2 edition of Multi-purpose canister system evaluation found in the catalog.
Multi-purpose canister system evaluation
1994 by U.S. Dept. of Energy, Office of Civilian Radioactive Waste Management in Washington, DC .
|Contributions||United States. Dept. of Energy. Office of Civilian Radioactive Waste Management|
|The Physical Object|
|Pagination||1 v. (various pagings)|
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Aug 13, · Multi-purpose canister system evaluation by,U.S. Dept. of Energy, Office of Civilian Radioactive Waste Management edition, Microform in English. Get this from a library.
Multi-purpose canister system evaluation: a systems engineering approach. [United States. Department of Energy. Office of Civilian Radioactive Waste Management.;].
The basis of comparison will be the conceptual design Multi-Purpose Canister (MPC) PWR waste package concepts. The objectives of this evaluation are to show that the criticality potential of the MOX fuel is equal to or lower than the DBF or, if necessary, indicate what. Abstract.
A multipurpose canister (MPC) made of austenitic stainless steel is loaded with used nuclear fuel assemblies and is part of the transfer cask system to move the fuel from the spent fuel pool to prepare for storage, and is part of the storage cask system for on-site dry storage.
The cask system design includes insertion of the US DOE Multi-Purpose Canister inside the DUCRETE cask. The economic comparison is from the time a cask is loaded in a spent fuel pool until it is placed in the repository and includes the utility and overall US system perspectives.
The dry-cask storage allows the SNF, which has already been cooled in the ISSF, to lower its radiation exposure and heat decayat a very low level. Design of the dry cask storage for SNF has been done.
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A typical multipurpose canister (MPC) is made of austenitic stainless steel and is loaded with spent nuclear fuel (SNF) assemblies. Because heat treatment for stress relief is not required for the construction of the MPC, the canister is susceptible to stress corrosion cracking in the weld or heat affected zone (HAZ) regions under long-term storage bookarchivesly.icu by: 1.
Dry cask storage is a method of storing high-level radioactive waste, such as spent nuclear fuel that has already been cooled in the spent fuel pool for at least one year and often as much as ten years. Casks are typically steel cylinders that are either welded or bolted closed.
The fuel rods inside are surrounded by inert bookarchivesly.icuy, the steel cylinder provides leak-tight containment of the. system is designed as a horizontal concrete module ().
6 The principal characteristics of dry cask storage systems are summarized in TABLEwhich is located at the end of this bookarchivesly.icu casks are designed to hold up to about 10 to 15 metric tons of spent fuel.
This is equivalent to about 32 pressurized water nuclear reactor (PWR) spent fuel assemblies or 68 boiling water nuclear reactor.
Learn more about the Ford Fusion. See the Ford Fusion price range, expert review, consumer reviews, safety ratings, and listings near you/5. To verify the effectiveness of surface treatment techniques on the commercialized canister, a mock-up bottom part of the Multi-Purpose Canister (MPC) (weight tons) with full-scale diameter ( mm) and wall thickness ( mm) was manufactured made of Type L SS using the laser welding bookarchivesly.icu: T.
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The NRC's evaluation and approval of the certification of the original HI-STORM FW System included an evaluation of the susceptibility to, and effects of, stress corrosion cracking and other corrosion mechanisms on safety-significant systems for spent nuclear fuel (SNF) dry cask storage (DCS) systems during an initial year certification period.
The Nuclear Regulatory Commission (NRC) is amending its regulations to add the NAC Universal Storage System (NAC-UMS) cask system to the list of approved spent fuel storage casks.
This amendment allows the holders of power reactor operating licenses to. UMS stands for ``Universal MPC System,'' where MPC is intended to indicate ``multi-purpose canister.'' Comment A One commenter agreed with one of the State's published comments.
Several comments also were made on topics pertaining to the decommissioning of the Maine Yankee site. With respect to the committee’s task to examine potential safety and security advantages of dry cask storage using various single- dual- or multi-purpose cask designs, the committee offers the following findings and recommendations.
Feb 27, · The canister in the concrete cask storage system is filled with helium gas, and its containment should be maintained and inspected during storage.
The helium gas enhances heat removal from spent fuel. When the helium gas leaked, the effect of helium convection is weakened in the canister.
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For the Fiscal Reporting Period February March 17, PMPR No. March 31, 2i/51 / Evaluation Division of Industrial & Medical Nuclear Safety Multi-Purpose Canister Monitored Retrievable Storage MSS NAS NAWG NCR NFS NMSS NOAA NRC NSRRC NTS NWPA NWTRB.
Apr 16, · Some will recall that March 9th was the comment deadline for another of Holtec's attempts to decrease safety by asking for exemptions re dry cask storage of damaged spent nuclear fuel rods, and other safety related exemptions.
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