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Jendl-4.0

Web19 ore fa · The database contains nuclear reaction data (neutron cross-sections and others) from main regional and national evaluated data libraries (ENDF/B-7.1, USA; JEFF-3.2, NEA; CENDL-3.1, China; JENDL-4.0u2, Japan; and BROND-2, Russia), all in ENDF format and related data processing computer codes for data preparation for neutron transport and … Web1 dic 2012 · The results for ENDF/B-VII.1 and JEFF-3.1.1 are more the 5000 pcm below the benchmark value, whereas the results for JENDL-4.0 are within the benchmark uncertainty range. There are two main possibilities why the performance of the libraries is so different for this benchmark case, whereas for the others the performance is similar.

JENDL project and related activities IEEE Conference Publication ...

Web12 apr 2024 · The fuel temperature is 900K and moderator temperature is 600K. JENDL-4.0 is used . U-235 enrichment of matrix is 0.2wt%. Pu enrichment of each region is shown in Table 1. Isotopic ratio of Pu is shown in Table 2. The calculations of the modified OpenMOC are performed under the conditions shown in Table 3. WebIn order to improve accuracy of the Monte-Carlo simulations including this energy region, the fourth version of Japanese Evaluated Nuclear Data Library High Energy File (JENDL … trophy online singapore https://rdhconsultancy.com

Evaluated Nuclear Data Library Descriptions - Nuclear …

WebJENDL-4.0 High Energy File (JENDL-4.0/HE) is an extended version of JENDL-4.0 up to 200 MeV for a number of nuclei which are relevant to high-energy applications. It also … Web10 apr 2024 · JENDL-4.0 の概要. 特 徴. 高速炉、熱中性子炉の設計・解析、核融合炉中性子工学、中性子遮蔽計算などに使える日本の汎用標準核データライブラリ。. 収録核種 … WebJENDL-4.0(=JENDL-3.3) was evaluated based on the Gwin et al. [Citation 36] In addition, JENDL-4.0 took the rather complicated energy dependence in keV energy region below … trophy optics

Nuclear Energy Agency (NEA) - Data available in the NEA database

Category:JENDL-4.0: A New Library for Nuclear Science and Engineering

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Jendl-4.0

JANIS 4.0 User

Web1 feb 2024 · On the other hand, the uncertainty prediction of nuclear data using the two evaluations ENDF/B-VII.1 and JENDL-4.0 are presented and discussed. In this work, all sensitivity and uncertainty calculations are based on the Monte Carlo code (MCNP6) [4] and the NJOY99 [ 5 ]. 2. TRIGA model description 2.1. General description WebJENDL-4.0/HE Benchmark Test with Concrete and Iron Shielding Experiments at JAEA/TIARA Konno Chikara, Matsuda Norihiro, Kwon Saerom, Ohta Masayuki, Sato Satoshi ICRS-13 & RPSD-2016, 13TH INTERNATIONAL CONFERENCE ON RADIATION SHIELDING & 19TH TOPICAL MEETING OF THE RADIATION PROTECTION AND …

Jendl-4.0

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WebWhat’s new in version 4.0. New functionalities: Ø Save and restore state: plots, tables, along with their settings like colors, line widths... can now be saved as a .JNS file, which can later be reopened. JNS files are simple XML files which can also be edited by hand (see III.B.5) Web16 dic 2024 · For instance, the JENDL 4.0 library is an updated version of JENDL 3.3, with the number of nuclides changing from 337 to 406. Based on reference, 30 fission products were added to JENDL 4.0, as were several updated cross-section values, such as a neutron capture cross section of 232 Th, 238 Pu, and 241 Am in the thermal energy range .

Web在中国cendl-3.1评价库[2]中,236np全套中子数据于2003年完成全新评价,此后的10年内,国际上先后公布了一些新的全套中子评价数据库[3-6],特别是2010年日本公布的全套中子评价数据库jendl-4.0[3],其对236np进行了全新的理论模型计算。 Webwhile those with JENDL-4.0/HE are smaller by ~ 40 % and ~ 20 % at maximum than those with FENDL-3.1b and JENDL-HE/2007, respectively. 3.5 Problems of 56Fe data in JENDL-4.0/HE In order to specify reasons for the larger underestimation of the calculation result with JENDL-4.0 in the iron experiment with 65 MeV neutrons, the cross section data

Webcomment. ↑. ↑. *) Fig1, Fig2 and Fig3 are made from pointwise files at 300 K. Fig1 : Total, elastic and inelastic scattering, capture and fission cross sections. Fig2 : Same as Fig1 … Web11 apr 2024 · Requester: Mr Arnaud COURCELLE at SACLAY, FR Email: [email protected] Project (context): LWR, Material recycling and NEA WPEC Subgroup 26 Impact:

Webnuclear data library, JENDL-4.0, has been released,5) and its excellent performance for fission reactor applications has been reported.6) The present paper is also one of the JENDL-4.0 benchmark reports, and evaluates the perform-ance of JENDL-4.0 for eff prediction for fast neutron sys-tems. Experimental data of eff, which had been obtained at

WebJENDL: AC-2008: 2008: Data up to 20 MeV for 79 actinides from 89 Ac to 100 Fm: 4.0/HE: 2016: Extended version of JENDL-4.0 up to 200 MeV for 130 nuclei: HE-2007: 2007: … trophy opt 2022Web27 apr 2024 · The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% ( 241 Pu), 3% ( 233 U, 240 Pu), or 2% ( 235 U, 239 Pu). The newly evaluated 235 U, 238 U and 239 Pu cross sections agree with the IAEA Neutron Data Standards 2024 within 2% with some exceptions. KEYWORDS: Fission cross … trophy order near metrophy orderWebJENDL-4.0 High-Energy File (JENDL-4.0/HE) [3], was released in 2015. It includes evaluated cross-sections for incident neutrons and protons up to 200 MeV for 130 and 133 nuclei, respectively. Substantial features of the JENDL-4.0/HE are, (1) systematic evaluation for medium-mass nuclei using the CCONE code [4] with trophy order formWebThe new library was released as JENDL-4.0, and the data can be retrieved from the Web site of the JAEA Nuclear Data Center. KEYWORDS: JENDL-4.0 nuclear data evaluation … trophy or medalWeb1 gen 2011 · 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 … trophy orderingWebIn order to improve accuracy of the Monte-Carlo simulations including this energy region, the fourth version of Japanese Evaluated Nuclear Data Library High Energy File (JENDL-4.0/HE) as a new special purpose file, was released in 2015. It includes evaluated cross-sections for incident neutrons and protons up to 200 MeV for 130 and 133 nuclei ... trophy organizer