EMSP project summary (Project ID: 60077): Development of nuclear analysis capabilities for DOE waste management activities | Zendy

C.V. Parks | Zendy; Bradley T. Rearden | Zendy; Mark D. DeHart | Zendy; B.L. Broadhead | Zendy; C.M. Hopper | Zendy; L.M. Petrie | Zendy

Open Access

EMSP project summary (Project ID: 60077): Development of nuclear analysis capabilities for DOE waste management activities

Author(s) -

C.V. Parks,

Bradley T. Rearden,

Mark D. DeHart,

B.L. Broadhead,

C.M. Hopper,

L.M. Petrie

Publication year - 2000

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/754354

Subject(s) - criticality , computer science , fissile material , grid , reliability engineering , process (computing) , spent nuclear fuel , monte carlo method , systems engineering , engineering , nuclear engineering , physics , geometry , mathematics , quantum mechanics , neutron , nuclear physics , operating system , statistics

The objective of this project is to develop and demonstrate prototypical analysis capabilities that can be used by nuclear safety analysis practitioners to: (1) demonstrate a more thorough understanding of the underlying physics phenomena that can lead to improved reliability and defensibility of safety evaluations; and (2) optimize operations related to the handling, storage, transportation, and disposal of fissile material and DOE spent fuel. To address these problems, this project has been investigating the implementation of sensitivity and uncertainty methods within existing Monte Carlo codes used for criticality safety analyses. It is also investigating the use of a new deterministic code that allows for specification of arbitrary grids to accurately model geometric details required in a criticality safety analysis. This capability can facilitate improved estimations of the required subcritical margin and potentially enable the use of a broader range of experiments in the validation process. The new arbitrary-grid radiation transport code will also enable detailed geometric modeling valuable for improved accuracy in application to a myriad of other problems related to waste characterization. Application to these problems will also be explored

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