Annals of Nuclear Science and Engineering最新文献

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Annals of Nuclear Science and Engineering

Pub Date : 1974-06-01 DOI: 10.1016/S0302-2927(74)80010-3

M.R. Hawkesworth

引用次数: 0

An analysis of in-core flux and temperature data for the evaluation of the performance of an operating reactor 用于评价运行反应堆性能的堆芯内通量和温度数据分析

Annals of Nuclear Science and Engineering

Pub Date : 1974-06-01 DOI: 10.1016/S0302-2927(74)80005-X

H. Fenech, W.G. Flournoy, P.K. Shen

A method of analysis of in-core flux measurements for nuclear reactors is presented. By appropriate data processing, the method determines separately the statistical and deterministic errors present in the measurement. Those errors are carried throughout the analysis for determination of the local power produced, the nuclear hot channel factor F_ΔH^N and the DNB ratio with a required confidence level. An application of the method is given using the flux measurement data obtained for the first core cycle at San Onofre Unit 1. In addition, the method is extended to the processing of the recorded data from in-core thermocouples to obtain the engineering hot channel factors F_ΔH^E and the coolant by-pass fraction. The results of this analysis stresses the importance of accurate processing of nuclear reactor in-core data. Valuable estimates can be made of the core flow distribution and the flow by-pass fraction. These estimates, however, require in-core and loop temperature measurements within an accuracy of ±0·2°F for a corresponding accuracy of 5 per cent on the by-pass flow fraction. This accuracy on temperature measurement is not presently obtainable but should be set as a goal for future pressurised water reactor instrumentation performances.

Accurate knowledge of the power and flow distributions under normal operating conditions does contribute significantly to the safe operation of nuclear power stations. In the selection of in-core instrumentation and its degree of sophistication such an advantage must be considered in the overall economic balance of the plant.

提出了一种核反应堆堆芯内通量测量的分析方法。通过适当的数据处理，该方法分别确定测量中存在的统计误差和确定性误差。这些误差贯穿于整个分析，以确定产生的局部功率、核热通道因子FΔHN和DNB比率，并具有所需的置信度。以圣奥诺弗雷1号机组第一次堆芯循环的通量测量数据为例，给出了该方法的应用。此外，将该方法扩展到对堆芯内热电偶记录数据的处理，以获得工程热通道因子FΔHE和冷却剂旁通分数。这一分析结果强调了准确处理核反应堆堆芯数据的重要性。可以对岩心的流动分布和分流率作出有价值的估计。然而，这些估计需要在±0.2°F的精度范围内进行芯内和环路温度测量，以获得旁通流量分数5%的相应精度。这种温度测量精度目前还无法实现，但应作为未来压水堆仪器性能的目标。准确了解正常运行条件下的功率和流量分布对核电站的安全运行具有重要意义。在选择堆芯内仪表及其复杂程度时，必须在电厂的整体经济平衡中考虑这种优势。

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引用次数: 0

Annals of Nuclear Science and Engineering

Pub Date : 1974-06-01 DOI: 10.1016/S0302-2927(74)80011-5

Raymond L. Murray (Head)

引用次数: 0

v¯p Measurements for 239Pu below 2 MeV 2mev以下239Pu的测量值

Annals of Nuclear Science and Engineering

Pub Date : 1974-06-01 DOI: 10.1016/S0302-2927(74)80001-2

R.L. Walsh, J.W. Boldeman

The large liquid scintillator method has been used to measure the energy dependence of ${\bar{v}}_{p}$ for ²³⁹Pu below 2 MeV. No fine structure in the low energy region was observed. An analysis of all existing ²³⁹Pu ${\bar{v}}_{p}$ data below 5 MeV suggests a two-line energy dependence with a change of slope at about 800 keV.

用大液体闪烁体法测量了2mev以下239Pu的v¯p的能量依赖性。在低能区未观察到精细结构。对所有现有的低于5 MeV的239Pu v¯p数据的分析表明，在约800 keV处斜率变化的两条线能量依赖关系。

引用次数: 6

Pulsed-neutron decay measurements on BeO systems in the vicinity of the continuum bound 连续界附近BeO系统的脉冲中子衰减测量

Annals of Nuclear Science and Engineering

Pub Date : 1974-06-01 DOI: 10.1016/S0302-2927(74)80004-8

M. Sohrabpour, S.R. Bull

Decay constants have been measured in BeO systems in the buckling range 0·0167–0·0342 cm⁻². The corresponding decay constants range from below the constant collision frequency limit, λ*, to values above the elastic continuum bound, λ_el. A range of λ_el(B²) has been determined experimentally and the results are compared with calculated values based on cross-section data generated by the GASKET code.

在0·0167 ~ 0·0342 cm−2的屈曲范围内测量了BeO体系的衰减常数。相应的衰减常数范围从低于恒定碰撞频率极限λ*到高于弹性连续界λel。实验确定了λel(B2)的范围，并与基于GASKET规范生成的截面数据的计算值进行了比较。

引用次数: 1

Annals of Nuclear Science and Engineering

Pub Date : 1974-06-01 DOI: 10.1016/S0302-2927(74)80008-5

W.J. French

引用次数: 0

About differential albedo of 137Cs gamma rays 137Cs射线的微分反照率

Annals of Nuclear Science and Engineering

Pub Date : 1974-06-01 DOI: 10.1016/S0302-2927(74)80006-1

D.B. Pozdneyev

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 : 1974-06-01 DOI: 10.1016/S0302-2927(74)80012-7

引用次数: 0

Management of high level radioactive wastes 高放射性废物的管理

Annals of Nuclear Science and Engineering

Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90013-0

J.R. Grover

Many groups of workers throughout the world are considering possible methods of storage or disposal of high level fission product wastes. It is the view of the United Kingdom that these wastes must be fixed in solids and must be retrievable, that is they should be stored and not disposed of. Mankind can plan ahead for a hundred years with a reasonable degree of safety, it is doubtful whether he can anticipate or plan ahead for a thousand years, and it is quite unrealistic to consider any non-retrievable disposal for periods as long as 10⁵ yr, which is a quite incomprehensible period of time.

全世界许多工人团体正在考虑储存或处置高水平裂变产物废料的可能方法。联合王国认为，这些废物必须固定在固体中，并且必须是可回收的，也就是说，它们应该被储存起来，而不是被处理掉。人类可以在合理的安全程度上提前计划一百年，但能否预测或提前计划一千年是值得怀疑的，而在长达105年的时间里考虑任何不可回收的处置是非常不现实的，这是一段相当不可理解的时间。

引用次数: 9

A condensed schedule for energy-resource development 浓缩的能源开发计划

Annals of Nuclear Science and Engineering

Pub Date : 1974-05-01 DOI: 10.1016/0302-2927(74)90015-4

S.S. Penner

A priority list is developed for large-scale implementation, prototype or pilot plant development, and supporting research, which has the following twin objectives: (i) minimization of the impact of embargoes on foreign fossil-fuel shipments to the United States and (ii) the speediest possible conversion to an abundant energy technology without the use of fossil fuels.

为大规模实施、原型厂或试验厂开发和支持性研究制定了一份优先清单，其中有以下两个目标:(1)尽量减少对美国的外国化石燃料禁运的影响;(2)在不使用化石燃料的情况下尽可能迅速地转换为丰富的能源技术。

引用次数: 1

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