Mathematical and computational problems in reactor calculations
From national topical meeting on mathematical models and computational techniques for analysis of nuclear systems; Ann Arbor, Michigan, USA (8 Apr 1973). In mathematical models and computational techniques for analysis of nuclear systems. Two computational problems connected with the solution of the neutron diffusion equation and neutron transport equation are considered. The first problem, called the local problem arises from the presence of material interfaccs and their effect on the differentiability of the solution. The second problem, called the globsl problem concerns lattice geometries and the use of homogenization procedures. For both problems there is given an informal discussion of the mathematical situation and of some numerical experiments. 19 references. (auth)
- Research Organization:
- Univ. of Maryland, College Park; American Nuclear Society. Michigan Section
- NSA Number:
- NSA-29-007181
- OSTI ID:
- 4392324
- Report Number(s):
- CONF-730414--P2
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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