钍基核燃料的基础研究

张家骅; 包伯荣; 夏源贤

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钍基核燃料的基础研究

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- 钍基核燃料的基础研究
- BASIC STUDY ON UTILIZATION OF THORIUM-BASED NUCLEAR FUEL
- Nuclear Techniques 1989年12卷第7期
- 作者机构：
  
  中国科学院上海原子核研究所
- 作者简介：
- 基金信息：
  
  Partly supported by IAEA
- DOI：
  中图分类号：
- 收稿日期：1989-01-30，
  
  纸质出版日期：1989-07
- 稿件说明：
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张家骅, 包伯荣, 夏源贤. 钍基核燃料的基础研究[J]. Nuclear Techniques, 1989,12(7):405-408.

Jiahua Zhang, Borong Bao, Yuanxian Xia. BASIC STUDY ON UTILIZATION OF THORIUM-BASED NUCLEAR FUEL[J]. 核技术, 1989, 12(7): 405-408.
张家骅, 包伯荣, 夏源贤. 钍基核燃料的基础研究[J]. Nuclear Techniques, 1989,12(7):405-408. DOI：

Jiahua Zhang, Borong Bao, Yuanxian Xia. BASIC STUDY ON UTILIZATION OF THORIUM-BASED NUCLEAR FUEL[J]. 核技术, 1989, 12(7): 405-408. DOI：

摘要

一系列ThO

样品在高通量堆中在不同辐照条件下进行了辐照. 在对每个样品进行冷却、溶解后

对

233

U、

232

U某些裂片与

、

之间的相关性进行了测定. 基于这些实验结果

提出了对设计一个Th-U核反应堆可能有用的某些物理参数的范围. 即: 1. 快热中子比

1; 2. 热中子通量

5×10

2.5×10

(n/cm

) ; 3.钍铀比

Th/U

80; 4. 可裂变燃料与非可裂变燃料之比

0.012

(

235

U+

233

U) / (

238

U+

232

Th)

0.03

Abstract

Four series of ThO

samples in pellet form have been irradiated in high flux reactor under various conditions. After cooling and dissolution of each sample separately

the interrelations between

233

232

233

certain fission fragment nuclides and

have been determined. Based on these experimental results

the ranges of some physical parameters which might be useful to the design of Th-U nuclear reactor have been presented. Namely

1. Ratio of fast neutron flux to thermal neutron flux

/ф

1;2. Intensity of thermal neutron flux

5×10

2.5×10

（n/cm

）; 3. Ratio of thorium to uranium

Th/U

80; 4. Ratio of fissionable fuel to non-fissionable fuel

0.012

（

235

U＋

233

U）/(

238

U+

232

Th)

0.03.

关键词

Keywords

references

IAEA Technical Committee on Utilization of Thorium-Based Nuclear Fuel : Current Status and Perspectives , Vienna, Austria , 2-4 Dec., 1985 .

Thorium fuel reactors , Proceedings of the Japan-U. S. seminar on thorium fuel reactors , Oct. 18-22, 1982 , Nara, Japan .

Assessment of thorium fuel cycles in pressurized water reactors, EPRI NP-359, Final Report February 1977 .

Zhang Jiahua et al , Chinese Journal of Nuclear Science and Engineering 6 （ 1986 ）, 2 : 192 .

THTR-300, Directory of Nuclear Reactor , IAEA , Vienna , Vol. X , 1976 , p. 305 .

Fort St. Vrain Nuclear Generating Station , ibid , Vol. IX , 1971 , p. 185 .

Consolidated Edison Thorium Reactor , ibid , Vol. Ⅳ , 1962 , p. 59 .

Peach Bottom-1 , ibid , Vol. Ⅶ 1968 , p. 251 .

Elk River Reactor , ibid , Vol. Ⅳ 1962 , p. 103 .

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