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Program name | Package id | Status | Status date |
---|---|---|---|
ZZ-FSXJ32 | NEA-1424/03 | Tested | 30-AUG-2002 |
ZZ-FSXJ32 | NEA-1424/06 | Tested | 30-AUG-2002 |
ZZ-FSXLIBJ33 | NEA-1424/07 | Tested | 26-OCT-2006 |
Machines used:
Package ID | Orig. computer | Test computer |
---|---|---|
NEA-1424/03 | DEC ALPHA W.S. | PC Pentium III 500 |
NEA-1424/06 | DEC ALPHA W.S. | PC Windows |
NEA-1424/07 | Many Computers | IBM PC,PC Windows |
NEA-1424/03 - ZZ-FSXJ32
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JENDL-3.2 based MCNP library.
FORMAT: MCNP
NUMBER OF GROUPS: Continuous energy cross section library.
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Hf, Ta, W, Pb, Bi, Ra, Ac, Th, Pa, U, Np, Pu, Am, Cm, Bk, Cf, Es, Fm.
TEMPERATURES: 293 K, 600 K, 900 K, 1200 K, 1500 K, 2000 K
ORIGIN: JENDL-3.2
WEIGHTING SPECTRUM: --
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The temperature-dependent continuous energy cross section library for MCNP, FSXJ32, was prepared from JENDL-3.2 for a variety of applications in the field of atomic energy.
NEA-1424/06 - ZZ-FSXJ32
April 2005: This is the DVD version of ZZ-FSXJ32 NEA-1424/03.
NEA-1424/07 - ZZ-FSXLIBJ33
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This version differs from version NEA-1424/05 in the following: Index files xsdir.fsxlb331 and xsdir.fsxlb332 have been updated, since atomic weights were missing for 23 nuclides.
JENDL-3.3 based MCNP library.
FORMAT: MCNP
NUMBER OF GROUPS: Continuous energy cross section library.
Nuclides: 337 nuclides contained in JENDL-3.3
1H, 2H, 3HE, 4HE, 6LI, 7LI, 9BE, 10B, 11B, natC, 14N, 15N, 16O, 19F, 23NA, 24MG, 25MG, 26MG, 27AL, 28SI, 29SI, 30SI, 31P, 32S, 33S, 34S, 36S, 35CL, 37CL, 40AR, 39K, 40K, 41K, 40CA, 42CA, 43CA, 44CA, 46CA, 48CA, 45SC, 46TI, 47TI, 48TI, 49TI, 50TI, natV, 50CR, 52CR, 53CR, 54CR,55MN, 54FE, 56FE, 57FE, 58FE, 59CO, 58NI, 60NI, 61NI, 62NI, 64NI, 63CU, 65CU, 69GA, 71GA, 70GE, 72GE, 73GE, 74GE, 76GE, 75AS, 74SE, 76SE, 77SE, 78SE, 79SE, 80SE-, 82SE, 79BR, 81BR, 78KR, 80KR, 82KR, 83KR, 84KR, 85KR, 86KR, 85RB, 87RB, 86SR, 87SR, 88SR, 89SR, 90SR, 89Y, 91Y, 90ZR, 91ZR, 92ZR, 93ZR, 94ZR, 95ZR, 96ZR, 93NB, 94NB, 95NB, 92MO, 94MO, 95MO, 96MO, 97MO, 98MO, 99MO, 100MO, 99TC, 96RU, 98RU, 99RU, 100RU, 101RU, 102RU, 103RU, 104RU, 106RU, 103RH, 105RH, 102PD, 104PD, 105PD, 106PD, 107PD, 108PD, 110PD, 107AG, 109AG, 110mAG, 106CD, 108CD, 110CD, 111CD, 112CD, 113CD, 114CD, 116CD, 113IN, 115IN, 112SN, 114SN, 115SN, 116SN, 117SN, 118SN, 119SN, 120SN, 122SN, 123SN, 124SN, 126SN, 121SB, 123SB, 124SB, 125SB, 120TE, 122TE, 123TE, 124TE, 125TE, 126TE, 127mTE, 128TE, 129mTE, 130TE, 127I, 129I, 131I, 124XE, 126XE, 128XE, 129XE, 130XE, 131XE, 132XE, 133XE, 134XE, 135XE, 136XE, 133CS, 134CS, 135CS, 136CS, 137CS, 130BA, 132BA, 134BA, 135BA, 136BA, 137BA, 138BA, 140BA, 138LA, 139LA, 140CE, 141CE, 142CE, 144CE, 141PR, 143PR, 142ND, 143ND, 144ND, 145ND, 146ND, 147ND, 148ND, 150ND, 147PM, 148PM, 148mPM, 149PM, 144SM, 147SM, 148SM, 149SM, 150SM, 151SM, 152SM, 153SM, 154SM, 151EU, 152EU, 153EU, 154EU, 155EU, 156EU, 152GD, 154GD, 155GD, 156GD, 157GD, 158GD, 160GD, 159TB, 162ER, 164ER, 166ER, 167ER, 168ER, 170ER, 174HF, 176HF, 177HF, 178HF, 179HF, 180HF, 181TA, 182W, 183W, 184W, 186W, 196HG, 198HG, 199HG, 200HG, 201HG, 202HG, 204HG, 204PB, 206PB, 207PB, 208PB, 209BI, 223RA, 224RA, 225RA, 226RA, 225AC, 226AC, 227AC, 227TH, 228TH, 229TH, 230TH, 232TH, 233TH, 234TH, 231PA, 232PA, 233PA, 232U, 233U, 234U, 235U, 236U, 237U, 238U, 235NP, 236NP, 237NP, 238NP, 239NP, 236PU, 237PU, 238PU, 239PU, 240PU, 241PU, 242PU, 244PU, 246PU, 241AM, 242AM, 242mAM, 243AM, 244AM, 244mAM, 240CM, 241CM, 242CM, 243CM, 244CM, 245CM, 246CM, 247CM, 248CM, 249CM, 250CM, 247BK, 249BK, 250BK, 249CF, 250CF, 251CF, 252CF, 254CF, 254ES, 255ES, 255FM
TEMPERATURES: 300 K
ORIGIN: JENDL-3.3
WEIGHTING SPECTRUM: --
THERMAL SCATTERING: Free gas model. KERMA factors are provided.
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The original JENDL-3.3 has two problems in Am-241 data. One is the missing of MF/MT=4/18, and the other is the incorrect neutron spectra for MT=18 below 500 keV.
The updated data have been produced as JENDL-3.3u. This version of fsxlib-j33 reflects the modifications.
In addition, the mass table in xsdir has been corrected for some missing nuclei such as Pu-236.
NEA-1424/03 - ZZ-FSXJ32
The nuclear data processing system NJOY-97 was used to produce FSXJ32. Reliability of the library was confirmed by solving several benchmark problems.
NEA-1424/07 - ZZ-FSXLIBJ33
The nuclear data processing system NJOY-99.67 was used to produce FSXLIBJ33. Reliability of the library was confirmed by solving several benchmark problems.
Package ID | Status date | Status |
---|---|---|
NEA-1424/03 | 30-AUG-2002 | Screened |
NEA-1424/06 | 30-AUG-2002 | Screened |
NEA-1424/07 | 26-OCT-2006 | Screened |
F. Maekawa, K. Sakurai, K. Kosako, E. Kume, N. Kawasaki, Y. Nomura and Y. Naito: Development of Automatic Editing System for MCNP Library "autonj", JAERI-Data/Code 99-048 (November 1999) in Japanese
NEA-1424/03 - ZZ-FSXJ32:
K. Kosako, F. Maekawa, Y. Oyama, Y. Uno and H. Maekawa
Nuclear Data Center
Japan Atomic Energy Research Institute
Tokai-mura, Ibaraki-ken 319-1195, Japan
NEA-1424/07 - ZZ-FSXLIBJ33:
K. Kosako(+), N. Yamano(+), T. Fukahori, K. Shibata(*) and A. Hasegawa
Nuclear Data Center
Japan Atomic Energy Research Institute
Tokai-mura, Ibaraki-ken 319-1195, Japan
(*) Corresponding author
(+) Sumitomo Atomic Energy Industries, Ltd.
Keywords: Monte Carlo method, cross sections, evaluated data, neutron cross sections.