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    <title>Transport Research International Documentation (TRID)</title>
    <link>https://trid.trb.org/</link>
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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>
      <url>https://trid.trb.org/Images/PageHeader-wTitle.jpg</url>
      <link>https://trid.trb.org/</link>
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    <item>
      <title>THE EFFECT OF THE CALCIUM LEACHING ON CAPACITY FOR CHLORIDE ION BINDING OF THE HARDENED CEMENT PASTE</title>
      <link>https://trid.trb.org/View/1351665</link>
      <description><![CDATA[Cement based materials such as the concrete are used as barriers of the radioactive waste disposal facilities. As for the cement based materials, the capacity for binding of the radionuclide is required in facilities, and the ability to control the leak of the nuclide to the external environment is also expected by the low diffusivity of cement based materials. The transport of radionuclide has to be controlled leakage to the external environment in the radioactive waste disposal facilities during 10,000 years. Therefore, the appropriate design of the radioactive disposal facilities is necessary, and the accurate mass transfer prediction model that considered the calcium leaching of cement based materials with the order for tens of thousands of years to evaluate it safely is necessary. In the current model, there is a difference between measurement and predicted value of chloride ion ingress as simulated a nuclide movement in the calcium leaching region of hardened cement paste. It is considered that the input parameter for the capacity for binding of the chloride ion of the hardened cement paste in calcium leaching region is not appropriate. The purpose of this study is to clarify the capacity for the binding of the hardened cement paste that calcium leaching occurred quantitatively. In the experiment, ammonium nitrate solution was used to accelerate calcium leaching of the hardened cement paste. The hardened cement paste with different composition by changing the immersion period was produced. The capacity for binding of the chloride ion by immersing the sample in NaCl solution was determined. In addition, the mineral composition of hardened cement paste was determined by the powder X-ray diffraction with Rietveld method, and the chemical bonding state of the silica chain of calcium silicate hydrate (C-S-H)  was measured by a solid nuclear magnetic resonance device (NMR) to clarify the mechanism that quantity of chloride ion adsorption changed. The results in this study are followings. As immersion period became long, the CaO/SiO₂ ratio of C-S-H in sample which immersed in ammonium nitrate solution decreased, and the capacity for chloride ion binding of leached sample also decreased. As for this reason, the decrease of the adsorption site by the polymerization of silica chains in C-S-H was suggested by the results obtained from NMR measurement, and monosulfate which was one of the hydrates in hardened cement paste was disappeared by calcium leaching. The capacity for chloride ion binding of hardened cement paste was formulated by the results of experiments, and it was able to estimate the predicted value with less than 25％ of errors.硬化セメントペーストからのカルシウム溶脱に伴うC-S-Hの劣化を考慮した物質移動特性変化について基礎的な知見を得ることを目的とし、促進溶脱試料を用いセメントペーストのカルシウム溶脱に伴うC-S-HのCaO/SiO₂の変化、Si鎖の化学状態及びC-S-Hの塩化物イオン吸着能力の変化について検討を行った。この結果、溶脱に伴うC-S-HのCaO/SiO₂の低下と吸着能力には相関関係があることが確認できた。また、この相関関係を用い、異なるCaO/SiO₂のC-S-Hの塩化物イオン吸着量を推定できる式を提案した。]]></description>
      <pubDate>Fri, 22 May 2015 16:14:07 GMT</pubDate>
      <guid>https://trid.trb.org/View/1351665</guid>
    </item>
    <item>
      <title>EVALUATION ON BEHAVIOR OF CEMENT HARDEND BODY DUE TO LONG TERM LEACHING AND HYDRATION</title>
      <link>https://trid.trb.org/View/1351627</link>
      <description><![CDATA[Structures made of cement based materials deteriorate by various factors. Calcium is a main component of a cementitious material, which is hardened with hydration process of cement. When water percolates into the cement hardened body under saturated conditions, the hydration products dissolve into pore solution and Calcium ions leach out from the hardened body, which makes its permeability become low. Since this phenomenon proceeds very slowly, it is not regarded as important deterioration in normal concrete structures. In radioactive waste processing structures, however, long-term durability is obviously required. In the above-mentioned case, it is necessary to consider deterioration due to Calcium leaching. The assessment of a change in quality of cement-hardened body due to Calcium leaching includes an immersion experiment and an electrical accelerating experiment. In this study, the immersion experiment and the electrical accelerating experiment were performed to evaluate the stability of cement-hardened body with the long-term Calcium leaching. As the results, it was confirmed that Calcium leaching from Ca(OH)₂ is easy to occur in the real diffusion phenomenon, which is generally known on durability against Calcium leaching, and the long-term electrical accelerating treatment was able to simulate Calcium leaching from Ca(OH)₂ in the real diffusion phenomenon and identify the influence of W/C and curing period on the durability of cement-hardened. Moreover, the electrical acceleration technique could be sufficiently applied to evaluate the influences of curing period and w/c ratio on the calcium leaching. The developed technique was further applied to obtain an insight into the long-term behavior of material up to 100 years.長期に亘り影響が懸念される溶脱現象を短期間で再現することを目的とした装置を作製した。これにより得られる溶脱現象に伴うセメント硬化体特性に関する情報を取得するとともに、電気的手法と浸漬法におけるCa溶脱現象の差異を確認することを目的とした。その結果、Caイオンの溶出あるいはCa（OH）<sub>2</sub> の消失について、実際の現象を再現できる可能性を示すことができた。特に、養生期間が短く、W/Cが高い場合ほど溶脱抵抗性は低く、溶脱現象の進行速度が速くなることを再現するとともに、Ca（OH）<sub>2</sub> の消失と関連づけて評価可能であることがわかった。さらに、長期にわたる溶脱現象の再現に必要な促進期間と溶脱抵抗性には相関が認められた。]]></description>
      <pubDate>Thu, 30 Apr 2015 09:23:48 GMT</pubDate>
      <guid>https://trid.trb.org/View/1351627</guid>
    </item>
    <item>
      <title>Durability and Safety of Concrete Structures in the Nuclear Context</title>
      <link>https://trid.trb.org/View/1141129</link>
      <description><![CDATA[In the field of nuclear energy, very challenging durability problems are being faced, such as how could the service life of present nuclear containments be prolonged and how can the durability of a radioactive storage on the very long term (several centuries) be assured? These difficult questions in a classical civil engineering view are even more complicated in the field of nuclear energy where the structures are massive and the safety of the installations has to be considered with specific care due to the related stakes. For concrete structures like the containment of nuclear power plants and the storages of radioactive waste, these stakes will be clarified with some examples of research concerning the mechanical behavior of concrete and concrete structures (at early age, in service on long scales of time and in the event of an accident), the durability of the concrete structures (leaching, swelling due to DEF) and the couplings between mechanics and durability. Finally, the importance of probabilistic aspects in durability and the inherent difficulties will be shown.]]></description>
      <pubDate>Mon, 25 Jun 2012 09:39:10 GMT</pubDate>
      <guid>https://trid.trb.org/View/1141129</guid>
    </item>
    <item>
      <title>New York State Low-Level Radioactive Waste Status Report for 1999</title>
      <link>https://trid.trb.org/View/864053</link>
      <description><![CDATA[This report summarizes data on low-level radioactive waste (LLRW) generated in New York State. It is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (NYSERDA) and on data from the U.S. Department of Energy (U.S. DOE). The New York State Low-Level Radioactive Waste Management Act (State Act) requires LLRW generators in the State to submit annual reports detailing the classes and quantities of waste generated. Section 1 covers volume, activity, and other characteristics of waste shipped for disposal in 1999. Section 2 summarizes volume, activity, and other characteristics of waste held for storage as of December 31, 1999. Section 3 shows historical LLRW generation and includes generators' projections for the next five years. Section 4 provides a list, by country, of all facilities from which 1999 LLRW reports were received.]]></description>
      <pubDate>Thu, 17 Jul 2008 09:23:56 GMT</pubDate>
      <guid>https://trid.trb.org/View/864053</guid>
    </item>
    <item>
      <title>THE TIME HAS COME FOR THE GOVERNMENT TO DEVELOP AND IMPLEMENT A TRANSPORTATION PLAN FOR YUCCA MOUNTAIN</title>
      <link>https://trid.trb.org/View/741753</link>
      <description><![CDATA[This article explores the 20-yr-old debate over the Yucca Mountain repository, and specifically the issues surrounding the transportation of hazardous waste. The Yucca Mountain Project is a proposed storage site for nuclear waste in the Nevada desert. Both opponents' contentions and arguments of supporters of this controversial program are examined. As a critical part of any proposed centralized shipment and storage of nuclear waste, the additional constraints imposed on the transportation industry as a result of the terrorist attacks of September 11, 2001 are also considered and discussed.]]></description>
      <pubDate>Mon, 20 Sep 2004 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/741753</guid>
    </item>
    <item>
      <title>THE CURRENT STATUS, SAFETY, AND TRANSPORTATION OF SPENT NUCLEAR FUEL</title>
      <link>https://trid.trb.org/View/689485</link>
      <description><![CDATA[The total estimated amount of spent nuclear fuel in the United States is 50,000 metric tons of heavy metal.  This paper provides an overview of the characteristics and properties of spent nuclear fuel, and discusses how to ensure the safety of its transportation and disposal.  A new repository is scheduled to be in operation by 2010 for the disposal of this fuel.  Strong evidence is cited that suggests that operations involving spent nuclear fuel can be done safely.  However, experience is limited in terms of the magnitude and repository-specific activities expected for future operations.  More emphasis should be placed on repository-specific operations, such as the safety of specific shipping routes to the proposed repository.  This author suggest that two actions should be taken:  (1) the record of experience with the shipping of spent nuclear fuel should be made available in a factual, understandable and comprehensive form; and (2) realistic risk studies should be conducted of alternative routes and means of transporting spent nuclear fuel to the repository site.]]></description>
      <pubDate>Fri, 13 Feb 2004 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/689485</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>HANFORD SITE ANNUAL DANGEROUS WASTE REPORT. WASTE MANAGEMENT FACILITY REPORT DANGEROUS WASTE</title>
      <link>https://trid.trb.org/View/630709</link>
      <description><![CDATA[No abstract provided.]]></description>
      <pubDate>Sun, 24 Feb 2002 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/630709</guid>
    </item>
    <item>
      <title>NEW ACCELERATED LEACHING EXPERIMENT: THE LIFT PROCEDURE</title>
      <link>https://trid.trb.org/View/539199</link>
      <description><![CDATA[In the past decades, cement-based materials have been increasingly used for the construction of radioactive-waste barriers.  The design of durable structures for this specific application requires a precise knowledge of the evolution of the material engineering properties over a 1000-year period.  Among the wide range of degradation phenomena to which the structure can be exposed during its service life, the leaching of calcium appears to be the most critical.  Given the intricate nature of the leaching process, a reliable prediction of the long term behavior of the concrete barriers can only be made through numerical modeling.  In order to generate more quantitative information on the subject, a new accelerated leaching test has been developed.  The operating principle of the test is quite simple.  The leaching process is accelerated by applying an external electric field through the material.  This paper details the different electrochemical phenomena involved during a LIFT experiment.  It also presents experimental data obtained for various neat paste samples.  In this series of tests, the evolution of the hydrated cement paste microstructure was studied using various experimental techniques, such as X-ray diffraction, DTA/TG analyses and scanning electron microscopy. The advantages and limitations of this new procedure are discussed.]]></description>
      <pubDate>Wed, 16 Sep 1998 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/539199</guid>
    </item>
    <item>
      <title>ENVIRONMENTAL ASSESSMENT ACCESS ROAD FROM STATE ROUTE 240 TO THE 200 WEST AREA.</title>
      <link>https://trid.trb.org/View/630717</link>
      <description><![CDATA[No abstract provided.]]></description>
      <pubDate>Mon, 24 Feb 1997 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/630717</guid>
    </item>
    <item>
      <title>OVERVIEW OF THE SPENT NUCLEAR FUEL PROJECT AT HANFORD.</title>
      <link>https://trid.trb.org/View/630812</link>
      <description><![CDATA[No abstract provided.]]></description>
      <pubDate>Mon, 24 Feb 1997 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/630812</guid>
    </item>
    <item>
      <title>ENVIRONMENTAL ASSESSMENT FOR THE RADIOACTIVE AND MIXED WASTE MANAGEMENT FACILITY.</title>
      <link>https://trid.trb.org/View/630699</link>
      <description><![CDATA[No abstract provided.]]></description>
      <pubDate>Mon, 24 Feb 1997 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/630699</guid>
    </item>
    <item>
      <title>AN ASSESSMENT OF THE VIABILITY OF STORING FFTF SODIM IN TANK CARS.</title>
      <link>https://trid.trb.org/View/522449</link>
      <description><![CDATA[No abstract provided.]]></description>
      <pubDate>Fri, 22 Dec 1995 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/522449</guid>
    </item>
    <item>
      <title>FIELD CHARACTERIZATION PLAN FOR THE 216-U-8 VITRIFIED CLAY PIPELINE.</title>
      <link>https://trid.trb.org/View/522451</link>
      <description><![CDATA[No abstract provided.]]></description>
      <pubDate>Fri, 22 Dec 1995 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/522451</guid>
    </item>
    <item>
      <title>AN ASSESSMENT OF THE VIABILITY OF STORING FFTF SODIUM IN TANK CARS.</title>
      <link>https://trid.trb.org/View/522461</link>
      <description><![CDATA[No abstract provided.]]></description>
      <pubDate>Fri, 22 Dec 1995 00:00:00 GMT</pubDate>
      <guid>https://trid.trb.org/View/522461</guid>
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