Transactions of the American Nuclear Society最新文献_第9页

Preliminary results of a Rossi-alpha experiment on the University of New Mexico`s AGN-201 reactor 新墨西哥大学AGN-201反应堆上罗西α实验的初步结果

Transactions of the American Nuclear Society Pub Date : 1994-07-01 DOI: 10.2172/10163021

R. Busch, G. Spriggs

引用次数: 8

Optical and thermophysical properties of high-temperature gaseous uranium for nuclear rocket applications 核火箭用高温气态铀的光学和热物理性质

Transactions of the American Nuclear Society Pub Date : 1994-06-27 DOI: 10.2514/6.1994-2898

V. Banjac, A. Heger

引用次数: 0

Fast shutdown-margin calculation using perturbation theory with regionwise flux expansion 基于区域通量展开的微扰理论快速停机余量计算

Transactions of the American Nuclear Society Pub Date : 1994-03-01 DOI: 10.13182/NSE94-A19812

Jengjung Fang, Y. Liu, Pin-Wu Kao

引用次数: 3

Impact of thermal loading on waste package material performance 热载荷对废旧包装材料性能的影响

Transactions of the American Nuclear Society Pub Date : 1994-01-01 DOI: 10.1557/PROC-353-671

D. Stahl, J. K. Mccoy, R. D. Mccright

引用次数: 4

Direct containment heating experiments in Zion Nuclear Power Plant geometry using prototypic materials 锡安核电站几何形状使用原型材料的直接安全壳加热实验

Transactions of the American Nuclear Society Pub Date : 1993-12-31 DOI: 10.2172/140597

J. L. Binder, L. McUmber, B. W. Spencer

{"title":"Direct containment heating experiments in Zion Nuclear Power Plant geometry using prototypic materials","authors":"J. L. Binder, L. McUmber, B. W. Spencer","doi":"10.2172/140597","DOIUrl":"https://doi.org/10.2172/140597","url":null,"abstract":"Direct Containment Heating (DCH) experiments have been completed which utilize prototypic core materials. The experiments reported on here are a continuation of the Integral Effects Testing (IET) DCH program. The experiments incorporated a 1/40 scale model of the Zion Nuclear Power Plant containment structures. The model included representations of the primary system volume, RPV lower head, cavity and instrument tunnel, and the lower containment structures. The experiments were steam driven. Iron-alumina thermite with chromium was used as a core melt stimulant in the earlier IET experiments. These earlier IET experiments at Argonne National Laboratory (ANL) and Sandia National Laboratories (SNL) provided useful data on the effect of scale on DCH phenomena; however, a significant question concerns the potential experiment distortions introduced by the use of non-prototypic iron/alumina thermite. Therefore, further testing with prototypic materials has been carried out at ANL. Three tests have been completed, DCH-U1A, U1B and U2. DCH-U1A and U1B employed an inerted containment atmosphere and are counterpart to the IET-1RR test with iron/alumina thermite. DCH-U2 employed nominally the same atmosphere composition of its counterpart iron/alumina test, IET-6. All tests, with prototypic material, have produced lower peak containment pressure rises; 45, 111 and 185 kPa in U1A, U1Bmore » and U2, compared to 150 and 250 kPa IET-1RR and 6. Hydrogen production, due to metal-steam reactions, was 33% larger in U1B and U2 compared to IET-1RR and IET-6. The pressurization efficiency was consistently lower for the corium tests compared to the IET tests.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"47 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1993-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78870917","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: 3

Interactions between drops of molten Al-Li alloys and liquid water 铝锂合金液滴与液态水的相互作用

Transactions of the American Nuclear Society Pub Date : 1993-08-01 DOI: 10.2172/10107057

M. Hyder, L. S. Nelson, P. M. Duda, D. Hyndman

{"title":"Interactions between drops of molten Al-Li alloys and liquid water","authors":"M. Hyder, L. S. Nelson, P. M. Duda, D. Hyndman","doi":"10.2172/10107057","DOIUrl":"https://doi.org/10.2172/10107057","url":null,"abstract":"Sandia National Laboratories, at the request of the Savannah River Technology Center (SRTC), studied the interactions between single drops of molten aluminum-lithium alloys and water. Most experiments were performed with ``B`` alloy (3.1 w/o Li, balance A1). Objectives were to develop experimental procedures for preparing and delivering the melt drops and diagnostics for characterizing the interactions, measure hydrogen generated by the reaction between melt and water, examine debris recovered after the interaction, determine changes in the aqueous phase produced by the melt-water chemical reactions, and determine whether steam explosions occur spontaneously under the conditions studied. Although many H{sub 2} bubbles were generated after the drops entered the water, spontaneous steam explosions never occurred when globules of the ``B`` alloy at temperatures between 700 and 1000C fell freely through water at room temperature, or upon or during subsequent contact with submerged aluminum or stainless steel surfaces. Total amounts of H{sub 2} (STP) increased from about 2 to 9 cm{sup 3}/per gram of melt as initial melt temperature increased over this range of temperatures.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"86 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1993-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77995730","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: 2

Cost estimate guidelines for advanced nuclear power technologies 先进核电技术成本估算指南

Transactions of the American Nuclear Society Pub Date : 1993-05-01 DOI: 10.2172/10176857

J. Delene, C. Hudson

引用次数: 42

Evaluation of the gas pressure resulting from an ITP waste tank deflagration 对ITP废液罐爆燃产生的气体压力进行评估

Transactions of the American Nuclear Society Pub Date : 1993-04-01 DOI: 10.2172/10188865

J. K. Thomas, S. Hensel

引用次数: 0

Critical technologies for reactors used in nuclear electric propulsion 核动力推进反应堆的关键技术

Transactions of the American Nuclear Society Pub Date : 1993-01-01 DOI: 10.2172/10171767

S. Bhattacharyya

{"title":"Critical technologies for reactors used in nuclear electric propulsion","authors":"S. Bhattacharyya","doi":"10.2172/10171767","DOIUrl":"https://doi.org/10.2172/10171767","url":null,"abstract":"Nuclear electric Propulsion (NEP) systems are expected to play a significant role in the exploration and exploitation of space. Unlike nuclear thermal propulsion (NTP) systems in which the hot reactor coolant is directly discharged from nozzles to provide the required thrust, NEP systems include electric power generation and conditioning units that in turn are used to drive electric thrusters. These thrusters accelerate sub atomic particles to produce thrust. The major advantage of NEP systems is the ability to provide very high specific impulses ([approximately]5000 s) that minimize the requirement for propellants. In addition, the power systems used in NEP could pro vide the dual purpose of also providing power for the missions at the destination. This synergism can be exploited in shared development costs. The NEP systems produce significantly lower thrust that NTP systems and are generally more massive. Both systems have their appropriate roles in a balanced space program. The technology development needs of NEP systems differ in many important ways from the development needs for NTP systems because of the significant differences in the operating conditions of the systems. The NEP systems require long-life reactor power systems operating at power levels that are considerably lower than those formore » NTP systems. In contrast, the operational lifetime of an NEP system (years) is orders of magnitude longer than the operational lifetime of NTP systems (thousands of second). Thus, the critical issue of NEP is survivability and reliable operability for very long times at temperatures that are considerably more modest than the temperatures required for effective NTP operations but generally much higher than those experienced in terrestrial reactors.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"44 1","pages":"17908"},"PeriodicalIF":0.0,"publicationDate":"1993-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75322916","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

The Accelerator Transmutation of Waste (ATW) concept overview 废物加速器嬗变(ATW)概念概述

Transactions of the American Nuclear Society Pub Date : 1993-01-01 DOI: 10.2172/10190589

H. Dewey

{"title":"The Accelerator Transmutation of Waste (ATW) concept overview","authors":"H. Dewey","doi":"10.2172/10190589","DOIUrl":"https://doi.org/10.2172/10190589","url":null,"abstract":"The accelerator transmutation of waste (ATW) concept is aimed at destroying key long-lived radionuclides (both actinides and fission products) in nuclear wastes, thereby reducing the long-term risks associated with the storage of such wastes. This technology could evolve into an approach to the production of fission power, utilizing abundant natural fuels and producing minimal long-lived nuclear waste. An ATW system would consist of the following components: 1. proton accelerator; 2. heavy-metal target; 3. moderating blanket; 4. thermal-to-electric power conversion plant; and 5. chemical separation facility. The linear accelerator provides a medium-energy, high-current proton beam that is directed at a heavy-metal target. The target converts the proton beam through spallation reactions into an intense neutron flux that is thermalized in the blanket region surrounding the target. The radioactive material to be transmuted is circulated through the blanket, where it undergoes neutron-induced reactions. Long-lived fission products undergo (n, [gamma]) reactions followed by beta decay, producing short-lived or stable products. The actinides are fissioned, producing additional neutrons and an assortment of fission products to reduce parasitic absorption in the blanket and to prevent further activation of these materials to long-lived radionuclides.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"72 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1993-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84737825","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