Thermal analysis of NNWSI conceptual waste package designs

Stein, W.; Hockman, J.N.; O'Neal, Welton

doi:10.2172/59316

Cited by 7 publications

(7 citation statements)

References 1 publication

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“…Calculated waste package temperatures for all of the reference and alternative designs are within the temperature limits imposed to avoid wasteform degradation (Stein et al, 1984). These limits are 350°C for spent fuel (cladding), 400°C for CHLW, and 500°C for VW/DHLW.…”

Section: Thermal Analysismentioning

confidence: 76%

“…At a temperature of 180°C the internal he lium pressure of the rods is 845 psig. A calculation using the computer code TAC02D (Stein, 1984) in dicates that the fuel rod ends, in contact with air space at the top and bottom of the canister, reach roughly 700°C during the 800°C, 30-min fire test. The hoop stress in the Zircaloy cladding at 845 psig pressure is 5591 psi, which is roughly 5.6 times greater than the Zircaloy yield strength at 700 to 800°C (-1000 psi).…”

Section: Fire Test Structural Analysismentioning

confidence: 99%

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Preclosure analysis of conceptual waste package designs for a nuclear waste repository in tuff

O'Neal¹,

Gregg²,

Hockman³

et al. 1984

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DISCLAIMERThie report wee prepared u an account of work tponeond by an agency of the UsJted SUM Government Netthw the Uaited Sutaa Oonmment swr any aneocy thereof, nor any of their iwHcyin, makae any warranty, txpreM or implied, or ajramei any legal liability or tatsontieiifcy for the aonracy, completeneM, or HHMMI of any infornation, appantw, product, or prooe* djedoeed, or reprmati that iti ma would not infringe privately owned rithu. Refer ence herein to any apeeiffc commercial product, proowi, or aervice by trade name, trademark, BtaMfactarer, or otherwiee doei not aeceewrily eonttitute or imply itt endonement, recommendatioe, or favoriat by the United Sutaa Oovernmaat or any agency thereof. Vx> viewi awl opinion* of authon eupmeed herein do not neceeserily Mate or reflect tboee of the United Statu Gwei-int or any anency thereof. LAWRENCE LIVERMORE NATIONAL LABORATORY Executive tUnder the direction of the Office of Civilian Radioactive Waste Management, the Department of Energy's (DOE) Nevada Nuclear Waste Storage Investigations (NNWSI) project is evaluating a candidate repository site at Yucca Mountain, Ne vada, for permanent disposal of high level nuclear waste. The Lawrence Livermore National Labora tory (LLNL), a participant in the NNWSI project, is developing waste package designs to meet NRC requirements. Included are designs for the refer ence waste form configurations of: (1) spent fuel (SF), which consists of both consolidated and un consolidated spent fuel rods from pressurizedwater-reactor (PWR) and boiling-water-reactor (BWR) assemblies, (2) commercial high level waste (CHLW), as a borosilicate glass containing commercial spent fuel reprocessing wastes, and (3) West Valley/defense high level waste (WV/ DHIW) immobilized in borosilicate glass. Refer ence and alternative package designs have been developed for each waste form for both vertical and horizontal emplacement configurations. All designs are for emplacement in a tuff repository located above the water table (in the vadose zone).Conceptual designs and analyses for waste packages in tuff below the water table were devel oped for the Office of Nuclear Waste Isolation Summary (ONWI) by Westinghouse Electric Corporation in 1981 -82 (Westinghouse, 1983. The candidate hori zon was changed by NNWSI to the vadose zone in late 1982 (Vieth, 1982;Dudley and Erdal, 1982). LLNL has made changes in and additions to the conceptual designs to reflect this change in the re pository location. Analyses have been performed to determine conformance of the selected design ensemble to NRC design requirements in the cur rently understood repository environment. Fig ure 1 shows the reference conceptual designs. The selected designs (Gregg and O'Neal, 1983) include reference and alternative designs that vary in com plexity, performance, and cost.From this ensemble, one set of designs (for SF, CHLW, and WV/DHIW) will be chosen which is expected to meet Nuclear Regulatory Commission (NRC)/Environmental Protection Agency (EPA) requirements when analyzed with accura...

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Section: Thermal Analysismentioning

confidence: 76%

Section: Fire Test Structural Analysismentioning

confidence: 99%

Preclosure analysis of conceptual waste package designs for a nuclear waste repository in tuff

O'Neal¹,

Gregg²,

Hockman³

et al. 1984

Self Cite

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“…1 Based on the maximum heat that the fuel bundles could release, we calculated the average heat density (0.24 W/in.…”

Section: Discussionmentioning

confidence: 99%

Thermal and stress analysis of hot isostatically pressed, alumina ceramic, nuclear waste containers

Chang¹,

Hoenig²

1990

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“…Early conceptual developments identifying EBS processes and time evolution for ihe expected conditions scenario appeared in several reports, e.g., the refer^ice environment for the waste packages, 3 thermal analysis, 4 and a "bathtub" water » contact mode for waste form alteration and radionuclide release. 5 The EBS scenarios activity has been expanded (SCP 2 Section 8.3.5.10.3.1) to address an NRC concern to assure attention to scenarios impacting the EBS subsystem, and to systematize the scenarios at the EBS scale and the EBS processes and event histories consequent to a scenario initiator.…”

Section: Ebs Scenariosmentioning

confidence: 99%

Status of integrated performance assessment of the waste packages and engineered barrier system

1992

International Journal of Rock Mechanics and Mining Sciences &am

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Performance assessment of the engineered barrier system for a nuclear waste repository combines information from relevant disciplines and predicts the net long-term performance of the EBS in units of regulatory goals for performance. The performance assessment models are .specific to the proposed Yucca Mountain, Nevada site. Early assessments are used for project planning and feedback. The EBS scenarios activity develops the scenarios and the consequent event sequences. Initial model development for single waste packages indicates that the radionuclide release rate performance is sensitive to the water flux, element solubil ities, and/or the mode of water contact with the waste. The latter in turn depends on local scale hydrology and the modes of corrosion for the container material. For the release rate summed over waste packages, variations among waste packages and their near-field environments are anticipated. These variations place demands on data acquisition and modeling, as well as modulate the impact of localized changes of conditions. Sampling in uncertainty assessment is a subsequent step in examining the reliability of predictions made in the performance assessments. Advances made in sampling methods arc referenced.

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Thermal analysis of NNWSI conceptual waste package designs

Cited by 7 publications

References 1 publication

Preclosure analysis of conceptual waste package designs for a nuclear waste repository in tuff

Preclosure analysis of conceptual waste package designs for a nuclear waste repository in tuff

Thermal and stress analysis of hot isostatically pressed, alumina ceramic, nuclear waste containers

Status of integrated performance assessment of the waste packages and engineered barrier system

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