【摘要】：先進(jìn)核能系統(tǒng)的自主化堆芯物理設(shè)計(jì)需要準(zhǔn)確的核數(shù)據(jù)為基礎(chǔ),實(shí)現(xiàn)堆用重要核數(shù)據(jù)從實(shí)驗(yàn)核數(shù)據(jù)庫(kù)出發(fā),到被RMC、MCNP等反應(yīng)堆蒙特卡羅程序所使用的連續(xù)能量點(diǎn)截面數(shù)據(jù)庫(kù),需要經(jīng)過共振參數(shù)評(píng)價(jià)、共振截面重造、多普勒展寬和概率表等關(guān)鍵處理環(huán)節(jié)。其關(guān)鍵方法和程序一直被國(guó)外權(quán)威程序所壟斷,是制約我國(guó)實(shí)現(xiàn)真正自主堆芯物理設(shè)計(jì)的重要因素。本文以反應(yīng)堆用重要核數(shù)據(jù)的評(píng)價(jià)、處理和應(yīng)用等重要環(huán)節(jié)的關(guān)鍵方法為主線,在關(guān)鍵算法研究的基礎(chǔ)上,研制具有自主知識(shí)產(chǎn)權(quán)的反應(yīng)堆重要核數(shù)據(jù)的評(píng)價(jià)、處理與應(yīng)用程序系統(tǒng)。主要研究?jī)?nèi)容如下:1)研究了非線性最小二乘擬合方法,實(shí)現(xiàn)了基于最新R矩陣近似公式的共振參數(shù)評(píng)價(jià)功能,研發(fā)了共振參數(shù)評(píng)價(jià)程序RRPE。2)針對(duì)自主研發(fā)核數(shù)據(jù)處理程序RXSP的現(xiàn)有共振重造模塊CSP的功能和收斂準(zhǔn)則方面的不足,擴(kuò)展了基于該R-Matrix Limited公式的共振重造功能。3)研究了不可分辨共振能區(qū)的概率表生成方法,在RXSP程序框架中研發(fā)了概率表生成模塊PURC,研究并解決了經(jīng)典算法中的效率瓶頸,并進(jìn)行了Open MP并行加速。4)研究了溫度相關(guān)截面的快速多普勒展寬方法與RMC程序的內(nèi)耦合方法,實(shí)現(xiàn)了RMC程序的內(nèi)置多普勒展寬功能(包括熱化數(shù)據(jù)插值)。通過上述研究,本文得到了如下結(jié)論:基于Levenberg-Marquardt方法研發(fā)的共振參數(shù)評(píng)價(jià)程序RRPE的評(píng)價(jià)精度與國(guó)際權(quán)威程序SAMMY大致相當(dāng);改進(jìn)的共振重造模塊CSP能夠?qū)崿F(xiàn)R-Matrix Limited格式的共振參數(shù)處理,處理精度與NJOY(2012)相當(dāng);在改進(jìn)排序算法和并行加速處理之后,基于“Ladder Sampling”方法研發(fā)的PURC模塊能夠?qū)崿F(xiàn)準(zhǔn)確、高效生成概率表截面數(shù)據(jù);基于快速多普勒展寬和熱化截面插值的RMC程序內(nèi)置多普勒展寬功能,能夠?qū)崿F(xiàn)中子輸運(yùn)過程中的溫度相關(guān)截面的快速處理,能夠應(yīng)用在具有大量核素和大量溫度反饋的反應(yīng)堆堆芯物理-熱工水力耦合計(jì)算中。
[Abstract]:The independent core physical design of advanced nuclear power system needs accurate nuclear data to realize the important nuclear data from experimental nuclear database to continuous energy point cross section database used by RMC,MCNP and other reactor Monte Carlo programs. The key processing links, such as resonance parameter evaluation, resonance cross section reconstruction, Doppler broadening and probability table, are needed. Its key methods and procedures have always been monopolized by foreign authoritative procedures, which is an important factor restricting the realization of truly autonomous core physical design in China. On the basis of the research of key algorithms, the evaluation of important nuclear data of reactors with independent intellectual property rights is developed on the basis of the key methods of critical links such as evaluation, processing and application of important nuclear data for reactor use. Processing and application system. The main contents are as follows: 1) the nonlinear least squares fitting method is studied, and the function of resonance parameter evaluation based on the latest R-matrix approximation formula is realized. The resonance parameter evaluation program (RRPE.2) is developed, which aims at the shortcomings in the function and convergence criteria of the existing resonant reconstruction module (CSP), which independently develops the nuclear data processing program (RXSP). The resonance reconstruction function based on the R-Matrix Limited formula is extended. 3) the probability table generation method of indiscernible resonance energy region is studied, and the probability table generation module PURC, is developed in the framework of RXSP program. The efficiency bottleneck of the classical algorithm is studied and solved, and the parallel acceleration of Open MP is carried out. 4) the fast Doppler broadening method of temperature-dependent cross section and the internal coupling method of RMC program are studied. The built-in Doppler broadening function of RMC program (including thermal data interpolation) is realized. Through the above-mentioned research, this paper draws the following conclusions: the evaluation accuracy of the resonance parameter evaluation program RRPE based on the Levenberg-Marquardt method is about the same as that of the international authoritative program SAMMY; The improved resonant reconstruction module CSP can realize the processing of resonance parameters in R-Matrix Limited format, and the processing precision is equal to that of NJOY (2012). After improving the sorting algorithm and parallel accelerated processing, the PURC module based on the "Ladder Sampling" method can achieve accurate and efficient generation of probability table cross-section data. The RMC code based on fast Doppler broadening and thermal cross-section interpolation has built-in Doppler broadening function, which can realize the fast processing of temperature-dependent cross sections in neutron transport process. It can be applied to the physical-thermal-hydraulic coupling calculation of reactor core with a large number of nuclides and a large amount of temperature feedback.
【學(xué)位授予單位】：清華大學(xué)
【學(xué)位級(jí)別】：博士
【學(xué)位授予年份】：2015
【分類號(hào)】：TL351.1

【參考文獻(xiàn)】

相關(guān)期刊論文 前3條

1 余健開;李松陽(yáng);王侃;王冠博;余綱林;;反應(yīng)堆用核截面處理程序RXSP的研發(fā)與驗(yàn)證[J];核動(dòng)力工程;2013年S1期

2 李松陽(yáng);王侃;余綱林;;中子截面Doppler展寬算法及并行計(jì)算方法[J];清華大學(xué)學(xué)報(bào)(自然科學(xué)版);2012年04期

3 何小榮,丘國(guó)春;Bayes 公式在數(shù)據(jù)處理中的應(yīng)用[J];廣西大學(xué)學(xué)報(bào)(自然科學(xué)版);1998年01期

相關(guān)博士學(xué)位論文 前1條

1 李松陽(yáng);在線多普勒展寬與核截面處理方法研究[D];清華大學(xué);2012年

，

本文編號(hào)：2451377