JENDL Actinoid File 2008

Iwamoto, Osamu; Nakagawa, Tsuneo; Otuka, Naohiko; Chiba, Satoshi; Okumura, Keisuke; Chiba, Go; Ohsawa, Takaaki; Furutaka, Kazuyoshi

doi:10.1080/18811248.2007.9711557

Cited by 18 publications

(11 citation statements)

References 45 publications

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“…Matsuoka and Ito [9] have shown that the application of a JENDL Actinide file 2008 [18] as the nuclear data library of MVP-BURN to the isotopic composition analysis of BWR MOX fuel samples of about 75 to 80 GWd/t in the MALIBU program gives about 2% to 10% overestimates of the measured isotopic compositions of 238 Pu while applying JENDL-3.3 shows about 5% to 10% underestimates though they are not shown in Figure 3. The burnup calculations of MVP-BURN for both libraries were performed by using the general-purpose chain model (u4cm6fp104bp12T).…”

Section: Introductionmentioning

confidence: 87%

Feedback on neutron capture cross sections of ²³⁸Pu and ²⁴¹Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

Yamamoto¹,

Sakai²

2015

Journal of Nuclear Science and Technology

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The atomic fractions of 238 Pu and 241 Am in MOX fuels recycled in light water reactors are 1% to 2% and not significant compared with those of major Pu isotopes. On the other hand, recent evaluated nuclear data libraries, such as JENDL-4.0 and JEFF-3.2, give noticeably different thermal and epithermal neutron capture cross sections for 238 Pu and 241 Am. The thermal neutron capture cross sections of 238 Pu and 241 Am in JEFF-3.2 are 31% and 9% larger than those of JENDL-4.0, respectively. This paper shows the effect of the differences in the neutron cross sections on analysis results of two different integral experiments. The first is the isotopic compositions of 238 Pu on UO 2 and MOX fuels irradiated in BWR and PWR, and the second is the critical experiments of the water moderated cores fully loaded with MOX fuels. The former was analyzed by using the continuous energy Monte Carlo burnup calculation code MVP-BURN and the latter by the continuous energy Monte Carlo calculation code MVP. The comparisons between the calculated and measured results indicate that the most likely thermal and epithermal neutron capture cross sections of 238 Pu and 241 Am should be around at the middle between those of JEFF-3.2 and JENDL-4.0.

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Section: Introductionmentioning

confidence: 87%

Feedback on neutron capture cross sections of ²³⁸Pu and ²⁴¹Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

Yamamoto¹,

Sakai²

2015

Journal of Nuclear Science and Technology

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“…• JENDL/AC-2008 [11] (Japan, 2008) for transmutation study, • EAF-2010 [12] (UK, 2010) for activation and transmutation studies, • FENDL-2.1 [13] (IAEA, 2004) for fusion applications, and • IRDFF-1.0 [14] (IAEA, 2012) for dosimetry applications.…”

Section: Evaluated Nuclear Data Libraries Available In the Worldmentioning

confidence: 99%

JENDL: Nuclear databases for science and technology

Shibata

2013

Journal of Nuclear Science and Technology

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It is exactly 50 years since the Japanese Nuclear Data Committee was founded both in the Atomic Energy Society of Japan and in the former Japan Atomic Energy Research Institute. The committee promoted the development of Japan's own evaluated nuclear data libraries. As a result, we managed to produce a series of Japanese Evaluated Nuclear Data Libraries (JENDLs) to be used in various fields for science and technology. The libraries are categorized into general-purpose and special-purpose ones. The generalpurpose libraries have been updated periodically by considering the latest knowledge on experimental and theoretical nuclear physics that was available at the time of the updates. On the other hand, the specialpurpose libraries have been issued in order to meet the needs for particular application fields. This paper reviews the research and development for those libraries.

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“…The nuclear data of 156 materials were selected from mainly ENDF/B-VII.0 and partly JENDL/AC 22) and IAEA NDS project.…”

Section: Matxs File In Ads-20mentioning

confidence: 99%

Important Remarks on Latest Multigroup Libraries

Konno

Takakura

Kondo

et al. 2011

Progress in Nuclear Science and Technology

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We have already pointed out that the background cross sections and weighting flux are not adequate in the multigroup library VITAMIN-B6. Here we examine whether the latest multigroup libraries, VITENEA-J, VITJEFF31.BOLIB, MATJEFF31.BOLIB, V7-200N47G in SCALE6, MATXS file in ADS-2.0, HILO2k and MATXSLIB-J33, have the same problems or not. The followings are found out from simple benchmark calculations with ANISN; 1) MATXSLIB-J33 has no problem, 2) VITENEA-J, VITJEFF31.BOLIB, V7-200N47G in SCALE6 and HILO2k are produced by using an inadequate weighting flux, 3) VITJEFF31.BOLIB, MATJEFF31.BOLIB and MATXS file in ADS-2.0 have insufficient background cross section data. It is noted that the self-shielding correction in VITENEA-J, VITJEFF31.BOLIB, MATJEFF31.BOLIB, V7-200N47G in SCALE6, MATXS file in ADS-2.0 and HILO2k is not always adequate, which can lead to unexpected results.

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JENDL Actinoid File 2008

Cited by 18 publications

References 45 publications

Feedback on neutron capture cross sections of ²³⁸Pu and ²⁴¹Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

Feedback on neutron capture cross sections of ²³⁸Pu and ²⁴¹Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

JENDL: Nuclear databases for science and technology

Important Remarks on Latest Multigroup Libraries

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JENDL Actinoid File 2008

Cited by 18 publications

References 45 publications

Feedback on neutron capture cross sections of 238Pu and 241Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

Feedback on neutron capture cross sections of 238Pu and 241Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

JENDL: Nuclear databases for science and technology

Important Remarks on Latest Multigroup Libraries

Contact Info

Product

Resources

About

Feedback on neutron capture cross sections of ²³⁸Pu and ²⁴¹Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments

Feedback on neutron capture cross sections of ²³⁸Pu and ²⁴¹Am from analyses of measured isotopic compositions of irradiated LWR fuels and MOX core physics experiments