先进核能系统设计分析软件与数据库研发进展

参照聚变系统设计研究而获得的实际需求,FDS团队基于现代信息技术发展了一系列先进核能系统设计分析软件与数据库,包括自动建模、物理与工程计算、虚拟仿真与可视化、系统工程与安全分析、数据库及其管理软件等。通过这些软件的发展,促进核科学技术和信息技术学科的深度交叉,探索发展核信息学与技术的途径。本文简要介绍团队开发的各种设计与分析软件的基本发展思路、主要功能与特点、涉及的关键算法与技术以及实际测试与应用情况。     

关于先进核能系统的经济性

从中子经济性角度对不同先进核能系统的嬗变（或增殖）经济性作初步分析和比较     

关于先进核能系统的嬗变能力

就中子经济性对不同类型先进核能系统的嬗变能力进行初步分析和比较。     

散裂中子源与先进核能系统

散裂中子源的应用日益受到人们的重视。本报告仅对散裂中子源的历史、物理基础、对加速器要求、靶系统及其应用于先进核能系统作一般介绍。     

加速器驱动先进核能系统及其研究进展

针对现有商业反应堆核燃料利用效率低和乏燃料安全处置难等问题,中国科学院原创性地提出了加速器驱动先进核能系统（ADANES）的概念。对ADANES进行了初步物理研究,对超导直线加速器、高功率散裂靶、堆芯结构材料、乏燃料处理和新型燃料制备等进行了大规模前期计算与关键参数实验,论证了系统的可行性。目前,加速器驱动嬗变研究装置已得到“十二五”国家重大科技基础设施的支持,计划于2019年动工。     

先进核能技术发展与展望

核能作为清洁、低碳、安全、高效的基荷能源,在应对全球气候变化中起到积极的正面作用。福岛核事故后,国际社会对核能安全性提出了新的、更高的要求;同时在开放的电力市场环境中,核能的大力发展又受制于经济性和环保等方面的因素。世界核能界正探索和开发新一代先进核能技术,以期解决核能发展的相关问题。本文调研了国际组织和主要核能强国的先进核能技术的发展情况,介绍我国先进核能技术的发展,浅析未来先进核能技术的发展趋势、重点发展方向和共性技术。     

315中子/42光子耦合细群核数据库HENDL3.0/FG研发

为了提高次临界堆(含热裂变包层)核分析的精度,设计开发了315群中子-42群光子耦合的细群核数据库HENDL3.0/FG (Fine-Group).评价核数据来源主要选用美国核数据中心公布的ENDF/B-Ⅶ.0库.利用蒙特卡罗粒子输运程序MCNP以及FDS团队自主研发的大型集成中子学计算分析系统VisualBUS程序进...     

高放废物的嬗变处置与不产生长寿命高放废物的先进核能系统

评述了近年来国际上比较关注的通过嬗变处置高放废物（ＨＬＷ）的方向和９０年代初进一步提出的不产生长寿命高放废物的先进核能系统概念，并对我国今后开展这方面工作提出了意见。     

先进钍基核能系统非能动慢化剂余热排出系统概念设计

简述了CANDU9、AP600和PIUS等核能系统余热排出系统的特点,并对它们的优缺点进行了综合评价,在此基础上提出了先进钍基核能系统（TANES）非能动慢化剂余热排出（PMRHR）系统的概念设计方案。对所提设计方案的性能特点进行了分析,并对完成设计的关键问题进行了阐述。     

混合评价核数据库HENDL1.0的研制与基准检验

为满足聚变 裂变次临界混合堆设计和其他相关研究的需要 ,以世界几个主要基本评价核数据库为数据来源 ,通过优选建立了名为HENDL1 .0 /E的多用途核数据库 ,采用国际通行的核数据库处理程序系统NJOY和TRANSX等程序制作了相应的工作数据库 ,其中包括多能群输运截面库HENDL1 .0 /MG、连续能量点状输运截面库HENDL1 .0 /MC、燃耗数据库HENDL1 .0 /BU和响应函数库HENDL1 .0 /RF ,利用世界上流行的中子输运程序对已有的一系列基准检验实验进行模拟计算和比较分析以检验混合库HENDL1 .0的正确性和有效性。     

Japanese Evaluated Nuclear Data Library (JENDL)

Three versions of Japanese Evaluated Nuclear Data Library (JENDL) are briefly explained. The first version, JENDL-1, was made aiming mainly at application to fast reactors. The second version, JENDL-2, was built as a bigger general purpose evaluated nuclear data library. It stores nuclear data for 181 nuclides. It has, however, some drawbacks particularly for fusion neutronics calculation. To remove these drawbacks of JENDL-2 and further extend its applicability, the third version, JENDL-3, has now been made. JENDL-3 includes photon-production data for some nuclides, in addition to the data contained in JENDL-2.     

更新的中国评价核参数库(CENPL-2)

发展了为核反应模型计算用的中国评价核参数库（CENPL）。国际原子能机构通过国际合作组装了一个为核反应数据模型计算用的推荐输入参数库（RIPL），CENPL的全部数据文档选作RIPL的起始文档，而由本工作组估算和推荐的主要模型参数选为RIPL的推荐模型参数。目前，正在研制更新的CENPL（CENPL－2），一方面，数据被检验、更新和扩充，特别注重研究适用于更高能区和非稳定核区的核模型理论计算的模型参数；另一方面，发展CENP的检索软件和网络软件，以实现网络在线服务。     

Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2

The revision work of JENDL-3 has been made by considering feedback information of various benchmark tests. The main revised quantities are the resonance parameters, capture and inelastic scattering cross sections, and fission spectra of main actinide nuclides, the total and inelastic scattering cross sections of structural materials, the resonance parameters the capture and inelastic scattering cross sections of fission products, and the γr-ray production data. The revised data were released as JENDL-3.2 in June 1994. The preliminary benchmark tests indicate that JENDL-3.2 predicts various reactor characteristics more successfully than the previous version of JENDL-3.1.     

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3

Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for ²³⁵U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL- 3.2.     

Development of a 1200 fine group nuclear data library for advanced nuclear systems

Accurate and reliable nuclear data libraries are essential for calculation and design of advanced nuclear systems.A 1200 fine group nuclear data library Hybrid Evaluated Nuclear Data Library/Fine Group (HENDL/FG) with neutrons of up to 150 MeV has been developed to improve the accuracy of neutronics calculations and analysis.Corrections of Doppler,resonance self-shielding,and thermal upscatter effects were done for HENDL/FG.Shielding and critical safety benchmarks were performed to test the accuracy and reliability of the library.The discrepancy between calculated and measured nuclear parameters fell into a reasonable range.     

先进堆非能动余热排出系统应对全厂断电事故的能力分析

采用RELAP5/MOD程序对先进堆全厂断电事故进行分析计算,论证非能动余热排出系统对事故的缓解能力.分析表明,先进堆在发生全厂断电事故后,完全能够依靠非能动余热排出系统导出堆芯余热,保证反应堆的安全;先进堆非能动余热排出系统的设计总体上是成功的.     

Development of Nuclear Safety Information Retrieval System

An on-line information retrieval system for quickly analyzing safety-related informations in nuclear power plants has been developed. By analyzing and evaluating the operating experience/failure reports it is shown that the system is a convenient tool in considering to have the availability of nuclear plants increased. The system may also be used for a variety of purposes. For example, it is useful as a data base for evaluation of the component reliability or for taking measures to meet the various failure situation of the nuclear plants.     

Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems

The isotopic composition of spent nuclear fuels is vital data for studies on the nuclear fuel cycle and reactor physics. The Japan Atomic Energy Agency (JAEA) has been active in obtaining such data for pressurized water reactor (PWR) and boiling water reactor (BWR) fuels, and some data has already been published. These data have been registered with the international Spent Fuel Isotopic Composition Database (SFCOMPO) and widely used as international benchmarks for burnup calculation codes and libraries.     

核设施流出物数据模型及其应用

核设施放射性流出物数据是核安全监管和应急管理的重要依据之一。XML技术是实现统一流出物数据交换规范的有效工具,有利于数据的汇总、统计和分析,强化对流出物监管的时效性。本文首先介绍了XML概念、流出物数据建模方法的选择,然后着重介绍了流出物模型建立的过程,最后展示了建立的模型以及应用情况。