NEXUS – A New Nuclear Data System for PWR and BWR CoreSimulators

机译：NEXUS –用于压水堆和压水堆堆芯模拟器的新型核数据系统

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This paper presents an overview of NEXUS, a newnuclear data system which is being developed forlight water core analysis by Westinghouse ElectricCo. with its partners Mitsubishi Heavy Industries(MHI), and the Korean Nuclear Fuel Co. (KNFC).This nuclear data system is being implemented withtwo Westinghouse core simulators: ANC (Liu, 1985)for PWR cores and POLCA7 (Lindahl, 1995) forBWR cores. The paper presents a description of themethods developed and implemented in NEXUS, thecomputer codes which make up the system, theNEXUS system data, and the effort currentlyunderway to qualify NEXUS for use in light waterreactor design and safety analyses. In addition, someresults from this qualification are presented whichdemonstrate the accuracy of NEXUS for representingcross section data.

机译：本文介绍了NEXUS的概况，NEXUS是一种新的核数据系统，正在由西屋电气公司开发，用于轻水芯分析。与它的合作伙伴三菱重工（MHI）和韩国核燃料公司（KNFC）一起使用两个西屋核心仿真器来实现该核数据系统：用于压水堆芯的ANC（Liu，1985）和用于压水堆的POLCA7（Lindahl，1995）。核心。本文介绍了在NEXUS中开发和实施的方法，构成系统的计算机代码，NEXUS系统数据以及目前正在努力使NEXUS可以用于轻水反应器设计和安全性分析的工作。此外，还提供了此鉴定的一些结果，这些结果证明了NEXUS表示横截面数据的准确性。

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来源
《International Conference on Nuclear Engineering: Abstracts》|2005年|1-7|共7页
会议地点 Beijing(CN)
作者
Baocheng Zhang; Chang. J. Hah; Erwin Müller; Mayhue, Larry T.; Daisuke Sato; Chao, Y. A.;
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Westinghouse Electric CompanyNuclear FuelP. O. Box 355Pittsburgh PA 15230-0355 USAPhone: +1 (412) 374-3858Email: zhangb@westinghouse.com;

Korean Nuclear Fuel CompanyTuejon KoreaPhone: 042 868 1471Email: cjhah@knfc.co.kr;

Westinghouse Electric CompanyNuclear Fuel Business UnitSE-721 63 V?ster?s SwedenPhone: +46 21 347889Email: erwin.muller@se.westinghouse.com;

Westinghouse Electric CompanyNuclear FuelPost Office Box 355Pittsburgh PA 15230-0355 USAPhone: +1 (412) 374-2745Email: mayhuelt@westinghouse.com;

Mitsubishi Heavy Industries Ltd.3-1 Minatomirai 3-Chome Nishi-kuYokohama 220-8401 JapanPhone: +81 45 224 9607Email: dsato@atom.hq.mhi.co.jp;

Westinghouse Electric CompanyNuclear Fuel29 Hong Cao RoadShanghai China 200233Phone: 86-21-648522;

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Westinghouse; code system; cross section; NEXUS; nuclear data;

机译：西屋代码系统；横截面;关系;核数据;

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1. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part Ⅰ: SETs, and ITFs of PWRs, BWRs, VVERs [J] . Aksan N. Nuclear Engineering and Design . 2019,第Deca期

机译：水冷核反应堆热工现象概述；
2. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part Ⅰ: SETs, and ITFs of PWRs, BWRs, VVERs [J] . Aksan N. Nuclear Engineering and Design . 2019,第DECa期

机译：水冷核反应堆热工现象概述；第一部分：PWR，BWR，VVER的SET和ITF
3. Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction [J] . Gonzalez-Robles E., Serrano-Purroy D., Sureda R., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2015,第Null期

机译：在氧化条件下，商用压水堆（52 MWd / kgU）和压水堆（53 MWd / kgU）的废核燃料包覆段在碳酸氢盐水中的溶解实验。基质和速释成分的实验测定
4. NEXUS – A New Nuclear Data System for PWR and BWR Core Simulators [C] . . 2005

机译：NEXUS –用于压水堆和压水堆堆芯模拟器的新型核数据系统
5. A word nexus for systematic interoperation of semantically heterogeneous data sources. [D] . Jannink, Jan Frederic. 2001

机译：语义异构数据源的系统互操作的词联系。
6. Data from calorimetric decay heat measurements of five used PWR 17x17 nuclear fuel assemblies [O] . Peter Jansson, Martin Bengtsson, Ulrika Bäckström, 2020

机译：来自五个二手PWR 17x17核燃料组件的量热衰减热测量数据
7. Workshop on data-acquisition and -display systems: directions after TMI. PWR; BWR [O] . 1980

机译：数据获取和-Display系统的研讨会：TMI后的方向。 PWR; BWR
8. Experimental Damping Data for Dynamic Analysis of Nuclear Power Plant Piping Systems (PWR; BWR) [R] . Ware, A. G. 1983

机译：核动力装置管道系统动态分析的实验阻尼数据（pWR; BWR）

NEXUS – A New Nuclear Data System for PWR and BWR CoreSimulators

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