International Reactor Dosimetry File 2002 - IAEA Publications

TABLE 2.2. MEASURED AND CALCULATED AVERAGED CROSS-
SECTIONS IN THE URANIUM-235 THERMAL FISSION NEUTRON
SPECTRUM (cont.)
Reaction
Updated RRDF-98
(mb)
IRDF-90
(mb)
Experimental (mb)
141 Pr(n,2n) 140 Pr 1.0922 — —
139 La(n,γ) 140 La 6.737 — 5.30 [2.17]
186 W(n,γ) 187 W 32.267 — —
204 Pb(n,n′) 204 Pb m 17.770 — 18.900 ± 2.000 [2.19]
19.080 ± 1.524 [2.22]
237 Np(n,f) 1356.2 1355.1 1350.0 ± 24.0 [2.31]
a
Evaluated by the author.
REFERENCES TO SECTION 2
[2.1] ZOLOTAREV, K.I., IGNATYUK, A.V., MAHOKHIN, V.N., PASHCHENKO,
A.B., RRDF-98, Russian Reactor Dosimetry File, Rep. IAEA-NDS-193, Rev. 0,
IAEA, Vienna (1999).
[2.2] ZSOLNAY, E.M., NOLTHENIUS, H.J., SZONDI, E.J., Nuclear Data for Reactor
Dosimetry Libraries: Analysis, Intercomparison and Selection of Data, Rep.
BME-NTI-251/2001, Institute of Nuclear Techniques, Budapest University of
Technology and Economics, Budapest (2001).
[2.3] KOCHEROV, N.P., McLAUGHLIN, P.K., The International Reactor Dosimetry
File (IRDF-90), Rep. IAEA-NDS-141, Rev. 2, IAEA, Vienna (1993).
[2.4] TRYKOV, E.L., TERTYCHNYI, G.Y., Institute of Physics and Power
Engineering (IPPE), Obninsk, personal communication, 1999.
[2.5] UHL, M., STROHMAIER, B., STAPRE — A Computer Code for Particle
Induced Activation Cross Section and Related Quantities, Rep. IRK 76-01,
University of Vienna (1976).
[2.6] YOUNG, P.G., ARTHUR, E.D., A Pre-equilibrium Statistical Nuclear Model
Code for Calculation of Cross Section and Emission Spectra, Rep. LA-6947, Los
Alamos Lab., NM (1977).
[2.7] RAYNAL, J., “Optical-model and coupled-channel calculations in nuclear
physics”, Computing as a Language of Physics (Proc. Int. Sem. Trieste, 1971),
IAEA, Vienna (1972) 281–322.
[2.8] BERSILLON, O., SCAT2 — A Spherical Optical Model Code, Rep. CEA-N-
2037, Commissariat à l’énergie atomique, Bruyères-le-Châtel (1978) 111.
11