热堆中钍铀转化规律

钍铀燃料循环以其优异的物理和化学特性，受到核能界的广泛关注。本文利用单群的点燃耗计算程序ORIGEN，分别研究了钍燃料在沸水堆（Boiling Water Reactor，BWR）、压水堆（Pressurized Water Reactor,PWR）和加拿大重水铀反应堆（Canada Deuterium Oxide Uranium，CANDU，又称坎杜堆）能谱中辐照时，232Th、233Th、233Pa、233U等核素生成量随中子注量率和中子能谱的变化规律，并探索了多次“辐照-冷却”循环对钍铀转化率的影响。计算结果表明，能谱相同时，233Th和233Pa存量的最大值与注量率有关；233U存量的...

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Bibliographic Details
Published in	核技术 Vol. 38; no. 5; pp. 78 - 85
Main Author	张海青林俊曹长青朱天宝朱智勇
Format	Journal Article
Language	Chinese
Published	中国科学院上海应用物理研究所嘉定园区上海201800 2015
Subjects	中子注量率中子能谱钍铀转化率 Neutron spectrum Neutron fluence rate Conversion rate of 232Th-233U 中子注量率钍铀转化率中子能谱
Online Access	Get full text
ISSN	0253-3219
DOI	10.11889/j.0253-3219.2015.hjs.38.050601

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Summary:	钍铀燃料循环以其优异的物理和化学特性，受到核能界的广泛关注。本文利用单群的点燃耗计算程序ORIGEN，分别研究了钍燃料在沸水堆（Boiling Water Reactor，BWR）、压水堆（Pressurized Water Reactor,PWR）和加拿大重水铀反应堆（Canada Deuterium Oxide Uranium，CANDU，又称坎杜堆）能谱中辐照时，232Th、233Th、233Pa、233U等核素生成量随中子注量率和中子能谱的变化规律，并探索了多次“辐照-冷却”循环对钍铀转化率的影响。计算结果表明，能谱相同时，233Th和233Pa存量的最大值与注量率有关；233U存量的最大值与注量率无关，大概在注量（注量率×时间）为4×10^16n·cm-2左右；注量率相同时，能谱越硬，333U存量的最大值越大。采取循环“辐照-冷却”可以提高233Th-233U的转化率，对于相同的总辐照时间，每次循环周期内的辐照时间越短，相对于总辐照时间相同的单次辐照，转化率增量提高越明显；当总辐照时间超过两个月时，循环辐照对转化率增量的作用较小，与单次辐照不冷却相比，转化率相对增量不超过1倍。
Bibliography:	ZHANG Haiqing ,LIN Jun, CAO Changqing, ZHU Tianbao, ZHU Zhiyong （Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China） 31-1342/TL Neutron fluence rate; Neutron spectrum; Conversion rate of 232Th-233U Background： Thorium-uranium fuel cycle is attracting more and more attention because of its unique physical and chemical characteristics. Purpose： Realizing the utilization of thorium fuel in thermal reactors can save the valuable natural uranium resources and produce more fissile fuel, which is conducive to the nuclear energy sustainable development. Methods： ORIGEN code was used to simulate the build-up characteristics of 232Th, 233Th, 233pa and 233U in neutron fluency rates and neutron spectra of typical Boiling Water Reactor （BWR）, Pressurized Water Reactor （PWR） and Canada Deuterium Oxide Uranium （CANDU） reactor, and the effects of multiple ＂irradiation-cooling＂ cycles on the thorium uranium conversion rate under various irradiation time were analyzed by num
ISSN:	0253-3219
DOI:	10.11889/j.0253-3219.2015.hjs.38.050601