Transactions of the American Nuclear Society最新文献_第4页

Computational Flow Predictions for the Lower Plenum of a High-Temperature, Gas-Cooled Reactor 高温气冷反应堆下静压室的计算流预测

Transactions of the American Nuclear Society Pub Date : 2006-11-01 DOI: 10.2172/911720

D. Guillen

引用次数: 5

Experimental measurement of flow phenomena in a VHTR lower plenum model VHTR下充气室模型流动现象的实验测量

Transactions of the American Nuclear Society Pub Date : 2006-09-01 DOI: 10.2172/948590

H. M. McIlroy, D. McEligot, R. Schultz, Daniel P. Christensen, R. Pink, R. Johnson

{"title":"Experimental measurement of flow phenomena in a VHTR lower plenum model","authors":"H. M. McIlroy, D. McEligot, R. Schultz, Daniel P. Christensen, R. Pink, R. Johnson","doi":"10.2172/948590","DOIUrl":"https://doi.org/10.2172/948590","url":null,"abstract":"The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further development by the Generation IV International Forum. In addition this system is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. In preparation for the thermal-hydraulics and safety analyses that will be required to confirm the performance of the NGNP, work has begun on readying the computational tools that will be needed to predict the thermal-hydraulics conditions and safety margins of the reactor design. Meaningful feasibility studies for VHTR designs will require accurate, reliable predictions of material temperatures which depend upon the thermal convection in the coolant channels of the core and other components. Unfortunately, one-dimensional system codes for gas-cooled reactors typically underpredict these temperatures, particularly for reduced power operations and hypothesized accident scenarios. Likewise, most turbulence models in general-purpose CFD codes also underpredict these temperatures. Matched-Index-of-Refraction (MIR) fluid dynamics experiments have been designed and built to develop benchmark databases for the assessment of CFD solutions of the momentum equations, scalar mixing and turbulence models for typical VHTR plenum geometries in the limiting case of negligiblemore » buoyancy and constant fluid properties.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"1 1","pages":"367-368"},"PeriodicalIF":0.0,"publicationDate":"2006-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79662597","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 7

The new center for advanced energy studies (CAES) 新的先进能源研究中心(CAES)

Transactions of the American Nuclear Society Pub Date : 2006-06-18 DOI: 10.18260/1-2--1328

L. Bond, R. A. Whadon, A. Kadak

引用次数: 0

SOURCE TERM REMEDIATION & DEMOLITION STRATEGY FOR THE HANFORD K-AREA SPENT FUEL BASINS 汉福德k区乏燃料池源期修复与拆除策略

Transactions of the American Nuclear Society Pub Date : 2006-03-23 DOI: 10.2172/881670

G. B. Chronister

引用次数: 1

Calculation of Critical Experiments involving U(37)O2F2 Solution U(37)O2F2溶液临界实验计算

Transactions of the American Nuclear Society Pub Date : 2006-03-03 DOI: 10.2172/885548

K. L. Goluoglu

引用次数: 0

Criticality Potential of Waste Packages Containing DOE SNF Affected by Igneous Intrusion 火成岩侵入对含DOE SNF废物包装临界潜势的影响

Transactions of the American Nuclear Society Pub Date : 2006-02-07 DOI: 10.2172/893931

D. Kimball, C. Sanders

{"title":"Criticality Potential of Waste Packages Containing DOE SNF Affected by Igneous Intrusion","authors":"D. Kimball, C. Sanders","doi":"10.2172/893931","DOIUrl":"https://doi.org/10.2172/893931","url":null,"abstract":"The Department of Energy (DOE) is currently preparing an application to submit to the U.S. Nuclear Regulatory Commission for a construction authorization for a monitored geologic repository. The repository will contain spent nuclear fuel (SNF) and defense high-level waste (DHLW) in waste packages placed in underground tunnels, or drifts. The primary objective of this paper is to perform a criticality analysis for waste packages containing DOE SNF affected by a disruptive igneous intrusion event in the emplacement drifts. The waste packages feature one DOE SNF canister placed in the center and surrounded by five High-Level Waste (HLW) glass canisters. The effective neutron multiplication factor (k{sub eff}) is determined for potential configurations of the waste package during and after an intrusive igneous event. Due to the complexity of the potential scenarios following an igneous intrusion, finding conservative and bounding configurations with respect to criticality requires some additional considerations. In particular, the geometry of a slumped and damaged waste package must be examined, drift conditions must be modeled over a range of parameters, and the chemical degradation of DOE SNF and waste package materials must be considered for the expected high temperatures. The secondary intent of this calculation is to present amore » method for selecting conservative and bounding configurations for a wide range of end conditions.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"12 1","pages":"145-146"},"PeriodicalIF":0.0,"publicationDate":"2006-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89821844","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Prototypical experiments on air oxidation of zircaloy cladding at high temperatures 锆合金包层高温空气氧化的原型实验

Transactions of the American Nuclear Society Pub Date : 2006-01-01 DOI: 10.5445/IR/270067262

M. Steinbrück, U. Stegmaier, T. Ziegler

{"title":"Prototypical experiments on air oxidation of zircaloy cladding at high temperatures","authors":"M. Steinbrück, U. Stegmaier, T. Ziegler","doi":"10.5445/IR/270067262","DOIUrl":"https://doi.org/10.5445/IR/270067262","url":null,"abstract":"The report presents the results of extensive experimental work on the oxidation of Zircaloy-4 in air at high temperatures. The experimental program was aimed at mechanistic phenomenology of the reaction between Zircaloy and air and investigation of air attack under prototypical conditions for air ingress under the conditions of an hypothetical severe nuclear reactor accident, i.e. at temperatures 800-1500 °C and consideration of mixed air(nitrogen)-steam atmospheres and pre-oxidation. The oxidation in air as well as in air and nitrogen-containing atmospheres leads to strong degradation of the cladding material. The main mechanism for this process is the formation of zirconium nitride and its re-oxidation. From safety point of view, the barrier effect of the fuel cladding is lost much earlier than during accident transients with only a steam atmosphere. Pre-oxidation in steam prevents air attack as long as the oxide scale is intact, i.e. at temperatures above 1050 °C (beyond breakaway regime) and as long as oxidising gases are available (no steam starvation conditions). Under steam/oxygen starvation conditions the oxide scale is reduced and significant external nitride formation takes place. Stronger degradation of cladding tubes was also observed in air-steam and nitrogen-steam mixtures over a wide range of compositions. Regarding modelling of air ingress in severe accident computer codes one conclusion is that parabolic correlations for oxidation in air may be applied only for high temperatures (>1400 °C) and for pre-oxidized cladding (> 1100 °C). For all other conditions faster, more linear reaction kinetics should be applied. The results presented in this report are mainly of phenomenological nature. Therefore, the program will be extended by selected experiments oriented on the determination of kinetic correlations.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"12 1","pages":"136-137"},"PeriodicalIF":0.0,"publicationDate":"2006-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78256970","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 11

Experimental Criticality Benchmarks for SNAP 10A/2 Reactor Cores SNAP 10A/2堆芯实验临界基准

Transactions of the American Nuclear Society Pub Date : 2005-12-19 DOI: 10.2172/885963

A. Krass

引用次数: 3

An Improved Analytical Approach to Determine the Explosive Effects of Flammable Gas-Air Mixtures 一种确定可燃气体-空气混合物爆炸效应的改进分析方法

Transactions of the American Nuclear Society Pub Date : 2005-11-10 DOI: 10.2172/888583

Joong M. Yang

引用次数: 3

Repository waste package transporter shielding weight optimization 堆积库废物包装运输机屏蔽重量优化

Transactions of the American Nuclear Society Pub Date : 2005-02-02 DOI: 10.2172/840150

C. Sanders, S. Su

引用次数: 0