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| Summary of JENDL-4.0 |
| Purpose |
To provide a Japanese standard library for fast breeder reactors, thermal reactors,
fusion neutronics and shielding calculations, and other applications
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Number of nuclides |
406 |
| Incident neutron energy range |
10-5 eV to 20 MeV |
| Format |
ENDF-6 Format.
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| Pointwise files |
prepared at 0K and 300K with LINEAR, RECENT and SIGMA1 (accuracy=0.1%) |
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Details of JENDL-4.0
(numerical data, descriptions, figures and tables of cross sections) |
- H, He, Li, Be, B, C, N, O, F (Z= 1 - 10)
- Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca (Z= 11 - 20)
- Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn (Z= 21 - 30)
- Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr (Z= 31 - 40)
- Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn (Z= 41 - 50)
- Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd (Z= 51 - 60)
- Pm, Sm, Eu, Gd, Tb, Dy, Er, Tm, Yb (Z= 61 - 70)
- Hf, Ta, W, Os, Au, Hg (Z= 71 - 80)
- Pb, Bi, Ra, Ac, Th (Z= 81 - 90)
- Pa, U, Np, Pu, Am, Cm, Bk, Cf, Es, Fm (Z= 91 - 100)
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| JENDL-4.0 Updated Files [JENDL-4.0u] |
Updated files of JENDL-4.0 are distributed when the data were modified
because of fatal compilation etc.
There are updated files for the nuclides as following. [ Update: 2012/09/14 ]
JENDL-4.0 : 
2H,
10B,
48Ti,
52Cr, 53Cr,
59Ni,
109Ag,
127mTe, 129mTe,
233U, 234U, 235U, 238U,
239Pu,
243Am
JENDL-4.0 Fission Yield Sublibrary :

241Pu,
242mAm.
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| JENDL-4.0 Plus Files [JENDL-4.0+] |
“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 JENDL4.0+ may include not only the nuclides already evaluated for JENDL-4.0 but also nuclides not evaluated yet.
There is no JENDL-4.0+ file now.
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| Downloading JENDL-4.0 |
DVD-ROM
containing JENDL-4.0 original files, pointwise files, and cross-section graphs is available on request.
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| Data files and Useful Reports made from JENDL-4.0 |
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| References of JENDL-4.0 |
- K. Shibata, O. Iwamoto, T. Nakagawa, N. Iwamoto, A. Ichihara, S. Kunieda, S. Chiba, K. Furutaka,
N. Otuka, T. Ohsawa, T. Murata, H. Matsunobu, A. Zukeran, S. Kamada, and J. Katakura:
"JENDL-4.0: A New Library for Nuclear Science and Engineering,"
J. Nucl. Sci. Technol.. 48(1), 1-30 (2011).
- K. Shibata, O. Iwamoto, T. Nakagawa, N. Iwamoto, A. Ichihara, S. Kunieda, S. Chiba, N. Otuka, and J. Katakura:
"JENDL-4.0: A New Library for Innovative Nuclear Energy Systems,"
Proc. 2010 the International Conference on Nuclear Data for Science and Technology (ND2010),
J. Korean. Phys. Soc., 59(23), 1046-1051 (2011).
- O. Iwamoto, T. Nakagawa, N. Otuka, and S. Chiba:
"Covariance Evaluation for Actinide Nuclear Data in JENDL-4,"
Proc. 2010 the International Conference on Nuclear Data for Science and Technology (ND2010),
J. Korean. Phys. Soc., 59(23), 1224-1229 (2011).
- G. Chiba, K. Okumura, K. Sugino, Y. Nagaya, K. Yokoyama, T. Kugo, M. Ishikawa and S. Okajima:
"JENDL-4.0 Benchmarking for Fission Reactor Applications,"
J. Nucl. Sci. Technol., 48(2), 172-187 (2011).
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Nuclear Data Center, Japan Atomic Energy Agency (JAEA)
Modified at 2013/04/02 15:11 JST
jendl@jaea.go.jp
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