The spent nuclear fuel (SNF) aging system at the proposed Yucca Mountain repository will provide site-specific casks and aging pads for thermal management of commercial SNF with a heat rate in excess of the waste package thermal output limit. An aging pad can accommodate 1,000 MTHM of SNF, containing a total of 100 aging casks with a horizontal module of 20 casks, and 80 vertical site-specific casks arranged in a 2 x 40 array. The proposed aging system will provide five aging areas in two separate locations. The first location will contain a single pad designated as Aging Area 17A (1,000 MTHM capacity). The second location will contain Aging Areas 17B through 17E (20,000 MTHM total capacity), each consisting of five aging pads arranged in a compact rectangular configuration. This paper presents calculated dose rates as a function of distance from Aging Areas 17A and 17B through 17E. In addition, the paper evaluates the effect of design parameter variations on dose rates with focus on spacing between casks and spacing between pads in Aging Areas 17B through 17E.
{"title":"Dose Rate Evaluation for Spent Fuel Aging Areas at Yucca Mountain","authors":"G. Radulescu, S. Su","doi":"10.2172/840134","DOIUrl":"https://doi.org/10.2172/840134","url":null,"abstract":"The spent nuclear fuel (SNF) aging system at the proposed Yucca Mountain repository will provide site-specific casks and aging pads for thermal management of commercial SNF with a heat rate in excess of the waste package thermal output limit. An aging pad can accommodate 1,000 MTHM of SNF, containing a total of 100 aging casks with a horizontal module of 20 casks, and 80 vertical site-specific casks arranged in a 2 x 40 array. The proposed aging system will provide five aging areas in two separate locations. The first location will contain a single pad designated as Aging Area 17A (1,000 MTHM capacity). The second location will contain Aging Areas 17B through 17E (20,000 MTHM total capacity), each consisting of five aging pads arranged in a compact rectangular configuration. This paper presents calculated dose rates as a function of distance from Aging Areas 17A and 17B through 17E. In addition, the paper evaluates the effect of design parameter variations on dose rates with focus on spacing between casks and spacing between pads in Aging Areas 17B through 17E.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"8 1","pages":"29-30"},"PeriodicalIF":0.0,"publicationDate":"2005-01-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77100203","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}
The mixed convection regime is a transitional heat transfer regime between forced convection and natural convection, where both the forced component of flow, and the buoyancy induced component are important. Aiding flow is when buoyancy forces act in the same direction as the forced flow (heated upflow or cooled downflow), while opposing flow is when the buoyancy force is in the opposite direction of the forced flow (cooled upflow or heated downflow). For opposing flow the buoyancy always increases the rate of heat transfer over the forced convection value. For aiding flow, as the heat flux increased, a reduction in heat transfer is encountered until a condition known as laminarization occurs, where the heat transfer is at a minimum value. Further increases in the wall heat flux causes re-transition to turbulence, and increased heat transfer. In this paper, for the first time, experiments were performed to characterize the effect of surface roughness on heat transfer in mixed convection, for the case of aiding flow. A correlation was developed to allow calculation of mixed convection heat transfer coefficients for rough or smooth tubes.
{"title":"Mixed Convection Heat Transfer Experiments in Smooth and Rough Verticla Tubes","authors":"P. Symolon, W. Neuhaus, R. O'dell","doi":"10.2172/850142","DOIUrl":"https://doi.org/10.2172/850142","url":null,"abstract":"The mixed convection regime is a transitional heat transfer regime between forced convection and natural convection, where both the forced component of flow, and the buoyancy induced component are important. Aiding flow is when buoyancy forces act in the same direction as the forced flow (heated upflow or cooled downflow), while opposing flow is when the buoyancy force is in the opposite direction of the forced flow (cooled upflow or heated downflow). For opposing flow the buoyancy always increases the rate of heat transfer over the forced convection value. For aiding flow, as the heat flux increased, a reduction in heat transfer is encountered until a condition known as laminarization occurs, where the heat transfer is at a minimum value. Further increases in the wall heat flux causes re-transition to turbulence, and increased heat transfer. In this paper, for the first time, experiments were performed to characterize the effect of surface roughness on heat transfer in mixed convection, for the case of aiding flow. A correlation was developed to allow calculation of mixed convection heat transfer coefficients for rough or smooth tubes.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"29 1","pages":"387-390"},"PeriodicalIF":0.0,"publicationDate":"2004-12-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84425873","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}
Pub Date : 2004-01-01DOI: 10.1515/ci.2004.26.3.23b
M. Bonardi, F. Groppi
{"title":"The new IUPAC project on Terminology, quantities and units concerning production and applications of radionuclides in radiopharmaceutical and radioanalytical chemistry","authors":"M. Bonardi, F. Groppi","doi":"10.1515/ci.2004.26.3.23b","DOIUrl":"https://doi.org/10.1515/ci.2004.26.3.23b","url":null,"abstract":"","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"2 1","pages":"851-852"},"PeriodicalIF":0.0,"publicationDate":"2004-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85413159","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}
W. Hamel, S. Douglass, Sewoong Kim, Pamela Murray, Yang Shou, S. Sridharan, G. Zhang, S. Thayer, R. Dubey
Due to the increasing number of work sites that are hazardous or merely inaccessible, remote manipulation has become more and more important. Nuclear, underwater, and space applications, exemplify a few of the dangerous environments in which work may be desired, while micromanipulation, which has become of more interest lately, is an example of an inherently inaccessible environment. The past 50 yr have seen great advances in remote manipulation technology, from the pioneering work of Ray Goertz in the 1950s to the ongoing development at Oak Ridge National Laboratory (ORNL) of the modular light-duty utility arm (MLDUA), which is a long-reach manipulator for use in the cleanup of the waste storage tanks. Mainly, research has either focused on the improvement of manually operated remote manipulators or teleoperators, in which a human is an integral part of the control loop, or autonomous robots, which have the required decision-making capability and sensors. However, in the past few years, it has become increasingly evident that there are limitations in each of these modalities, which make them individually unsuited for certain tasks. While a human operator may be required to make high-level decisions, fatigue and tedium can result from repetitive tasks. On the other hand,more » computers can provide fast and efficient operation but are limited by their currently inadequate decision-making abilities as well as inaccuracies in the utilized sensors. An ideal teleoperator would be one in which the human is involved in the operation only to the extent that high-level decisions must be made and corrections must be made to account for inaccuracies in the sensors. Responsibilities such as gross alignment and repetitive motions would be delegated to computer control.« less
{"title":"HUMAN MACHINE COOPERATIVE TELEROBOTICS","authors":"W. Hamel, S. Douglass, Sewoong Kim, Pamela Murray, Yang Shou, S. Sridharan, G. Zhang, S. Thayer, R. Dubey","doi":"10.2172/894296","DOIUrl":"https://doi.org/10.2172/894296","url":null,"abstract":"Due to the increasing number of work sites that are hazardous or merely inaccessible, remote manipulation has become more and more important. Nuclear, underwater, and space applications, exemplify a few of the dangerous environments in which work may be desired, while micromanipulation, which has become of more interest lately, is an example of an inherently inaccessible environment. The past 50 yr have seen great advances in remote manipulation technology, from the pioneering work of Ray Goertz in the 1950s to the ongoing development at Oak Ridge National Laboratory (ORNL) of the modular light-duty utility arm (MLDUA), which is a long-reach manipulator for use in the cleanup of the waste storage tanks. Mainly, research has either focused on the improvement of manually operated remote manipulators or teleoperators, in which a human is an integral part of the control loop, or autonomous robots, which have the required decision-making capability and sensors. However, in the past few years, it has become increasingly evident that there are limitations in each of these modalities, which make them individually unsuited for certain tasks. While a human operator may be required to make high-level decisions, fatigue and tedium can result from repetitive tasks. On the other hand,more » computers can provide fast and efficient operation but are limited by their currently inadequate decision-making abilities as well as inaccuracies in the utilized sensors. An ideal teleoperator would be one in which the human is involved in the operation only to the extent that high-level decisions must be made and corrections must be made to account for inaccuracies in the sensors. Responsibilities such as gross alignment and repetitive motions would be delegated to computer control.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"24 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2003-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72717122","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}
Measurements using {sup 252}Cf as a timed source of neutrons and gammas have in recent years undergone significant maturation. These methods use {sup 252}Cf as an observable source of spontaneous fission neutrons and gammas in conjunction with one or more neutron- and/or gamma-sensitive detectors to measure the time-distribution of correlated detector counts following (a) an observed {sup 252}Cf-fission event and/or (b) a counting event in another detector. Detection of {sup 252}Cf spontaneous fission is frequently achieved via use of a small ionization chamber in which the {sup 252}Cf is contained--in this case the timing of source emission events is random. However, one application subsequently described uses a neutron-absorbent ''shutter'' to modulate {sup 252}Cf emissions to produce a neutron source with deterministic timing. Other applications, frequently termed noise-analysis measurements, transform the time-distributions to the frequency domain. Collectively, these correlation methods use {sup 252}Cf to ''excite'' the fissile material and the response of the material is measured by an array of detectors and analyzed using standard time-correlation and/or frequency-analysis techniques. In recent years numerous advances have been made in the application of these methods to in-situ, or field measurements directed at characterizing various configurations of fissile material in operational facilities.
{"title":"Correlation Measurements with {sup 252}Cf to Characterize Fissile Material","authors":"J. Mattingly","doi":"10.2172/816191","DOIUrl":"https://doi.org/10.2172/816191","url":null,"abstract":"Measurements using {sup 252}Cf as a timed source of neutrons and gammas have in recent years undergone significant maturation. These methods use {sup 252}Cf as an observable source of spontaneous fission neutrons and gammas in conjunction with one or more neutron- and/or gamma-sensitive detectors to measure the time-distribution of correlated detector counts following (a) an observed {sup 252}Cf-fission event and/or (b) a counting event in another detector. Detection of {sup 252}Cf spontaneous fission is frequently achieved via use of a small ionization chamber in which the {sup 252}Cf is contained--in this case the timing of source emission events is random. However, one application subsequently described uses a neutron-absorbent ''shutter'' to modulate {sup 252}Cf emissions to produce a neutron source with deterministic timing. Other applications, frequently termed noise-analysis measurements, transform the time-distributions to the frequency domain. Collectively, these correlation methods use {sup 252}Cf to ''excite'' the fissile material and the response of the material is measured by an array of detectors and analyzed using standard time-correlation and/or frequency-analysis techniques. In recent years numerous advances have been made in the application of these methods to in-situ, or field measurements directed at characterizing various configurations of fissile material in operational facilities.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"29 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2000-01-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85756899","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}
Pub Date : 1999-09-01DOI: 10.1016/S0149-1970(02)00014-8
Joann Campbell, G. Spriggs
{"title":"Delayed neutron spectral data for Hansen-Roach energy group structure","authors":"Joann Campbell, G. Spriggs","doi":"10.1016/S0149-1970(02)00014-8","DOIUrl":"https://doi.org/10.1016/S0149-1970(02)00014-8","url":null,"abstract":"","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"56 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1999-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80067813","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}
R. Sanchez, R. Kimpland, K. Butterfield, P. Jaegers, W. Casson
Fissile material in waste is frequently encountered in decontamination and decommissioning activities. Thousands of drums containing radioactive waste are stored in storage facilities throughout the DOE complex. The amount of fissile material in each drum is generally small because of the criticality safety limits that have been calculated using neutron transport computer codes such as MCNP, KENO, or ONEDANT. No experimental critical data are available to assure the correctiveness of the calculations for those systems containing fissile material (U-235, U-233, and Pu-239) in contact with matrix material (Al{sub 2}O{sub 3}, CaO, MgO, and SiO{sub 2}) in the drums. The purpose of the U-235 foil-SiO{sub 2}-polyethylene experiment is to provide experimental data to validate the computer transport codes and the cross section data.
{"title":"Critical mass experiment using U-235 foils-SiO{sub 2}-polyethylene plates","authors":"R. Sanchez, R. Kimpland, K. Butterfield, P. Jaegers, W. Casson","doi":"10.2172/334338","DOIUrl":"https://doi.org/10.2172/334338","url":null,"abstract":"Fissile material in waste is frequently encountered in decontamination and decommissioning activities. Thousands of drums containing radioactive waste are stored in storage facilities throughout the DOE complex. The amount of fissile material in each drum is generally small because of the criticality safety limits that have been calculated using neutron transport computer codes such as MCNP, KENO, or ONEDANT. No experimental critical data are available to assure the correctiveness of the calculations for those systems containing fissile material (U-235, U-233, and Pu-239) in contact with matrix material (Al{sub 2}O{sub 3}, CaO, MgO, and SiO{sub 2}) in the drums. The purpose of the U-235 foil-SiO{sub 2}-polyethylene experiment is to provide experimental data to validate the computer transport codes and the cross section data.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"3 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1998-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75587765","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}
Criticality dimensions for highly enriched {sup 235}U(93.5) and {sup 239}Pu(95.5) systems mixed with D{sub 2}O were studied. The objective of this work is to investigate the minimum critical mass and concentration of uranium and plutonium systems in a reflector-moderated arrangement. The present work demonstrates the critical instability of these systems that are moderated and reflected by D{sub 2}O and expands in previous unpublished work. These calculations were performed in a spherical geometry with the DANTS codes using the Hansen-Roach cross section library. Densities examined ranged from normal to very small, and are assumed to be uniform throughout the core. These spherical systems are reflected by 100 cm of D{sub 2}O.
{"title":"Critical mass analysis for {sup 235}U and {sup 239}Pu systems moderated and reflected by D{sub 2}O","authors":"D. Loaiza, W. Stratton","doi":"10.2172/334334","DOIUrl":"https://doi.org/10.2172/334334","url":null,"abstract":"Criticality dimensions for highly enriched {sup 235}U(93.5) and {sup 239}Pu(95.5) systems mixed with D{sub 2}O were studied. The objective of this work is to investigate the minimum critical mass and concentration of uranium and plutonium systems in a reflector-moderated arrangement. The present work demonstrates the critical instability of these systems that are moderated and reflected by D{sub 2}O and expands in previous unpublished work. These calculations were performed in a spherical geometry with the DANTS codes using the Hansen-Roach cross section library. Densities examined ranged from normal to very small, and are assumed to be uniform throughout the core. These spherical systems are reflected by 100 cm of D{sub 2}O.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"19 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1998-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90291757","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}
An overview is provided on cavitation threshold measurement experiments for water and mercury. Various aspects to be considered that affect onset determination are discussed along with design specifications developed for construction of appropriate apparatus types. Both static and transient-cavitation effects were studied using radically different apparatus designs. Preliminary data are presented for cavitation thresholds for water and mercury over a range of temperatures in static and high-frequency environments. Implications and issues related to spallation neutron source target designs and operation are discussed.
{"title":"Experimental determination of cavitation thresholds in liquid water and mercury","authors":"R. Taleyarkhan, C. West, F. Moraga","doi":"10.2172/291065","DOIUrl":"https://doi.org/10.2172/291065","url":null,"abstract":"An overview is provided on cavitation threshold measurement experiments for water and mercury. Various aspects to be considered that affect onset determination are discussed along with design specifications developed for construction of appropriate apparatus types. Both static and transient-cavitation effects were studied using radically different apparatus designs. Preliminary data are presented for cavitation thresholds for water and mercury over a range of temperatures in static and high-frequency environments. Implications and issues related to spallation neutron source target designs and operation are discussed.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1998-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86386315","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}
Pub Date : 1998-11-01DOI: 10.13182/FST98-A11963716
K. Schultz, D. Goodin, R. Petzoldt
The Target Factory at an inertial fusion energy (IFE) power plant must produce {approximately}500,000 targets each day, fill them with deuterium-tritium fuel, cool them to cryogenic temperature, and layer the solid fuel inside the capsule. The targets must then be accurately delivered to the high-temperature target chamber at a rate of {approximately}6 Hz without mechanical or thermal damage. Prediction of target location at shot time must be very accurate. Design studies predict that this is achievable but will require development. Preliminary experiments at Lawrence Berkeley National Laboratory have successfully demonstrated that the accuracy requirements for indirect drive target injection can be met, at least for injection into a vacuum chamber at room temperature with low repetition rate. As part of the US IFE program, General Atomics is constructing an experimental target injection and tracking system to develop the scientific understanding necessary for injection of cryogenic IFE targets into a high-temperature reaction chamber.
{"title":"An IFE target injection and tracking experiment","authors":"K. Schultz, D. Goodin, R. Petzoldt","doi":"10.13182/FST98-A11963716","DOIUrl":"https://doi.org/10.13182/FST98-A11963716","url":null,"abstract":"The Target Factory at an inertial fusion energy (IFE) power plant must produce {approximately}500,000 targets each day, fill them with deuterium-tritium fuel, cool them to cryogenic temperature, and layer the solid fuel inside the capsule. The targets must then be accurately delivered to the high-temperature target chamber at a rate of {approximately}6 Hz without mechanical or thermal damage. Prediction of target location at shot time must be very accurate. Design studies predict that this is achievable but will require development. Preliminary experiments at Lawrence Berkeley National Laboratory have successfully demonstrated that the accuracy requirements for indirect drive target injection can be met, at least for injection into a vacuum chamber at room temperature with low repetition rate. As part of the US IFE program, General Atomics is constructing an experimental target injection and tracking system to develop the scientific understanding necessary for injection of cryogenic IFE targets into a high-temperature reaction chamber.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"37 2 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1998-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87442390","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}
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