa

Monte Karuro Keisanho Kodoka No Genjo; Dai-3-Kai Monte Karuro Shimyureshon Kenkyukai Hobunshu, p.168 - 176, 2004/12

no abstracts in English

Journal Articles

Integral benchmark experiments of the Japanese Evaluated Nuclear Data Library (JENDL)-3.3 for the fusion reactor design

Nishitani, Takeo; Ochiai, Kentaro; Maekawa, Fujio; Shibata, Keiichi; Wada, Masayuki*; Murata, Isao*

IAEA-CN-116/FT/P1-22 (CD-ROM), 8 Pages, 2004/11

no abstracts in English

JAEA Reports

Production of MVP neutron cross section libraries based on the latest evaluated nuclear data files

Mori, Takamasa; Nagaya, Yasunobu; Okumura, Keisuke; Kaneko, Kunio*

JAERI-Data/Code 2004-011, 119 Pages, 2004/07

JAERI-Data-Code-2004-011.pdf:5.93MB

The 2nd version of code system, LICEM-2, has been developed to produce neutron cross section libraries for the MVP continuous energy Monte Carlo code from an evaluated nuclear data library in the ENDF format. The code system can process nuclear data in the latest ENDF-6 format and produce cross section libraries for MVP's capability of transport calculation at arbitrary temperature. By using the present system, MVP neutron cross section libraries have been prepared from the latest evaluations of JENDL, ENDF/B and JEFF data bases. This report describes the specification of MVP neutron cross section library, the details of each code in the code system, how to use them and MVP neutron cross section libraries produced with the code system.

Journal Articles

Present status and activities of High energy nuclear data evaluation; For future radiation utilization facilities

Fukahori, Tokio; Mukaiyama, Takehiko; Oyama, Yukio; Chiba, Satoshi; Takada, Hiroshi; Maekawa, Hiroshi; Shibata, Tokushi*; Nakamura, Takashi*; ; ; et al.

Nihon Genshiryoku Gakkai-Shi, 40(1), p.3 - 28, 1998/00

 Times Cited Count:1 Percentile:8.82(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Neutron cross section library production code system for continuous energy Monte Carlo code MVP; LICEM

Mori, Takamasa; Nakagawa, Masayuki;

JAERI-Data/Code 96-018, 121 Pages, 1996/05

JAERI-Data-Code-96-018.pdf:3.38MB

no abstracts in English

JAEA Reports

FSXLIB-J3R2: A continuous energy cross section library for MCNP based on JENDL-3.2

Kosako, Kazuaki*; Maekawa, Fujio; Oyama, Yukio; Uno, Yoshitomo; Maekawa, Hiroshi

JAERI-Data/Code 94-020, 42 Pages, 1994/12

JAERI-Data-Code-94-020.pdf:1.18MB

no abstracts in English

JAEA Reports

JAEA Reports

JNDC nuclear data library of fission products; Second version

Tasaka, Kanji; Katakura, Junichi; Ihara, Hitoshi; Yoshida, Tadashi*; Iijima, Shungo*; Nakashima, Ryuzo*; Nakagawa, Tsuneo; Takano, Hideki

JAERI 1320, 253 Pages, 1990/09

JAERI-1320.pdf:10.61MB

no abstracts in English

Journal Articles

Activity report of Japanese Nuclear Data Committee in period of April 1987 to March 1989

Japanese Nuclear Data Committee

Nihon Genshiryoku Gakkai-Shi, 32(1), p.56 - 64, 1990/01

no abstracts in English

JAEA Reports

Journal Articles

Activity report of Japanese Nuclear Data Committee in the period of April 1985 to March 1987

Japanese Nuclear Data Committee

Nihon Genshiryoku Gakkai-Shi, 29(11), p.982 - 991, 1987/11

This is a progress report on the activities of the Japanese Nuclear Data Committee (JNDC) in the period of April 1985 to March 1987. As special topics, two prominent results are presented, the completion of Japanese Evaluated Nuclear Data Library version 3 (JENDEL-3), and plans for the Post-JENDL-3 activity program. In the former, it includes the scope of JENDEL-3, contribution to the fusion neutronics and some problems between simultaneous evaluations of important nuclides and FBR integral tests. For the latter, the recommendation from the working groups on teh special purpose file and on the plan of the Post-JENDEL-3 activity are presented. Some remarks for the promotion of the utilization of JENDEL are also described.

JAEA Reports

PROFPY: A Computer Code for Producing Nuclear Data Library of Fission Products

; ; Tasaka, Kanji; ; ;

JAERI-M 9714, 132 Pages, 1981/10

JAERI-M-9714.pdf:3.58MB

no abstracts in English

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