Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology最新文献_第7页

Atomnaya energiya contents and abstracts of vol. 20, no. 3 《原子能源》第20卷目录和摘要。3.

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90165-0

引用次数: 0

Accident and self-regulation studies of pulsed fast reactors 脉冲快堆的事故与自我调节研究

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90155-8

J. Randles

{"title":"Accident and self-regulation studies of pulsed fast reactors","authors":"J. Randles","doi":"10.1016/0368-3230(66)90155-8","DOIUrl":"10.1016/0368-3230(66)90155-8","url":null,"abstract":"<div>A previously developed theory of pulsed fast reactor kinetics, inclusive of feedback effects, is reduced to a simple form and a standard method is applied to obtain a numerical description of pulsed excursions. This method is embodied in a fortran computer programme which executes the arithmetic for any desired number of cases and presents all physical variables of interest as a function of the time during a pulse. The main qualitative ideas underlying the theory are illustrated by numerical examples, in particular, the competition for dominance between a prompt positive Doppler and delayed axial thermal fuel expansion effect and the excitation of elastic waves in the fuel slugs are both brought out clearly.It is shown that, in accident conditions, a fast pulsed reactor similar to the proposed Euratom system sora possesses a strong net negative feedback which makes the system self-regulating with respect to the fuel temperature, but that such feedback does not appreciably raise the reactivity pulse amplitudes responsible for serious damage. The effect of drifts in the base reactivity is discussed and the reaction of the safety shutdown system is considered. It is concluded that systems similar to the sora reactor have to be designed so that all possible drifts are far below 2 % Δk/sec.In connexion with the general question of the choice of the fuel material for a pulsed fast reactor, it is shown that, from the safety viewpoint, the value of the coefficient of thermal expansion of the fuel can be ignored. Thus, all other things being equal, a ceramic is as good as a metallic fuel.</div>","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 9","pages":"Pages 713-728"},"PeriodicalIF":0.0,"publicationDate":"1966-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90155-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89098459","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Non-elastic interaction cross sections of neutrons with 7Li, 12C, 14N, 27Al, 56Fe, Cu, Pb, 235U, 238U and 239Pu 中子与7Li、12C、14N、27Al、56Fe、Cu、Pb、235U、238U和239Pu的非弹性相互作用截面

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90164-9

Yu.G. Degtyarev

引用次数: 1

Atomnaya energiya contents and abstracts of vol. 20, no. 4 《原子能源》第20卷目录和摘要。4

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90166-2

引用次数: 0

A review of pebble bed reactors and the characteristics of packed beds 球床反应器的研究进展及填料床的特点

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90157-1

K.T. Claxton

{"title":"A review of pebble bed reactors and the characteristics of packed beds","authors":"K.T. Claxton","doi":"10.1016/0368-3230(66)90157-1","DOIUrl":"10.1016/0368-3230(66)90157-1","url":null,"abstract":"<div>This paper gives a general picture of the pebble bed reactor concept up to the present time. The main advantages and disadvantages are listed, these being chiefly concerned with the rather unique spherical fuel element.The principal performance and design data etc. are given for an experimental pebble bed reactor and power plant as conceived by the Oak Ridge design team. Also included are data and a description of the BBC-Krupp reactor (AVR) of the pebble bed type under construction at Julich in West Germany; mention is also made of a possible West German pebble bed power reactor (THTR). An account is given of the Australian work on pebble bed reactors which differs from all others in the choice of support material for the fuel.A more detailed account follows of three important aspects of this reactor type—fuel elements, coolant contamination and fuel handling. This is followed by sections on the heat transfer and fluid dynamic characteristics of packed beds, of which the pebble bed reactor is an example.In conclusion some of the principal research and development problems associated with this reactor concept are discussed.An Appendix summarizes the various pebble bed reactors conceived since the original conceptual design by Farrington Daniels in 1944.</div>","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 9","pages":"Pages 735-777"},"PeriodicalIF":0.0,"publicationDate":"1966-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90157-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75878910","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 3

Stability of coupled core reactors by the second method of Liapunov 用Liapunov第二方法研究耦合堆芯的稳定性

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90156-X

H.S. Murray, D.G. Schultz, L.E. Weaver

引用次数: 2

Spheroidal reactor analysis 球形反应堆分析

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90159-5

Tien-Chen Liu, Chung-Ching Liu, Ji-Peng Chien

引用次数: 0

Study of the possibility of using thorium in fast power reactors 在快堆中使用钍的可能性研究

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90161-3

A.I. Leipunskii, O.D. Kazachkovskii, S.B. Shikhov, V.M. Murogov

引用次数: 0

Relationship between the separation factor during isotopic exchange and the properties of the exchanging molecules 同位素交换分离因子与交换分子性质的关系

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90160-1

A.M. Rozen, A.I. Mikhailichenko

引用次数: 0

The pile-neutron burn-up cross section of 149Pm and samarium poisoning 149Pm堆-中子燃烧截面与钐中毒

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI: 10.1016/0368-3230(66)90163-7

I.A. Kondurov, L.M. Gracheva, A.I. Egorov, D.M. Kaminker, A.M. Nikitin, Yu.V. Petrov

引用次数: 0