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    <title>Transport Research International Documentation (TRID)</title>
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    <copyright>Copyright © 2026. National Academy of Sciences. All rights reserved.</copyright>
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    <managingEditor>tris-trb@nas.edu (Bill McLeod)</managingEditor>
    <webMaster>tris-trb@nas.edu (Bill McLeod)</webMaster>
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      <title>Transport Research International Documentation (TRID)</title>
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      <title>Thermal Boundary Conditions from Engulfing Fires</title>
      <link>https://trid.trb.org/View/1530824</link>
      <description><![CDATA[This research was part of an ongoing program aimed at understanding the response of rail casks transporting radioactive materials in a fire during a hypothetical accident. Determination of a realistic fire boundary condition provides cask designers with a tool to predict accurately the response of a cask in a fire. In one approach to determining this thermal input, data were analyzed from previous engulfing fire experiments on casklike objects. In another approach an analytical model was developed to investigate the influence of test objects on the fire. As has long been suspected, the cask and the fire environment strongly interact. The response of a cask in a fire is highly dependent on the physical and thermal characteristics of the cask; in fact, a very massive cask can alter the early fire environment. Therefore, it appears unlikely that a simple fire boundary condition can be derived that will accurately describe the response of a cask in a fire.]]></description>
      <pubDate>Mon, 20 Aug 2018 22:14:02 GMT</pubDate>
      <guid>https://trid.trb.org/View/1530824</guid>
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    <item>
      <title>Used Fuel Disposition Campaign. Transportation Shock and Vibration Literature Review</title>
      <link>https://trid.trb.org/View/1258379</link>
      <description><![CDATA[The purpose of this report is to document the results of a literature review conducted of studies related to the vibration and shock associated with the normal conditions of transport for rail shipments of used nuclear fuel from commercial light-water reactors. The objective of this report is to determine if adequate data exist to realistically evaluate the impacts of the shock and vibration associated with the normal conditions of transport on commercial light-water reactor used nuclear fuel shipped in current-generation high-capacity rail transportation casks. The literature review concentrated on papers and reports related to the transport of used nuclear fuel, radioactive waste, or other radioactive material, in part because of the weight associated with commercial light-water reactor used nuclear fuel rail transportation casks, which is about 300,000 lb., and because the weight of the transportation cask on a railcar directly affects the magnitude of vibrations and shock imparted to the used nuclear fuel contained in the transportation cask.]]></description>
      <pubDate>Tue, 03 Sep 2013 12:24:18 GMT</pubDate>
      <guid>https://trid.trb.org/View/1258379</guid>
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      <title>Assessing Aggregates for Radiation-Shielding Concrete</title>
      <link>https://trid.trb.org/View/1251421</link>
      <description><![CDATA[Petrographic examination provides an effective means of detecting potentially deleterious and undesirable materials in aggregates for concrete. In this article, the authors discuss aggregates used in radiation-shielding concrete (RSC). They also cite the standards and describe the procedures for evaluating these aggregates. The article discusses how RSC is used in nuclear power plants, health care facilities, and storage/transport casks for radioactive wastes. High-density aggregates are used in RSC mixtures to attenuate gamma rays and light atomic weight aggregates are used to absorb neutrons, so their properties and proportions will affect a mixture’s radiation-shielding characteristics.]]></description>
      <pubDate>Mon, 03 Jun 2013 09:21:20 GMT</pubDate>
      <guid>https://trid.trb.org/View/1251421</guid>
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      <title>Bounding Criticality Safety Analyses for Shipments of Unconfigured Spent Nuclear Fuel</title>
      <link>https://trid.trb.org/View/870961</link>
      <description><![CDATA[In November 1996, a request was made to the US Department of Energy for a waiver for three shipments of spent nuclear fuel (SNF) from Oak Ridge National Laboratory (ORNL) to the Savannah River Site (SRS) in the US NRC certified BMI- 1 cask (CoC 5957). Although the post-irradiation fissile mass (based on chemical assays) in each shipment was less than 800 g, a criticality safety analysis was needed because the pre-irradiation mass exceeded 800 g, the fissile material limit in the CoC. The analyses were performed on SNF consisting of aluminum-clad U(sub 3)O(sub 8), UAl(sub x), and U(sub 3)Si(sub 2) plates, fragments and pieces that had been irradiated at ORNL during the Reduced Enrichment Research and Test Reactor Program of the 1980s. The highlights of the approach used to analyze this unique SNF and the benefits of the waiver are presented in this paper.]]></description>
      <pubDate>Mon, 29 Sep 2008 11:47:59 GMT</pubDate>
      <guid>https://trid.trb.org/View/870961</guid>
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      <title>Evaluation of Effect of Fuel Assembly Loading Patterns on Thermal and Shielding Performance of a Spent Fuel Storage/Transportation Cask</title>
      <link>https://trid.trb.org/View/864801</link>
      <description><![CDATA[The licensing of spent fuel storage casks is generally based on conservative analyses that assume a storage system being uniformly loaded with design basis fuel. The design basis fuel typically assumes a maximum assembly enrichment, maximum burn up, and minimum cooling time. These conditions set the maximum decay heat loads and radioactive source terms for the design. Recognizing that reactor spent fuel pools hold spent fuel with an array of initial enrichments, burners, and cooling times, this study was performed to evaluate the effect of load pattern on peak cladding temperature and cask surface dose rate. Based on the analysis, the authors concluded that load patterns could be used to reduce peak cladding temperatures in a cask without adversely impacting the surface dose rates.]]></description>
      <pubDate>Thu, 24 Jul 2008 13:34:52 GMT</pubDate>
      <guid>https://trid.trb.org/View/864801</guid>
    </item>
    <item>
      <title>Comparative Safety of the Transport of High-Level Radioactive Materials on Dedicated, Key, and Regular Trains</title>
      <link>https://trid.trb.org/View/795105</link>
      <description><![CDATA[This study compares the risks in transporting spent nuclear fuel and high-level radioactive waste under three rail shipment alternatives: 1) regular train service, operating without restrictions with the exception of current hazardous materials regulations; 2) dedicated train service, operating with consist and operational restrictions; and 3) key train service, similar to regular train service with the additional speed limitation of 50 mph. Dedicated train shipments have a lower overall radioactivity exposure risk during incident-free transport than shipments by regular or key trains; the advantage is primarily derived from the differences in the duration and frequency of yard visits, which account for a significant portion of total exposure for impacted populations. Crew population doses, however, are higher for dedicated trains because of crews working closer to the cask. Estimated population group exposures are low and do not include any additional protective measures, which may be implemented to mitigate exposure.  The accident analysis estimated the difference in accident probability between dedicated, regular, and key trains, and it identified two significant risks potentially impacting the cask—high-speed collisions and derailments, and long duration, high-temperature HAZMAT-involved fires. The analysis shows that speed restrictions reduce collision probability at high speeds and result in an overall reduction in the derailment rate. Dedicated trains reduce the likelihood of high-temperature fires due to lessened exposure to other hazardous material. The risk for loss of shielding accidents is shown to be lower for the shorter dedicated trains due to the decreased number of potentially derailed cars.]]></description>
      <pubDate>Wed, 03 Jan 2007 08:48:44 GMT</pubDate>
      <guid>https://trid.trb.org/View/795105</guid>
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    <item>
      <title>TASK 6.3 - SAFE RAIL TRANSPORTATION OF NUCLEAR MATERIALS: INTERMODAL DESIGN REQUIREMENTS</title>
      <link>https://trid.trb.org/View/660473</link>
      <description><![CDATA[In the broadest sense, the word "intermodal" refers to all shipments which move via more than one transportation mode in their passage from origin to destination.  In the transportation industry, however, "intermodal" has come to refer to freight loaded into standard containers which are readily accommodated by various transportation modes.  More specifically, in the railroad industry "intermodal" generally implies (1) containers equipped with special corner castings which allow them to be secured to specially designed railroad cars, highway chassis and marine vessels and (2) truck semi-trailers (which are containers with wheels).  This report considers the following three general approaches to the intermodal transportation of spent nuclear fuel by motor truck and railroad: 1. the intermodal movement of a trailer holding a nuclear fuel cask; 2. the intermodal movement of a container holding a nuclear fuel cask; and 3. the intermodal movement of a nuclear fuel cask only.]]></description>
      <pubDate>Tue, 12 Aug 2003 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/660473</guid>
    </item>
    <item>
      <title>SHIPPING CONTAINER RESPONSE TO SEVERE HIGHWAY AND RAILWAY ACCIDENT CONDITIONS. MAIN REPORT</title>
      <link>https://trid.trb.org/View/660468</link>
      <description><![CDATA[This report describes a study performed by the Lawrence Livermore National Laboratory to evaluate the level of safety provided under severe accident conditions during the shipment of spent fuel from nuclear power reactors. The evaluation is performed using data from real accident histories and using representative truck and rail cask models that likely meet 10 CFR 71 regulations. The responses of the representative casks are calculated for structural and thermal loads generated by severe highway and railway accident conditions. The cask responses are compared with those responses calculated for the 10 CFR 71 hypothetical accident conditions. By comparing the responses it is determined that most highway and railway accident conditions fall within the 10 CFR 71 hypothetical accident conditions. For those accidents that have higher responses, the probabilities and potential radiation exposures of the accidents are compared with those identified by the assessments made in the "Final Environmental Statement on the Transportation of Radioactive Material by Air and other Modes," NUREG-0170. Based on this comparison, it is concluded that the radiological risks from spent fuel under severe highway and railway accident conditions as derived in this study are less than risks previously estimated in the NUREG-0170 document.]]></description>
      <pubDate>Mon, 11 Aug 2003 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/660468</guid>
    </item>
    <item>
      <title>TASK 2.3 - ASPECTS OF RAILCAR DESIGN FOR CARS INTENDED TO MOVE CASKS CONTAINING SPENT NUCLEAR FUEL ELEMENTS</title>
      <link>https://trid.trb.org/View/660469</link>
      <description><![CDATA[This paper describes regulations and specifications that should be addressed when designing railroad cars and casks systems that will be used to transport spent nuclear reactor fuel.  This task will focus on systems for the transportation of elements of spent nuclear fuel that have been out of reactors for a time period of at least ten years.]]></description>
      <pubDate>Mon, 11 Aug 2003 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/660469</guid>
    </item>
    <item>
      <title>THE ROAD TO YUCCA MOUNTAIN, NEVADA : CAN TRUCKS SAFELY HAUL NUCLEAR WASTE?</title>
      <link>https://trid.trb.org/View/734885</link>
      <description><![CDATA[With the approval of a plan to ship thousands of tons of radioactive nuclear waste from roughly 141 reactors to the U.S. Energy Department repository in Yucca Mountain in Nevada has drawn criticism from safety groups for lack of planning to ensure there is no accidental release of radioactive materials during the journey. Experts are in disagreement over the safest mode for transporting the spent fuel. Rail, highway and even barge transport are being weighed. A 1990 study by the state of Nevada predicted a large number of incidents and crashes, extrapolating from historic crash data. Critics also contend that testing of the shipping casks has yet to demonstrate that they can withstand crash level forces. The U.S. Energy Department responds that it has shipped nuclear material a total of 1.6 million miles over the past 30 years without incident. However, there were releases before that, notable leaks between 1957 and 1964. Critics also say the number of trips needed is vastly understated. The final Environmental Impact Statement by the department said the likelihood of "maximum reasonably foreseeable accidents" is 2.3 in 10 million for trucks and 2.8 in 10 million for rail. Other concerns center around exposure experienced by transport workers, potential public health risks if a leak occurred near a major population center and whether the emergency responders located along the often-remote and rural routes have the capability of dealing with the aftermath of a spill.]]></description>
      <pubDate>Wed, 02 Apr 2003 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/734885</guid>
    </item>
    <item>
      <title>COLLECTION AND ANALYSIS OF TRANSIENT TEST DATA USING THE MOBILE INSTRUMENTATION DATA ACQUISITION SYSTEM (MIDAS)</title>
      <link>https://trid.trb.org/View/465943</link>
      <description><![CDATA[Packages designed to transport radioactive materials are required to survive exposure to environments defined in Code of Federal Regulations.  Cask designers can investigate package designs through structural and thermal testing of full-scale packages, components, or representative models.  The acquisition of reliable  response data from instrumentation measurement devices is an essential part of this testing activity.  Sandia National Laboratories, under the sponsorship of the US Department of Energy, has developed the Mobile Instrumentation Data Acquisition System (MIDAS) dedicated to the collection and processing of structural and thermal data from regulatory tests.]]></description>
      <pubDate>Wed, 31 Dec 1997 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/465943</guid>
    </item>
    <item>
      <title>PAVEMENT STRAINS INDUCED BY SPENT-FUEL TRANSPORTATION TRUCKS</title>
      <link>https://trid.trb.org/View/415070</link>
      <description><![CDATA[Four types of vehicles are being considered for the transportation of spent-fuel casks to the high-level nuclear waste repository that is to be located in Yucca Mountain, Nevada.  The use of a finite-layer moving-load model to compute the pavement strains is described.  Pavement strains are required to compare the relative pavement damage caused by each of the spent-fuel trucks and to estimate the increased cost associated with the increase in maintenance and rehabilitation on pavements caused by the spent-fuel trucks.  The strain response induced by the spent-fuel trucks for a site near Reno, Nevada, is reported.  The asphalt concrete layer and the unbound materials are assumed viscoelastic and elastic, respectively. Pavement material properties were deduced from falling-weight deflectometer testing.  The study reveals that the strain response is affected strongly by the axle configuration and by the speed of the vehicle.  Increased vehicle speed reduces the pavement strains substantially; longitudinal strains in the asphalt concrete layer decrease by as much as 33% when the speed of the vehicle increases from 30 to 60 km/hr.  A substantial compressive strain component is also present when tandem and tridem axle loading are considered.  The difference in contribution to pavement distress between the two legal-weight trucks and between the two overweight trucks is minimal. Laboratory fatigue and cyclic triaxial tests are being evaluated to compare the effects of legal-weight and overweight axle loading.]]></description>
      <pubDate>Thu, 23 Feb 1995 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/415070</guid>
    </item>
    <item>
      <title>SUPPLEMENT TO ORNL/SUB/86-SA094/1 ON USE OF TRANSPORTABLE STORAGE CASKS IN THE NUCLEAR WASTE MANAGEMENT SYSTEM</title>
      <link>https://trid.trb.org/View/345420</link>
      <description><![CDATA[This supplemental report consists of an update of ORNL/Sub/86-SA094/1 and a summary of the composite results. Section 1.0 is an introduction providing background information on the study.  Section 2.0 presents a composite summary of the results of both the original and supplemental study, and the conclusions resulting therefrom.  Section 3.0 presents a summary status of the use of metal storage casks and horizontal storage modules in the United States. Section 4.0 presents the results of an analysis of preliminary designs of MRS and repository facilities with regard to their prospective ability to handle transportable storage casks (TSCs) and storage-only casks (SOCs).  Section 5.0 presents an update of the estimated costs and savings in the utility and Department of Energy (DOE) spent fuel management systems resulting from the use of TSCs and SOCs therein, as well as estimated costs to the utility resulting from the use of horizontal storage modules (HSMs).  Section 6.0 discusses the alternatives available to DOE in dealing with the prospective acceptance of spent nuclear fuel in TSCs or SOCs, and includes both alternatives developed in the original study and the supplemental study.]]></description>
      <pubDate>Fri, 30 Nov 1990 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/345420</guid>
    </item>
    <item>
      <title>TRANSPORTATION BUSINESS PLAN</title>
      <link>https://trid.trb.org/View/267973</link>
      <description><![CDATA[This publication sets the context for business strategy decisions by providing pertinent background information describing requirements of the transportation system. Included in the document are strategies for procuring shipping casks and transportation support services.  The system development cycle attempts to utilize the private sector to maximum extent possible.  The specific objectives of this plan are as follows: to ensure the availability of transportation equipment needed to complete the required shipments from waste generators (This equipment will maximize payloads in order to reduce the number of shipments while fully complying with all applicable safety requirements); to establish a transportation system to safely conduct shipments in a timely fashion; to acquire specialized transportation equipment if needed; and to maintain and enhance institutional relationships needed to establish the transportation system and to conduct transportation operations in an publicly acceptable manner that is in full compliance with applicable regulations. Details are given of transportation systems acquisition phase I which includes the developmentof prototypical spent-fuel and radioactive waste costs required for civilian radioactive waste transport.  In phase II, the Department of Energy (DOE) will develop a transportation system to conduct civilian waste shipments as required. The details of this phase are described including the   business strategy (service contractors, carriage arrangements, training, inspection, maintenance, procurement program management/control plan, schedule, contingent-plans). Transportation institutional program elements are also covered.]]></description>
      <pubDate>Thu, 31 Jul 1986 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/267973</guid>
    </item>
    <item>
      <title>SAFETY ASSESSMENT OF SPENT-FUEL TRANSPORTATION IN EXTREME ENVIRONMENTS</title>
      <link>https://trid.trb.org/View/170390</link>
      <description><![CDATA[Preliminary estimates of the health effects and/or consequences resulting from a malevolent attack on a spent fuel truck shipment in downtown New York City have been made. This estimate is based upon a measured quantity (0.78 +- 0.05 g) of respirable radioactive material released from a 1/4 scale event. A linear extrapolation from the 1/4 scale event to the generic full scale event has been made and an aerosolized release fraction (0.0023 percent) of the total heavy metal inventory of a three-PWR assembly truck cask has been calculated. Although scaling of the source term parameters is tentative at this point in the program, a full scale experiment is planned in 1981 to verify the scaling methodology used in these calculations. A preliminary correlation between spent fuel and surrogate fuel source terms has been shown to be feasible and that radionuclide size partitioning can be determined experimentally. Finally, it has been shown, based on our preliminary experimental source term data, that a maximum of 25 total latent cancer fatalities could occur, assuming a release in downtown New York City. This is 20 times smaller than the latent cancer fatalities predicted in the Urban Study. (ERA citation 06:018118)]]></description>
      <pubDate>Thu, 28 Oct 1982 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/170390</guid>
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