Published 1995 | Version v1
Journal article

Multigroup cross-section generation with spatial and angular adjoint weighting

  • 1. Pennsylvania State Univ., University Park, PA (United States)

Description

The multigroup discretization is the most common technique used to treat the energy variable in deterministic transport methods. In contrast, most Monte Carlo simulations are able to use the piecewise linear continuous, or pointwise, energy discretization. Monte Carlo simulations may thus be used to benchmark approximations made in multigroup calculations. Several such benchmarks and other studies have been applied to the problem of light water reactor pressure vessel fluence determination and reduction at Pennsylvania State University. These studies indicate that a significant portion of the discrepancy between Monte Carlo and deterministic calculations may be attributed to the techniques used to generate multigroup constants

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
73
Journal Page Range
p. 175-177.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
Winter meeting of the American Nuclear Society (ANS).
Dates
29 Oct - 1 Nov 1995.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28018821
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; CALCULATION METHODS; CROSS SECTIONS; MULTIGROUP THEORY; NEUTRON FLUENCE; NEUTRON TRANSPORT THEORY; REACTOR PHYSICS; WATER COOLED REACTORS
Descriptors DEC
REACTORS; TRANSPORT THEORY

Optional Information

Secondary number(s)
CONF-951006--.