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Data Book for calculating neutron yields from ({alpha}, n) reaction and spontaneous fission

Technical Report:

Abstract

Neutron yields from ({alpha}, n) reaction and spontaneous fission, which are very important in analyzing radiation shielding of spent fuel storage, transport, and safe handling, were collected and evaluated to determine the recommendable values. For thick target neutron yields from ({alpha}, n) reactions, the most accurate data of West and Sherwood, the newest evaluated data of Heaton et al., and the data of high atomic number nuclides evaluated by Nakasima were adopted. And the experimental data at a high energy region of Stelson and McGowan were also used as references. The data for estimating neutron yields of unmeasured elements are also prepared in this Data Book by using theoretical values of ({alpha}, n) excitation function and the evaluation formulas on stopping power by Ziegler. For neutron yields from spontaneous fission, the values recommended by S. Raman were mainly adopted. Neutron energy spectra of ({alpha}, n) reaction and spontaneous fission were also included in this Data Book. Neutron production data of compounds can be obtained by using the neutron yield and stopping power of each single element. (author).
Authors:
Matsunobu, Hiroyuki; Oku, Takeshi; [1]  Iijima, Shungo; Naito, Yoshitaka; Masukawa, Fumihiro; Nakasima, Ryuzo
  1. Sumitomo Atomic Energy Industries Ltd., Osaka (Japan)
Publication Date:
Jan 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-1324
Reference Number:
SCA: 663440; 663610; 050900; PA: JPN-92:011196; SN: 93000918601
Resource Relation:
Other Information: PBD: Jan 1992
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NEUTRON EMISSION; ALPHA REACTIONS; SPONTANEOUS FISSION; SHIELDING; SPENT FUEL STORAGE; NUCLEAR DATA COLLECTIONS; EXCITATION FUNCTIONS; STOPPING POWER; EVALUATED DATA; COMPILED DATA; 663440; 663610; 050900; D-, T-, AND HE-INDUCED REACTIONS AND SCATTERING; NEUTRON PHYSICS; TRANSPORT, HANDLING, AND STORAGE
OSTI ID:
10111235
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE93753275; TRN: JP9211196
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
268 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Matsunobu, Hiroyuki, Oku, Takeshi, Iijima, Shungo, Naito, Yoshitaka, Masukawa, Fumihiro, and Nakasima, Ryuzo. Data Book for calculating neutron yields from ({alpha}, n) reaction and spontaneous fission. Japan: N. p., 1992. Web.
Matsunobu, Hiroyuki, Oku, Takeshi, Iijima, Shungo, Naito, Yoshitaka, Masukawa, Fumihiro, & Nakasima, Ryuzo. Data Book for calculating neutron yields from ({alpha}, n) reaction and spontaneous fission. Japan.
Matsunobu, Hiroyuki, Oku, Takeshi, Iijima, Shungo, Naito, Yoshitaka, Masukawa, Fumihiro, and Nakasima, Ryuzo. 1992. "Data Book for calculating neutron yields from ({alpha}, n) reaction and spontaneous fission." Japan.
@misc{etde_10111235,
title = {Data Book for calculating neutron yields from ({alpha}, n) reaction and spontaneous fission}
author = {Matsunobu, Hiroyuki, Oku, Takeshi, Iijima, Shungo, Naito, Yoshitaka, Masukawa, Fumihiro, and Nakasima, Ryuzo}
abstractNote = {Neutron yields from ({alpha}, n) reaction and spontaneous fission, which are very important in analyzing radiation shielding of spent fuel storage, transport, and safe handling, were collected and evaluated to determine the recommendable values. For thick target neutron yields from ({alpha}, n) reactions, the most accurate data of West and Sherwood, the newest evaluated data of Heaton et al., and the data of high atomic number nuclides evaluated by Nakasima were adopted. And the experimental data at a high energy region of Stelson and McGowan were also used as references. The data for estimating neutron yields of unmeasured elements are also prepared in this Data Book by using theoretical values of ({alpha}, n) excitation function and the evaluation formulas on stopping power by Ziegler. For neutron yields from spontaneous fission, the values recommended by S. Raman were mainly adopted. Neutron energy spectra of ({alpha}, n) reaction and spontaneous fission were also included in this Data Book. Neutron production data of compounds can be obtained by using the neutron yield and stopping power of each single element. (author).}
place = {Japan}
year = {1992}
month = {Jan}
}