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JNC TJ9400 2000-009, 63 Pages, 2000/02
JNC-TJ9400-2000-009.pdf:2.48MB
The present status of nuclear data for technetium (Tc)-99, which is a well-known fission product (FP), has been reviewed and investigated. And making use of the Kyoto university Lead Slowing-down Spectrometer (KULS), the cross section of the 
Tc (n, 
) 
Tc reaction has been measured in the energy range from thermal to keV neutron energy with an Ar-gas proportinal counter. The neutron flux/spectrum has been monitored with a BF
proportional counter, and the relative measurement has been normalized to the well-known standard capture cross section value for the Tc (n, ) Tc reaction at 0.0253 eV. Self-shielding corrections, especially near the resonance peaks, were made by the calculations with the MCNP code. Although the experimental data measured by Chou et al with a lead slowing-down spectrometer are higher in general, the energy dependency is similar to the present measurement. The evaluated data in ENDF/B-VI and JENDL-3.2 are higher near the resonances at 5.6 and 20 eV and above several 100 eV. A lead slowing-down spectrometer was installed coupled to a 46 MeV electron linac at the Research Reactor Institute, Kyoto university (KURRI). Characteristics of the Kyoto University Lead Slowing-down Spectrometer (KULS) were measured and (1)the relation between neutron slowing-down time t(
s) and energy E(keV) (E=190/t
in Bi hole and E=156/t in Pb hole) and (2)the energy resolution (
40% in Bi and Pb holes) were experimentally investigated. (3)The neutron energy spectrum in the KULS was also measured by the neutron TOF method. The results obtained by the MCNP code were in general agreement with these experimental ones.
Aso, Tomokazu; Ishikura, Shuichi*; Teshigawara, Makoto*; Hino, Ryutaro
JAERI-Tech 97-063, 59 Pages, 1997/12
no abstracts in English
*
PNC TJ9604 97-001, 108 Pages, 1997/03
A lead slowing-down spectrometer was installed coupled to the 46 MeV electron linac at Research Reactor Institute, Kyoto university (KURRI). Characteristics of the Kyoto University Lead Slowing-down Spectrometer (KULS) were measured for (1)the relation between neutron slowing-down time t(s) and energy E (keV) (E=190/t in Bi hole and E=156/ in Pb hole), (2)energy resolutlon (40 % in Bi and Pb holes), and (3)neutron energy spectrum by the neutron TOF method. The results obtained by the MCNP code were in general agreement with these experimental ones. The KULS has been applied to the fission cross section measurements of Am-241, Am-243 and Am-242m relative to that of U-235 from 0.1 eV to 10 keV, making use of the back-to-back type double fission chambers. For Am-241, Dabbs and ENDF/B-VI data are in good agreement with the present measurement. The JEND L-3.2 data are smaller by a factor of 2 between 10 and 200 eV. The ENDF/B-VI data for Am-243 are lower between 15 and 60 eV, and the JENDL-3.2 are lower in general above 100 eV. It has been found that the preliminary result for the Am-242m(n,f) reaction is close to the ENDF/B-VI and the JENDL-3.2 data. Thermal neutron cross sections for Am-241 and Am-243 have also been measured in a standard Maxwellian distribution spectrum field. Finally, aiming at the measurement of capture cross section for MA nuclides, the experimental investigation for Np-237 sample (2 mg) has been performed with the KULS. Due to the comparable background counts to the foreground ones, the capture events from the sample have scarecely been detected with an Ar-gas proportional counter.
; Sugikawa, Susumu; ; Miyoshi, Yoshinori; Miyauchi, Masakatsu; Izawa, Naoki
JAERI-Tech 96-058, 28 Pages, 1997/01
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 21(5), p.434 - 440, 1979/00
Times Cited Count：0no abstracts in English
; *
Nihon Genshiryoku Gakkai-Shi, 1, P. 304, 1959/00
no abstracts in English
-ray spectroscopy measurement systemTakamine, Jun; Rodriguez, D.; Koizumi, Mitsuo; Seya, Michio
no journal, ,
As the part of basic development of the active neutron nondestructive measurement techniques with collaboration between JAEA and EC-JRC, A technical development of delayed spectrometry intended for determining ratio of fissile isotopes (e.g 
U, 
Pu, 
Pu) is being performed. For the purpose of design of neutron moderator for D-T neutron source used in DGS, simulations are performed using simplified model. We report the results and a concept of system based on them.
