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Plasma physics and controlled nuclear fusion research conference proceedings 等离子体物理与受控核聚变研究会议论文集
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90018-X
D. Dobrott
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引用次数: 1
The accurate fission cross-section of 239Pu from 0·005 eV to 0·1 eV and its reference value at 2200 m/s 得到了239Pu在0.005 ~ 0.1 eV范围内的精确裂变截面及其2200 m/s时的参考值
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90011-7
A.J. Deruytter , W. Becker

A precise measurement of the fission cross-section of 239Pu was performed with a slow chopper at the Belgian BR2-reactor (energy range 0·000 to 0·1 eV). Simultaneous recordings of pulse-height and time-of-flight spectra of successively compared 239Pu layers and standard elemental boron layers were made. The detection of the 10B(n, α)7Li and 239Pu(n, ƒ) reaction fragments is made with excellent pulse-height resolution in low geometry with a AuSi surface barrier detector. The separation between the pile-up tail produced by the α-particles of 239Pu and the fission fragment energy-distribution was very good. The amount of 10B in the elemental boron layers was determined by weighing in vacuum combined with careful chemical and isotopic analysis of witness foils. The relative amounts of 10B were checked by neutron-counting in the geometry of the experiment. The amounts of 239Pu on the fission foils were determined from precise low-geometry α-counting and the knowledge of the isotopic composition and α-half-life values. The α-activity was controlled before and after the measurements.

The fission cross-section was calculated in the energy-range from 0·005 to 0·1 eV and its absolute value deduced at 2200 m/s was 741·9 ± 3·4b. These cross-section values were used to calculate the Westcott g/tf-factor for a 20·44°C Maxwellian neutron distribution with as results gƒ = 1·0553 ± 0·0013.

在比利时br2反应堆(能量范围为0·000 ~ 0·1 eV)上，用慢波斩波器对239Pu的裂变截面进行了精确测量。同时记录了连续比较的239Pu层和标准元素硼层的脉冲高度和飞行时间谱。利用AuSi表面势垒探测器，在低几何形状条件下对10B(n， α)7Li和239Pu(n, f)反应碎片进行了极好的脉冲高度分辨率检测。239Pu α-粒子产生的堆积尾与裂变碎片能量分布的分离效果很好。通过真空称量，结合对见证箔进行细致的化学和同位素分析，确定了元素硼层中10B的含量。在实验的几何图形中，通过中子计数来检查10B的相对量。利用精确的低几何α-计数和对同位素组成和α-半衰期值的了解，确定了裂变箔上239Pu的含量。测定前后对α-活性进行控制。计算了在0.005 ~ 0.1 eV能量范围内的裂变截面，在2200 m/s时得到的裂变截面绝对值为741·9±3.4 b。这些截面值用于计算20.44°C麦克斯韦中子分布的Westcott g/tf因子，结果为gf = 1.0553±0.013。
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引用次数: 8
A transmission method to measure capture rates in fast reactors 一种测量快堆俘获率的传输方法
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90012-9
Dietmar Kuhn

A method is described to measure neutron capture rates of materials in a cavity in the center of a fast reactor. The method is based on neutron transmission through a probe of the material to be investigated and can be used also in zero power facilities. Some measurements were done for U-235 and for U-238. On account of the special detector used, it is limited, however, to sufficiently hard neutron energy spectra.

介绍了一种测量快堆中心空腔中材料中子俘获率的方法。该方法基于中子通过待测材料探针的透射，也可用于零功率设施。对U-235和U-238进行了一些测量。然而，由于使用了特殊的探测器，它受到足够硬中子能谱的限制。
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引用次数: 0
Factors influencing the economical application of food irradiation proceedings of a panel on the technological factors involved in the economical application of food irradiation 影响食品辐照经济应用的因素有关食品辐照经济应用所涉及的技术因素的小组会议记录
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90020-8
C.L. Comar
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引用次数: 0
Irradiation facilities for research reactors 研究反应堆的辐照设施
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90019-1
W.L. Whittemore
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引用次数: 12
The total cross-section of natural uranium for fast neutrons in the energy range (0·8–9·0 MeV) 天然铀对能量范围(0.8 ~ 0.9 MeV)的快中子的总截面
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90010-5
D.B.C.B. Syme , J.D. Kellie, J. McKeown , S.J. Hall, G.I. Crawford

The total cross-section of natural uranium for fast neutrons in the energy range (0·8–9·0 MeV) has been measured with good resolution and statistical precision, using a time-of-flight spectrometer based on an electron linear accelerator as neutron source. The results are compared with other recent data, with the recommended ENDF/B III evaluation and with theoretical calculations.

利用以电子直线加速器为中子源的飞行时间谱仪，以较好的分辨率和统计精度测量了能量范围(0·8-9·0 MeV)内天然铀对快中子的总截面。结果与其他近期数据、推荐的ENDF/B III评价和理论计算进行了比较。
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引用次数: 0
Papers to be published 拟发表的论文
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90022-1
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引用次数: 0
Current papers in nuclear energy 最新的核能论文
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90021-X
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引用次数: 0
The effect of the anisotropic scattering on the thermal utilization factor 各向异性散射对热利用系数的影响
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90014-2
N.I. Laletin, N.V. Sultanov, Yu.A. Vlasov, S.I. Koniaev

In calculations of the thermal utilization factor for heterogeneous reactors the anisotropic scattering is taken into account usually in the transport and sometimes in the linear-anisotropic approximations. The work of Eccleston and McCormick make doubtful the generally accepted opinion that the second angular moment of the scattering kernel has little effect on the disadvantage factor in slab cells in nuclear reactors.

In the present work we have investigated the effect of the second and higher angular moments of the scattering kernel on the thermal utilization factor. The formulas appropriate for the qualitative analysis of the question under consideration are given and a set of cells was calculated by various methods. A disagreement between the data obtained and those reported by Eccleston and McCormick is shown.

在非均相反应器热利用系数的计算中，各向异性散射通常在输运中考虑，有时在线性各向异性近似中也考虑。埃克莱斯顿和麦考密克的工作使人们对普遍接受的散射核的第二角矩对核反应堆板室的不利因素影响不大的观点产生了怀疑。在本工作中，我们研究了散射核的第二次和更高的角矩对热利用系数的影响。给出了适用于所考虑问题的定性分析的公式，并用各种方法计算了一组单元格。所获得的数据与埃克莱斯顿和麦考密克报告的数据之间存在分歧。
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引用次数: 7
Radiobiological applications of neutron irradiation, proceedings of a panel, Vienna. 6–10 December 1971 中子辐照的放射生物学应用，小组会议录，维也纳，1971年12月6-10日
Annals of Nuclear Science and Engineering
Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90017-8
W.L. Whittemore
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引用次数: 0
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