Simulation study on 232Th-233U conversion in thermal reactors

ZHANG Haiqing; LIN Jun; CAO Changqing; ZHU Tianbao; ZHU Zhiyong

doi:10.11889/j.0253-3219.2015.hjs.38.050601

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Simulation study on 232Th-233U conversion in thermal reactors

更新时间：2021-03-03

- Simulation study on 232Th-233U conversion in thermal reactors
- NUCLEAR TECHNIQUES Vol. 38, Issue 5, Article number: 050601(2015)
- 作者机构：
  
  中国科学院上海应用物理研究所嘉定园区,上海,201800
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2015.hjs.38.050601
  CLC：
- Published：08 May 2015
- 稿件说明：
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ZHANG Haiqing, LIN Jun, CAO Changqing, et al. Simulation study on 232Th-233U conversion in thermal reactors[J]. Nuclear techniques, 2015, 38(5): 050601
DOI：

ZHANG Haiqing, LIN Jun, CAO Changqing, et al. Simulation study on 232Th-233U conversion in thermal reactors[J]. Nuclear techniques, 2015, 38(5): 050601 DOI： 10.11889/j.0253-3219.2015.hjs.38.050601.

摘要

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4×1016 n?cm?2左右；注量率相同时，能谱越硬，233U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。

Abstract

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 numerical comparison. Results: Simulation results showed that the maximum inventory of 233Th and 233Pa is irrelevant to the neutron fluency rates when neutron spectrum is fixed. When the neutron fluency rates are preset

the harder the neutron spectrum is

the larger the maximum inventory of 233U will be obtained. Multiple “irradiation-cooling” cycles can improve the conversion rate of 232Th-233U

but the relative increment is becoming smaller and smaller

compared to the continuous irradiation conversion rate. Conclusion: This work provides relevant theoretical basis for thermal reactors thorium-uranium fuel cycle research. Abstract

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