The energy release from fission products

A. Tobias
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引用次数: 10

Abstract

A simple method has been used to estimate mean beta and gamma decay energies of the short lived fission products, for which only half-life measurements and total decay energy estimates are available. This has enabled calculations to be made of beta and gamma decay heating from fission products which are in agreement with experimental results to better than 10 per cent for decay times as short as 1 s. Calculated beta and gamma decay energy following a long irradiation of 335U (thermal fission), is found to reproduce to better than 3 per cent a currently accepted curve of beta + gamma decay energy (SHURE, 1961) following an infinite irradiation of 235U, for decay times 1 ≤ t ≤ 108 s. These calculations also gave values B (∞, 0)=6·60 Me/fission, G (∞, 0)=6·56 Me/fission, D (∞, 0)=21·44 Me/fissionfor the total beta, gamma and total kinetic energy release respectively, from thermal neutron fission of 235U. A study of the calculations of ENGLAND (1970) and comparisons made, do not support his suggestion that the data of SHURE (1961), which is widely used in industry, underestimates beta + gamma decay energy by ∼ 20 per cent. This suggestion would have serious implications on reactor design criteria; however, it is implied on the basis of comparisons presented in this paper, that the results of ENGLAND (1970) over-estimate by ∼ 15–20 per cent the beta + gamma decay energy following fission for decay times 10 < t ≤ 106 s.

Therefore the results of the present work reject the idea, implicit in the results of ENGLAND'S calculations, that reactor systems have been underdesigned with respect to decay heat removal.

In addition, the present calculations show that the code FISP, together with its data library, provide a reliable means of estimating fission product decay energy release at all decay times after fission.

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裂变产物释放的能量
用一种简单的方法来估计短寿命裂变产物的平均衰变能量和γ衰变能量,其中只有半衰期测量和总衰变能量估计可用。这使得从裂变产物中产生的β和γ衰变加热的计算结果与实验结果一致,在衰变时间短至15秒的情况下,其结果优于10%。经过长时间的335U(热裂变)辐照后计算出的β和γ衰变能量,在235U无限辐照后的β + γ衰变能量曲线(SHURE, 1961)中,衰变时间为1≤t≤108 s,其再现率优于3%。计算还得出235U热中子裂变总释放的β、γ和总动能分别为B(∞,0)=6·60 Me/裂变、G(∞,0)=6·56 Me/裂变、D(∞,0)=21·44 Me/裂变。对ENGLAND(1970)的计算和所作的比较的研究不支持他的建议,即广泛用于工业的SHURE(1961)的数据低估了β + γ衰变能量约20%。这一建议将对反应堆设计标准产生严重影响;然而,在本文提出的比较的基础上暗示,英格兰(1970)的结果高估了裂变后衰变次数为10 <的β + γ衰变能量约15 - 20%;T≤106 s。因此,目前工作的结果否定了英格兰计算结果中隐含的想法,即反应堆系统在衰变热去除方面设计不足。此外,本文的计算表明,FISP程序及其数据库提供了一种可靠的方法来估计裂变后所有衰变时间的裂变产物衰变能量释放。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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The neutron yield from Li, Be, Co and Cu under proton bombardment at energies from 5 to 10 MeV The emission spectra of NaD2O, InBe, LaBe and NaBe photoneutron sources Neptunium-237 production and recovery An exact solution of a transcendental equation basic to the theory of intermediate resonance absorption of neutrons Mathematical theory of transport processes in gasesJ. H. Ferziger and H. G. Kaper, North Holland, Amsterdam (1972). pp. 579
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