巻号一覧
後続誌
4 巻, 7 号
選択された号の論文の11件中1～11を表示しています
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捕捉物質の条件大塚 益比古1962 年 4 巻 7 号 p. 423-430
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーConcerning thermal neutron trap reactors, a comparative study of trapping media is made by an analytical approach especially to derive criteria of highly trapping media. Spherical and cylindrical shapes of media are analyzed in the two-group diffusion theory. A criterion is that the thermal neutron diffusion coefficient of a trapping medium must be much smaller than each of the slowing-down length and the thermal neutron diffusion length, provided that both lengths should be modified in case of a finite cylinder. A small size of trap reactors can be realized by a medium whose characteristic lengths are both short.
Calculated values of the trapping effectiveness and the optimum radius of each ordinary moderator are given. Although the comparison with experiments is not yet possible for lack of experimental information under the conditions assumed in this theoretical study, it is suggested that the trapped thermal neutron flux cannot be definitely larger than the flux at the periphery of a trapping mediumroy a factor of ten.抄録全体を表示PDF形式でダウンロード (521K) -
宮永 一郎, 山本 峯澄, 備後 一義1962 年 4 巻 7 号 p. 431-435
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーThe thermal neutron responses of the film (Fuji Badge Film III, Type A) and the silver-activated phosphate glass (8×8×4.7 mm) which has the composition of Li-Al-B-Ag were measured. Thermal neutron exposure was made in the hole No.7 (thermal column) of JRR-1 (Water Boiler Type, 50 kW) in JAERI. The thermal neutron flux was measured by the activation of gold foils. Cd and Sn filter combination and B2O3 were used to differentiate thermal neutron and γ rays. The thermal neutron responses of film and glass in Equivalent Ra dose were (3.84±0.77)×10-10 rads/ncm-2 and (4.14±0.46)×10-9 rads/ncm-2 respectively. Capture γ ray emission of 1 mm Cd was determined to be (1.50±0.30)×10-9 rads/ncm-2 and (1.62±0.17)×10-9 rads/ncm-2 by film and glass measurements respectively, and agreed well with the calculated value of 1.2×10-9 rads/ncm-2 as the lower limit.
The practical method of determination of thermal neutron and γ ray dose in the mixed radiation fields was presented when film or glass are used as the personnel monitoring dosimeters.抄録全体を表示PDF形式でダウンロード (322K) -
渡辺 鐶1962 年 4 巻 7 号 p. 435-439
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーIn measuring absolute value of radioactivity of radioisotope which emits soft β ray, such as 35S and 14C, error caused mainly by self-absorption of β ray in source. In present paper, preparation method of 35S source with less self-absorption and estimation of amount of self-absorption in source were discussed. The most suitable procedures for source preparation of 35S were as follows;
(1) sample solution, sulfuric acid in dilute hydrochloric acid solution, was dropped on thin vinyle film and dried up on a desicant.
(2) this source was dissolved with redistilled water and again dried up in ammoniac atmosphere.
95Nb, which emit β ray with the same maximum and mean energy as that of 35S and emit prompt γ ray, was taken. The crystal sizes of 95Nb source were compared that of 35S sources under the view of microscope. Then the amounts of self-absorption of β ray in these 95Nb sources were drived from the ratio of 4πβ counting rate and 4πβ-γ coincidence counting rate. The amount of self-absorption, which was obtained by using above mentioned method, was about 5% for ordinary source and less than 2% for good source.抄録全体を表示PDF形式でダウンロード (6405K) -
I. 年齢理論野沢 豊吉1962 年 4 巻 7 号 p. 440-447
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーThe diffusion process of neutrons scattered anisotropically in the laboratory system is studied as a stochastic one by using Markov's method. A recurrence formula is derived for the characteristic function which should describe the population of neutrons around a source. The problem is reduced to that of obtaining the maximum eigenvalue and its associated eigenfunction of an integral equation with real symmetric kernel and is solved asymptotically for aged neutrons. It has been suggested that the conventional Fermi age
τu=1/3 u/ξ 1/1-μ(1/Σs)2, u: lethargy, should better be replaced by
τn=1/3 n 1+μ/1-μ(1/Σs)2, n: nos. of collision,
μ being the average cosine of the scattering angle in the laboratory.抄録全体を表示PDF形式でダウンロード (492K) -
望月 博治, 田中 義久, 東原 義治, 長渡 甲太郎, 頼久 勝明1962 年 4 巻 7 号 p. 448-456
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーIn the present work, we obtained buildup factors experimentally for heterogeneous media, composed of various combinations of materials (H2O, Fe and Pb), for 60Co γ-rays. On the basis of the results, we obtained an empirical formula which is acceptable physically and capable of quick and easy calculation of buildup factors for heterogeneous media, composed of arbitrary combinations of materials, by using known buildup factors for the finite homogeneous media of the materials included in the compound. Experimental buildup factors are not intrinsically different over 10% from the calculated values from the formula for the shield thickness of 06mfp and for 60Co γ-ray source. The experimental results obtained indicate that the buildup factors agree well with the theoretical values for iron, lead, and multilayers of materials investigated here in the case of relatively small thickness of lead slabs, but not for water and multilayers in the case of large thickness of lead slabs. The effect of heterogeneity of compounds on buildup factors was also investigated.抄録全体を表示PDF形式でダウンロード (4082K) -
上野 馨, 張 昭鼎1962 年 4 巻 7 号 p. 457-462
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーA radiochemical study of the solvent extraction behavior of more than fifty chemical elements in the hydrochloric acid-tetraphenylarsonium chloride chloroform system was performed. The distribution ratios were determined in the hydrochloric acid solutions of 0.5 to 12 N concentrations. It has been concluded.
(1) Cationic species in hydrochloric acid solution are not extractable.
(2) Anionic species in hydrochloric acid solution are readily extracted, but it was found that monovalent species are much more extractable than di- or tri-valent species.抄録全体を表示PDF形式でダウンロード (347K) -
1962 年 4 巻 7 号 p. 462
発行日: 1962年
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (48K) -
能沢 正雄, 野本 昭二, 石川 寛1962 年 4 巻 7 号 p. 463-480
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーCompared with thermal reactors, fast reactors have inherent advantages in the breeding properties, since the fast reactor is designed to minimize the moderating materials in its core so as to keep the neutron spectrum hard. Design and calculations of the reactor at high neutron energy necessitate to use the informations for nuclear cross sections in the wide range of neutron energy.
In Chap. I and II, energy resources for future and meanings of breeding are discussed. In Chap. III, nuclear constants required in the calculation of fast reactors are reviewed in connection with current nuclear experiments and theories. In Chap. IV and V, parametric studies of a number of types of fuel elements and reactor configurations are surveyed. Different types of fast reactors are described with their advantages in several points. In this survey, the emphasis are put upon the physical pictures of breeding in fast reactor, but not on the calculational techniques.抄録全体を表示PDF形式でダウンロード (5202K) -
関口 忠1962 年 4 巻 7 号 p. 481-487
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (645K) -
1962 年 4 巻 7 号 p. 488-490
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (231K) -
H. HOWELLS1962 年 4 巻 7 号 p. 491-494
発行日: 1962/07/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (347K)
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