Journal of Nuclear Energy. Part B. Reactor Technology最新文献

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Thoria as a Fertile Component for a Liquid Metal Breeder Blanket 钍作为液态金属增殖毯的可育成分

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30016-X

A. Brown, A. Chitty

The crystal chemistry and physics of thoria are reviewed with emphasis on the properties required to form a stable suspension of thoria in liquid bismuth. The variation of the density of thoria with temperature has been determined accurately over the temperature range 0–1100°C and a measurement of the adsorbed gas (CO₂ and CO) has been made. It is shown that thoria is intrinsically wetted by bismuth provided the thoria surface is free from contamination. The solution of certain elements in the bismuth is shown to cause wetting of thoria produced by decomposition of thorium salts, and some elements are shown to reduce thoria with subsequent formation of ThBi₂. A suspension of thoria in liquid bismuth containing an added element E is stable if the following relationship is satisfied: $- Δ G_{o x} (C) < - Δ G_{o x} (E) < - Δ G_{o x} (A l)$

The results are discussed in terms of the thermodynamics of oxidation/reduction processes.

综述了钍的晶体化学和物理性质，重点介绍了在液态铋中形成稳定的钍悬浮液所需的性质。在0 ~ 1100℃的温度范围内，准确测定了钍的密度随温度的变化，并对吸附气体(CO2和CO)进行了测量。结果表明，只要钍表面不受污染，其本质上是被铋润湿的。某些元素在铋中的溶解被证明会引起钍盐分解产生的钍的润湿，而一些元素被证明会减少钍，随后形成ThBi2。如果满足以下关系，添加元素E的液态铋中的钍悬浮液是稳定的:−ΔGox(C)<−ΔGox(E)<−ΔGox(Al)。

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引用次数: 4

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30022-5

C.M. Nicholls

引用次数: 0

Temperature Distributions In Cylindrical Plain-Canned Fuel Elements Under Some Transient Conditions 一些瞬态条件下圆柱形普通罐装燃料元件的温度分布

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30018-3

R.E. Strickland, M. Angelopoulos

Two critical requirements in the design and operation of natural uranium reactors are the maintenance at all times of the maximum fuel temperature below 600°C, the phase change value and the limiting of the temperature of the can to a value such that its strength and corrosion-resistance properties are adequate. It is necessary, therefore, to examine temperature distributions in the fuel and can under possible significant transient conditions. Three such conditions are numerically examined using the experimental heat transfer data of HUGHES and SLACK (1958). In two cases, the temperature response to a step change in flux and to a typical flux control disturbance, the results show the time-lag effect due to the dominant time constant which has a characteristic value for each fuel-plus-can system. In the third case, the maximum temperature reached during fuel element charging under load is examined.

设计和运行天然铀反应堆的两个关键要求是始终保持最高燃料温度低于600°C，相变值和将罐的温度限制在足以使其强度和耐腐蚀性能的值。因此，有必要在可能出现的重大瞬态条件下检查燃料和燃料中的温度分布。利用HUGHES和SLACK(1958)的实验传热数据对这三种条件进行了数值检验。在两种情况下，温度对流量阶跃变化的响应和对典型流量控制扰动的响应，结果表明，由于占主导地位的时间常数对每个燃料加罐系统都有一个特征值，因此存在时滞效应。在第三种情况下，检查了燃料元件在负载下充电时达到的最高温度。

引用次数: 0

Losses Incurred in Turning a Gas Flowing in an Annular Duct Back into the Central Tube 将在环形管道中流动的气体转回中心管所造成的损失

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30020-1

F. Cheers

Tests have been carried out to determine the effect of the geometrical arrangement on the losses incurred in turning a fluid from an annular duct back into the central passage. It is shown that if the layout is well chosen, the losses need not be much greater than those for a sudden contraction of the same area ratio.

已经进行了试验，以确定几何布置对将流体从环形管道转回中央通道所产生的损失的影响。结果表明，如果布局选择得当，其损失不必比相同面积比的突然收缩大很多。

引用次数: 0

Calculation of the thermal conductivity of molten metals 熔融金属导热系数的计算

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30025-0

G.F. Butenko, M.I. Radchenko

引用次数: 0

Critical heat fluxes for water flowing in tubes 水在管内流动的临界热流密度

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30024-9

I.T. Aladiev, L.D. Dodonov, V.S. Udalov

引用次数: 0

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30023-7

L.C. Widdoes

引用次数: 0

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30021-3

H.H. Yoshikawa

引用次数: 0

A Pulsed Reactor 脉冲反应堆

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30026-2

T.N. Zubarev

The design of a pulsed reactor using ordinary water and enriched uranium is presented together with a method of computing the physical and thermal parameters. Very stable heat production during the neutron bursts can be ensured, provided certain conditions are fulfilled. Calculations show that the suggested design can provide a thermal power of ≳5 MW with a mean neutron flux in the core ≳ 10¹⁴ neutrons.cm⁻². sec⁻¹ and a peak flux during the burst of about 10¹⁷ neutrons.cm⁻².sec⁻¹.

介绍了一种以普通水和浓缩铀为原料的脉冲堆的设计，并给出了物理和热参数的计算方法。在满足一定条件的情况下，可以保证中子爆炸过程中产生非常稳定的热。计算表明，该设计可提供约5 MW的热功率，核心平均中子通量约为1014 neutron .cm - 2。在爆发期间的峰值通量约为1017个中子。cm−2.sec−1。

引用次数: 2

Contact Angles between Liquid Bismuth and Pure Iron and Mild Steel. A Study of Interfacial Reactions 液态铋与纯铁和低碳钢的接触角。界面反应的研究

Journal of Nuclear Energy. Part B. Reactor Technology

Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30017-1

D.H. Kerridge , S.D. Ford

The receding and advancing contact angles between liquid bismuth and pure iron and mild steel have been measured and the change of contact angle with time at a series of temperatures has been determined. Two chemical reactions have been found to take place at the solid-liquid interface. The first is thought to be the reaction of chloride ions (present as bismuth oxychloride impurity in the solution) with the iron surface; the second the reduction of bismuthyl ions by the iron. The first process has an activation energy of 30 kcal and the second process an activation energy of 15 kcal.

测定了液态铋与纯铁和低碳钢之间的后退接触角和前进接触角，并测定了在一系列温度下接触角随时间的变化。在固液界面上发现了两种化学反应。第一种被认为是氯离子(在溶液中以氯化铋氧杂质的形式存在)与铁表面的反应;第二种是铋离子被铁还原。第一方法的活化能为30千卡，第二方法的活化能为15千卡。

引用次数: 0

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