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Jendl-4.0

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 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 .

JENDL-4.0 - JAEA

WebThe data for light elements and structural materials were partly reevaluated. Moreover, covariances were estimated mainly for actinoids. The new library was released as … WebJSSTDL-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 … small breasts after weight loss https://jd-equipment.com

今野 力 (Chikara Konno) - 論文 - researchmap

Webjendl-3.3 : 0 k , 300 k JENDL-4.0 : 0 K , 300 K Downloading Files : [ Plot Data ] , [ Gnuplot Input ] , [ PNG Image ] Web13 set 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, … WebThere is a discrepancy of 10-25% discrepancy from 0.5 to 20 keV with JENDL-4.0. Nonetheless, above this energy, the JENDL-4.0 seems to reproduce the present data better as the results agree within uncertainties up to 500 keV. The cross-section results contain errors below 4% from 0.5 to 30 keV. solve for x. y c x+b

Remarks on KERMA Factors in ACE files - ScienceDirect

Category:Some Comments to JSSTDL-300 - 百度学术

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Jendl-4.0

Japanese evaluated nuclear data library version 5: JENDL-5

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. 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 …

Jendl-4.0

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Web11 apr 2024 · Requester: Mr Arnaud COURCELLE at SACLAY, FR Email: [email protected] Project (context): LWR, Material recycling and NEA WPEC Subgroup 26 Impact: Web1 ott 2014 · JENDL-4.0 Neutronics experiment DT neutron MCNP 1. Introduction Nuclear data libraries are some of the most important data needed for controlling the calculation accuracy in nuclear analyses for fusion reactor designs.

Web18 gen 2024 · In 2010, the Japan Atomic Energy Agency released JENDL4.0 [ 5 ]. In this new library, much emphasis is placed on the improvement of fission products and minor actinoid data. As of 2016, the ENDF files of some nuclides in JENDL4.0 have been updated. 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。

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 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 ...

WebJENDL-4.0 adopted mt12-15 mt3 data including the capture reaction for a lot of nuclei, where the kinematics KERMA and DPA data have the same problem as that in nuclei without secondary gamma data (JENDL-4.0 and FENDL-3.1b in Fig. 10 are not correct. The difference between ENDF/B-VII.1

Web1 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 … small breast size chartWebWhat’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) solve for y. a. 115� b. 108� c. 90� d. 130http://aesj.net/hp/pnst/06/225_229.pdf solve for y in terms of x. x − 4y 8Web31 gen 2024 · On the other hand, JENDL-4.0/HE, which is the extended version of JENDL-4.0 up to 200 MeV for 130 nuclei, can reproduce experimental data for the neutron … small breastshot water wheel designWeb26 ott 2024 · JENDL project and related activities Abstract: The latest version of general-purpose file JENDL-4.0 was released in 2010 with improving fission product and minor actinide data as well as covariance data to meet needs of innovative reactors. solve for y examplesWeb27 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 … solve for y poker out loudWeb15 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 … solve for y. a. 115° b. 108° c. 90° d. 130°