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Use of the Streaming Matrix Hybrid Method for discrete-ordinates fusion reactor calculations

Conference ·
OSTI ID:6911868
; ; ;
The use of the discrete-ordinates method for solving two-dimensional, neutral-particle transport in fusion reactor blankets and shields is often limited by inherent inaccuracies due to the ray-effect. This effect presents a particular problem in the case of neutron streaming in the large internal void regions of a fusion reactor. A deterministic streaming technique called the Streaming Matrix Hybrid Method (SMHM) has been incorporated in the two-dimensional discrete-ordinates code TRIDENT-CTR. Calculations have been performed for an actual inertial-confinement fusion (ICF) reactor design using TRIDENT-CTR both with and without the SMHM. Comparisons of the calculated fluxes indicate that substantial mitigation of the ray effect can be achieved with the SMHM. Calculations were performed for the Los Alamos FIRST STEP hybrid ICF reactor designed for tritium production. Conventional /sup 238/U fuel rod assemblies surround the spherical steel target chamber to form an annular cylindrical blanket. An axial fuel region is included to complete the blanket.
Research Organization:
Los Alamos National Lab., NM (USA)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
6911868
Report Number(s):
LA-UR-84-170; CONF-840614-18; ON: DE84006019
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BREEDING BLANKETS
COMPUTER CALCULATIONS
CONFINEMENT
DISCRETE ORDINATE METHOD
EVEN-EVEN NUCLEI
HEAVY NUCLEI
INERTIAL CONFINEMENT
ISOTOPES
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEI
PLASMA CONFINEMENT
RADIATION STREAMING
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
URANIUM 238
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES