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Se(
, n) cross section and the evaluation of uncertainty of 
Se(n, ) cross sectionKitatani, Fumito
Kaku Deta Nyusu (Internet), (114), p.44 - 49, 2016/06
no abstracts in English
W, 
Re and 
Os; Implications for the Re-Os cosmochronologyShizuma, Toshiyuki; Utsunomiya, Hiroaki*; Mohr, P.*; Hayakawa, Takehito; Goko, Shinji*; Makinaga, Ayano*; Akimune, Hidetoshi*; Yamagata, Tamio*; Ota, Masahisa*; Ogaki, Hideaki*; et al.
Physical Review C, 72(2), p.025808_1 - 025808_9, 2005/08
Times Cited Count：44 Percentile：90.03(Physics, Nuclear)Cross sections of the W, Re, Os(
) reactions were measured using quasi-monochromatic photon beams from laser Compton scattering (LCS) with average energies from 7.3 to 10.9 MeV. The results are compared with the predictions of Hauser-Feshbach statistical calculations using four different sets of input parameters. In addition, the inverse neutron capture cross sections were evaluated by constraining the model parameters, especially the 
strength function, on the basis of the experimental data. The present experiment helps to further constrain the correction factor 
for the neutron capture on the 9.75 keV state in Os. Implications of to the Re-Os cosmochronology are discussed with a focus on the uncertainty in the estimate of the age of the Galaxy.
-ray spectroscopic methodsFurutaka, Kazuyoshi
JNC TN8400 2000-028, 70 Pages, 2000/10
JNC-TN8400-2000-028.pdf:1.71MB
This report describes the study done by the author as a postdoctoral research associate at Japan Nuclear Cycle Development Institute. This report is divided into two parts: improvements in accuracy in determination of thermal neutron capture cross sections, and improvements in accuracy of photo-nuclear absorption cross section measurements using the HHS. (1)In the measurements of thermal neutron capture cross sections using an activation method, accuracies of the final results attained are limited by (1) accuracy of -ray peak detection efficiencies, and (2) accuracies of -ray emission probabilities. In this study; to determine thermal neutron capture cross sections more accurately, the following researches have been done using a newly developed three-dimensional coincidence measurement system: (1)accurate determination of -ray standard sources using a - coincidence method, for precise calibration of -ray peak detection efficiency, and (2) development of a 
- coincidence measurement system using a plastic scintillation detector as a -ray detector, for the determination of -ray emission probabilities of short-lived nuclides, and measurement of -ray emission probabilities of 
Tc nuclide using the coincidence system. (2)To transform radioactive nuclides with small thermal neutron capture cross sections, use of photonuclear absorption reaction has been suggested. In order to transform these nuclides efficiently using the reaction, one has to know detailed behavior of the photo-absorption cross sections. In this study, a Monte-Carlo simulation code has been used to create a standard set of -ray response functions of the high-resolution high-energy spectrometer (HHS), to enable reliable analyses of the data obtained by the spectrometer.
*
JNC TJ9400 2000-008, 61 Pages, 2000/02
For studies on nuclear transmutation of long-lived fission products (LLFPs) in a fast reactor, detailed characteristics of reactor core such as transmutation performance have to be investigated, so accurate neutron cross section data of LLFPs become necessary. Therefore, the keV-neutron capture cross sections of Tc-99, which is one of important LLFPs, were measured in the present study to obtain the accurate data. The measurement was relative to the standard capture cross sections of Au-197. A neutron time-of-flight method was adopted with a ns-pulsed neutron source by a Pelletron accelerator and a large anti-Compton NaI(TI) gamma-ray detector. As a result, the capture cross sections of Tc-99 were obtained with the error of about 5 % in the incident neutlon energy region of 10 to 600 keV. The present data were compared with other experimental data and the evaluated values of JENDL-3.2, and it was found that the evaluations of JENDL-3.2 were 15-20 % smaller than the present measurements.
*
JNC TJ9400 99-001, 78 Pages, 1999/03
For studies on incineration of long-lived fission products (LLFPs) in a fast reactor, detailed characteristics of reactor core such as incineration performance have to be investigated. Therefore, accurate neutron cross section data of LLFPs become necessary. In the present study, in order to perform the precise measurements of keV-neutron capture cross sections of Tc-99, which is one of most important LLFPs, the details of the Tc-99 sample and the measurements with our experimental facilities were investigated.
JAERI-M 6306, 53 Pages, 1975/11
no abstracts in English
Genshikaku Kenkyu, 7(6), 580 Pages, 1962/00
no abstracts in English
Hashimoto, Shintaro; Nagai, Yasuki*; Minato, Futoshi; Tsukada, Kazuaki
no journal, ,
Study for radioisotopes (RIs) production using accelerator neutron sources plays an important role in development of production method to supply stably RIs for medical use. We measured yields of not only 
Cu produced by neutrons but also 
Ga by protons in 
ZnO samples irradiated by neutrons from 
Be(d,n) reaction with 40-50 MeV deuterons, and developed a powerful method to estimate the yields using a general purpose Monte Carlo particle transport simulation mode PHITS with cross section data of the (d,n) reaction and JENDL-4.0/HE. We found a good agreement between new measured yields and estimated results within a factor of 3. Furthermore, we experimentally observed that yields of Ga are enhanced by covering the samples with polyethylene blocks. However, PHITS cannot reproduce the enhancement probably due to insufficient description of scattered neutrons form the blocks in the calculation.
Hashimoto, Shintaro; Nagai, Yasuki*
no journal, ,
In the study of radioisotope (RI) production using accelerator neutrons, a combination method of the particle transport code PHITS and the induced radioactivity code DCHAIN is powerful tools for calculating the RI production and its time course due to beam irradiation. We improved the method of RI production by neutrons above 20 MeV, which was not sufficiently reliable in the combined calculations. The RI production by neutrons above 20 MeV is usually calculated by a nuclear reaction model, which does not reproduce experimental data well. Therefore, we improved the method by preparing evaluated nuclear data of neutrons above 20 MeV and using it automatically in the combined calculation.
Lu produced by deuteronsHashimoto, Shintaro; Nagai, Yasuki*
no journal, ,
A plan by irradiating enriched 
Yb samples with accelerated deuterons has been considered to produce Lu, one of the medical radioisotopes. However, Lu isotopes other than Lu are produced by nuclear reactions between the deuteron and the other Yb isotopes included in the enriched Yb sample, and are impurities in the Lu product. In this study, we determined all reaction cross section models for Lu isotopes production by deuteron irradiation on Yb samples on the basis of experimental data of the Lu production cross section. By combining these models with the particle and heavy-ion transport code system, PHITS, we can evaluate the yield of each Lu isotopes produced and the purity of Lu nuclides when Yb samples with arbitrary composition ratios are irradiated with deuteron beams.
