【摘要】：反應(yīng)堆堆芯溫度變化時(shí),堆內(nèi)各種材料的中子截面均隨溫度發(fā)生變化,從而引起反應(yīng)性變化。為了準(zhǔn)確模擬反應(yīng)堆內(nèi)不同溫度下中子與各種材料間的相互作用,需要生成不同溫度下的反應(yīng)截面。傳統(tǒng)在線核截面生成方法雖然避免了直接存儲(chǔ)大量核截面數(shù)據(jù),但是仍然存在嚴(yán)重的效率低下以及能區(qū)適應(yīng)性窄的問(wèn)題。本文在充分調(diào)研國(guó)內(nèi)外蒙特卡羅(簡(jiǎn)稱(chēng)蒙卡)中子輸運(yùn)中的在線核截面生成方法現(xiàn)狀基礎(chǔ)上,基于中國(guó)科學(xué)院核能安全技術(shù)研究所·FDS團(tuán)隊(duì)自主研發(fā)的超級(jí)蒙卡核模擬軟件系統(tǒng)SuperMC,根據(jù)可分辨共振能區(qū)、熱能區(qū)與不可分辨共振能區(qū)截面的特點(diǎn),開(kāi)展了蒙卡中子輸運(yùn)寬能區(qū)在線核截面生成方法研究。本文的主要研究?jī)?nèi)容與創(chuàng)新點(diǎn)包括:(1)提出了基于雙指數(shù)變換-高斯積分耦合的可分辨共振能區(qū)在線核截面生成方法。針對(duì)寬能區(qū)中可分辨共振能區(qū)截面生成耗時(shí)嚴(yán)重問(wèn)題,提出在低能區(qū)使用基于雙指數(shù)變換的在線核截面生成方法,在高能區(qū)使用基于高斯-厄米特積分的在線核截面生成方法,在保證核截面精度的同時(shí),極大地提高了截面生成效率。測(cè)試結(jié)果顯示,該方法在保證核截面生成精度的基礎(chǔ)上,與解析方法相比截面生成效率提高達(dá)12倍;國(guó)際臨界安全基準(zhǔn)例題Jezebel及Godiva等的驗(yàn)證結(jié)果證實(shí)了該方法的有效性。(2)提出了基于Neville插值的熱能區(qū)在線核截面生成方法。根據(jù)溫度相關(guān)的熱散射截面特性,提出使用Nevlle插值算法在線生成目標(biāo)溫度對(duì)應(yīng)的熱散射截面。采用國(guó)際核數(shù)據(jù)委員會(huì)發(fā)布的S(α,β)基準(zhǔn)例題等進(jìn)行測(cè)試,結(jié)果表明,在保證精度同時(shí),使用基于Neville插值的熱散射截面在線生成方法比傳統(tǒng)方法的效率提高一個(gè)數(shù)量級(jí)以上。(3)發(fā)展了基于分段線性插值的不可分辨共振能區(qū)在線核截面生成方法。該方法結(jié)合了不同溫度下概率表參數(shù)的特征,使用相鄰溫度間隔的核截面經(jīng)分段線性插值方法在線生成目標(biāo)溫度的核截面。國(guó)際快堆堆芯模型bigtenl及bigten2等測(cè)試結(jié)果表明,該方法與基準(zhǔn)值的偏差小于20pcm,證明了方法的準(zhǔn)確性。為了驗(yàn)證本文提出的寬能區(qū)在線核截面生成方法的準(zhǔn)確性和有效性,采用國(guó)際臨界安全基準(zhǔn)例題、反應(yīng)性多普勒系數(shù)基準(zhǔn)例題與IAEA BN-600基準(zhǔn)例題等進(jìn)行了綜合驗(yàn)證。通過(guò)與傳統(tǒng)核截面生成方法與基準(zhǔn)值進(jìn)行對(duì)比,結(jié)果表明本文發(fā)展的蒙特卡羅中子輸運(yùn)在線核截面生成方法能夠準(zhǔn)確高效地生成各種溫度下的中子截面,可用于反應(yīng)堆多物理耦合計(jì)算。
[Abstract]:When the reactor core temperature changes, the neutron cross section of various materials in the reactor varies with the temperature, which causes the reactivity change. In order to accurately simulate the interaction between neutrons and various materials at different temperatures in the reactor, reaction cross sections at different temperatures should be generated. Although the traditional on-line generation method avoids storing a large number of nuclear cross-section data directly, there are still serious problems such as low efficiency and narrow energy region adaptability. In this paper, based on the investigation of the present situation of on-line nuclear cross section generation in Monte Carlo neutron transport at home and abroad, Based on the characteristics of the super Monka nuclear simulation software system SuperMC, developed by the FDS team of the Institute of Nuclear Safety Technology of the Chinese Academy of Sciences, according to the cross sections of the distinguishable resonance energy region, the thermal energy region and the indistinguishable resonance energy region, In this paper, the method of generation of nuclear cross section in the wide energy region of neutron transport in Monka is studied. The main research contents and innovations in this paper are as follows: (1) an on-line generation method of discernible resonance energy region core cross-section based on double exponential transformation and Gao Si integral coupling is proposed. In order to solve the problem of time-consuming generation of the visible resonance cross section in the wide energy region, an on-line generation method based on double exponential transformation is proposed in the low energy region and an on-line generation method based on Gauss Hermitt integral in the high energy region. At the same time, the accuracy of the core section is guaranteed, and the efficiency of section generation is greatly improved. The test results show that the efficiency of cross section generation is 12 times higher than that of analytical method on the basis of ensuring the generation accuracy of the core section. The validity of the proposed method is verified by Jezebel and Godiva. (2) an on-line generation method of thermal energy region nuclear cross section based on Neville interpolation is proposed. According to the characteristic of the temperature dependent heat scattering cross section, the Nevlle interpolation algorithm is proposed to generate the heat scattering cross section corresponding to the target temperature online. Using the S (偽, 尾) benchmark and other examples issued by the International Nuclear data Commission, the results show that, at the same time, the accuracy is guaranteed, The on-line generation method of heat scattering cross section based on Neville interpolation is more than one order of magnitude higher than that of the traditional method. (3) the method of generation of core cross section in the indiscernible resonance energy region based on piecewise linear interpolation is developed. Based on the characteristics of probability table parameters at different temperatures, the kernel cross-section of the adjacent temperature interval is generated online by piecewise linear interpolation. The test results of bigtenl and bigten2 show that the deviation between the method and the reference value is less than 20pcmwhich proves the accuracy of the method. In order to verify the accuracy and effectiveness of the method proposed in this paper, the international critical safety benchmark, the reactive Doppler coefficient benchmark and the IAEA BN-600 benchmark are used to verify the accuracy and effectiveness of the proposed method. Compared with the conventional nuclear cross section generation method and the reference value, the results show that the Monte Carlo neutron transport on-line nuclear cross section generation method developed in this paper can accurately and efficiently generate neutron cross sections at various temperatures. It can be used for reactor multi-physical coupling calculation.
【學(xué)位授予單位】：中國(guó)科學(xué)技術(shù)大學(xué)
【學(xué)位級(jí)別】：博士
【學(xué)位授予年份】：2017
【分類(lèi)號(hào)】：TL329

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