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Title: VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport

Abstract

The computer code block VENTURE, designed to solve multigroup neutronics problems with application of the finite-difference diffusion-theory approximation to neutron transport (or alternatively simple P$sub 1$) in up to three- dimensional geometry is described. A variety of types of problems may be solved: the usual eigenvalue problem, a direct criticality search on the buckling, on a reciprocal velocity absorber (prompt mode), or on nuclide concentrations, or an indirect criticality search on nuclide concentrations, or on dimensions. First- order perturbation analysis capability is available at the macroscopic cross section level. (auth)

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., Tenn. (USA)
OSTI Identifier:
4158202
Report Number(s):
ORNL-5062
NSA Number:
NSA-33-006854
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 30-JUN-76
Country of Publication:
United States
Language:
English
Subject:
N79100* -Reactors-Reactor Theory & Calculation; 220100* -Nuclear Reactor Technology-Theory & Calculation; *COMPUTER CODES- V CODES; *REACTOR KINETICS- NEUTRON TRANSPORT THEORY; CRITICALITY; EIGENVALUES; FINITE DIFFERENCE METHOD; NEUTRON DIFFUSION EQUATION

Citation Formats

Vondy, D.R., Fowler, T.B., and Cunningham, G.W.. VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport. United States: N. p., 1975. Web. doi:10.2172/4158202.
Vondy, D.R., Fowler, T.B., & Cunningham, G.W.. VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport. United States. doi:10.2172/4158202.
Vondy, D.R., Fowler, T.B., and Cunningham, G.W.. Wed . "VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport". United States. doi:10.2172/4158202. https://www.osti.gov/servlets/purl/4158202.
@article{osti_4158202,
title = {VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport},
author = {Vondy, D.R. and Fowler, T.B. and Cunningham, G.W.},
abstractNote = {The computer code block VENTURE, designed to solve multigroup neutronics problems with application of the finite-difference diffusion-theory approximation to neutron transport (or alternatively simple P$sub 1$) in up to three- dimensional geometry is described. A variety of types of problems may be solved: the usual eigenvalue problem, a direct criticality search on the buckling, on a reciprocal velocity absorber (prompt mode), or on nuclide concentrations, or an indirect criticality search on nuclide concentrations, or on dimensions. First- order perturbation analysis capability is available at the macroscopic cross section level. (auth)},
doi = {10.2172/4158202},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1975},
month = {10}
}