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Jendl-4.0

Webjendl-3.3 : 0 k , 300 k JENDL-4.0 : 0 K , 300 K Downloading Files : [ Plot Data ] , [ Gnuplot Input ] , [ PNG Image ] 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

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

WebJENDL-4.0 Japanese Evaluated Neutron Data Library, released in 2010. The library is in ENDF-6 format and contains data for 406 materials from 1-H-1 to 100-Fm-255. More … WebNew in version 3.0 (February 2009) ... • Angular distributions of emitted neutrons (if available in MF=4). • Energy distributions of emitted neutrons and photons (if available in MF=5). • Computations (mathematical operations) on cross sections (MF=3). New in version 1.0 (April 2007) • Interactive access to ENDF/B-VII.0, JEFF-3.1, JENDL ... landgericht bochum referendare https://smediamoo.com

(PDF) Neutron yield calculation of p-Li thick target by using PHITS ...

WebJENDL An Evaluated Nuclear Data Library is a data file that contains recommended nuclear data. The Nuclear Data Center (NDC) of Japan Atomic Energy Agency (JAEA) is making … Web12 ago 2011 · Covariances of actinide nuclear data stored in JENDL-4.0 have been evaluated based on available experimental data and reaction model calculation. The … Web1 gen 2024 · Status of the JENDL project after releasing the latest general purpose file JENDL-4.0 is described. By correcting errors and adding covariance data of JENDL-4.0, 38 files have been released... help your neighbors

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Category:JANIS 4.0, a Java-based nuclear data display program

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Jendl-4.0

Evaluated Nuclear Data File IAEA

Web1 apr 2014 · The author has been able to process ENDF/B-VII.1 using NJOY.99 to produce groupwise data and run a significant number of benchmark cases without issue. Two … Web1 gen 2016 · JENDL-4; 2:1: −0.861: −0.918: 2:13: −0.887: −1.494: 2:19: −0.838 +0.317: In this expression we are assigning all the shift in the calculated reactivity from cold to hot conditions to the bias in the calculation of the temperature effect which means that we are assuming that the bias on the calculation of the Boron and water ...

Jendl-4.0

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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. Web为了满足ads反应堆核设计与分析的需求,本文在对ads次临界系统能谱特点分析的基础上,结合 hendl[4-7]系列数据库的开发经验,设计并制作了适用于ads核设计分析的数据库 hendl-ads/mc,并采用一系列基准实验例题对该核数据库进行了校核以检验数据库的准确 …

Web27 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 … 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.

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, … WebJENDL-4.0. Therefore, it is considered that the MA data in JENDL-4.0 is quite applicable to the MA-loaded fast reactor core analyses with high accuracy. New Evaluations The data …

Web15 giu 2024 · Applications files are proposed for all (2813 targets as all T1/2 > 1 s from Z=1-115 Hydrogen to Moscovium) or a selection of isotopes: 630 neutron targets as the union …

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-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 ... landgenuss bayerwaldWeb10 apr 2024 · “JENDL-4.0 Plus Files (JENDL-4.0+)” is the collection of data files newly evaluated or reevaluated after the JENDL-4.0 was distributed (in May 2010). The … landg equity releasehttp://aesj.net/hp/pnst/06/225_229.pdf landgericht bochum presseWebJSSTDL-300 [3], a common multigroup library of neutron 300 groups and gamma 104 groupsfor shielding applications produced from JENDL-3.2 [4] with the PROF-GROUCH-G/B [5] code byJapanese Nuclear Data Committee, is widely applied in Japan. However, the self-shielding correction inJSSTDL-300 is probably inadequate due to the following two … help your neighbor imagesWebtransform those information in MF=4 and MF=5 formats. 4- There is sometimes in the MF=6 format information concerning the recoil nucleus. GEANT4 are not well prepared to manage this information, so this information has been omitted. GEANT4 meeting, CIEMAT - March 2011 Emilio Mendoza Cembranos help your neighbour bookhamWeb1 dic 2013 · Toward the development of the next version of Japanese Evaluated Nuclear Data Library (JENDL) general-purpose file, we calculate neutron cross-sections on 63, 65Cu from 50 keV to 20 MeV, which is... landgenuss aboWeb10 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 … help your neighbor bible verse