P{sup N}FE component of the UNIC code.
Abstract
A code package called UNIC is currently under development at Argonne (Argonne National Laboratory). This new code package is focused on high fidelity solutions for nuclear reactor plant operations. The focus of this paper is the development of a spherical harmonics method used to solve the neutron transport equation. This new code, called P{sub N}FE, is just one of the components of UNIC. P{sub N}FE is targeted for use on massively parallel platforms using the PETSc library developed at ANL. In this paper, an overview of the theory behind the spherical harmonics method is given along with some results obtained with a parallel implementation of the code.
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Org.:
- NE
- OSTI Identifier:
- 977023
- Report Number(s):
- ANL/NE/CP-58818
TRN: US1002701
- DOE Contract Number:
- DE-AC02-06CH11357
- Resource Type:
- Conference
- Resource Relation:
- Conference: Joint International Topical Meeting on Mathematics & Computations and Supercomputing in Nuclear Applications (M&C + SNA 2007); Apr. 15, 2007 - Apr. 19, 2007; Monterey, CA
- Country of Publication:
- United States
- Language:
- ENGLISH
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 97 MATHEMATICAL METHODS AND COMPUTING; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; U CODES; ANL; REACTOR OPERATION; NEUTRON TRANSPORT; SPHERICAL HARMONICS METHOD; P CODES; PARALLEL PROCESSING
Citation Formats
Smith, M. A., Palmiotti, G., Rabiti, C., Kaushik, D., Siegel, A., Smith, B., Lewis, E. E., and Northwestern Univ.. P{sup N}FE component of the UNIC code.. United States: N. p., 2007.
Web.
Smith, M. A., Palmiotti, G., Rabiti, C., Kaushik, D., Siegel, A., Smith, B., Lewis, E. E., & Northwestern Univ.. P{sup N}FE component of the UNIC code.. United States.
Smith, M. A., Palmiotti, G., Rabiti, C., Kaushik, D., Siegel, A., Smith, B., Lewis, E. E., and Northwestern Univ.. Mon .
"P{sup N}FE component of the UNIC code.". United States.
doi:.
@article{osti_977023,
title = {P{sup N}FE component of the UNIC code.},
author = {Smith, M. A. and Palmiotti, G. and Rabiti, C. and Kaushik, D. and Siegel, A. and Smith, B. and Lewis, E. E. and Northwestern Univ.},
abstractNote = {A code package called UNIC is currently under development at Argonne (Argonne National Laboratory). This new code package is focused on high fidelity solutions for nuclear reactor plant operations. The focus of this paper is the development of a spherical harmonics method used to solve the neutron transport equation. This new code, called P{sub N}FE, is just one of the components of UNIC. P{sub N}FE is targeted for use on massively parallel platforms using the PETSc library developed at ANL. In this paper, an overview of the theory behind the spherical harmonics method is given along with some results obtained with a parallel implementation of the code.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}
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COMPILATION OF CROSS SECTIONS FOR SOME NEUTRON INDUCED THRESHOLD REACTIONS: Mg$sup 24$(n,p)Na$sup 24$, Al$sup 27$(n,/cap alpha/)Na$sup 24$, Al$sup 27$(n,p)Mg$sup 27$, P$sup 31$(n,p)Si$sup 31$, S$sup 32$(n,p)P$sup 32$, Fe$sup 54$(n,p)Mn$sup 54$, Fe$sup 56$(n,p)Mn$sup 56$, Ni$sup 58$(n,p)Co$sup 58$
Cross sections for neutron threshold reactions (n,p) with Mg/sup 24/, Al/ sup 27/, Pa/sup 31/, S/sup 32/, Fe/sup 54/, Fe/sup 56/, and Ni/sup 58/ and for the (n, alpha ) reaction with Al/sup 27/ are presented. The cross-section values are printed on several sheets of transparent paper enabling a survey of a given series of measurements separately as well as permitting the intercomparison of different measuring series. Uncertainties of cross section values and neutron energies are indicated. The figures of merit for the reactions are also included. (C.E.S.) -
Simultaneous evaluation of 32S(n,p), 56Fe(n,p), 65Cu(n,2n) cross sections
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Evaluations of the /sup 58/Fe(n,. gamma. )/sup 59/Fe, and /sup 54/Fe(n,p)/sup 54/Mn reactions for the ENDF/B-V dosimetry file. [E < 15 MeV]
A generalized least-squares adjustment procedure was used to evaluate two important dosimetry reactions for the ENDF/B-V files. Calculations for the cross section adjustments were made with the computer code FERRET, where input data included both integral and differential experimental data results. For the /sup 54/Fe reaction, important ratio measurements were renormalized to ENDF/B-V evaluations of /sup 235/U(n,f), /sup 238/U(n,f), and /sup 56/Fe(n,p). A priori curves which are required for the calculations were obtained using Hauser-Feshbach calculations from the codes NCAP (/sup 58/Fe) and HAUSER-5 (/sup 54/Fe). Covariance matrices were also calculated and are included in the evaluations. 8 figures, 1more » -
Measurement of the {sup 59}Co(n,{alpha}){sup 56}Mn, {sup 59}Co(n,p){sup 59}Fe and {sup 59}Co(n,2n){sup 58m+g}Co cross sections between 8 and 14 MeV
The cross sections of {sup 59}Co(n,{alpha}), {sup 59}Co(n,p) and {sup 59}Co(n,2n) have been measured in the energy range 8.1-14.3 MeV. Substantial differences between our data and recent evaluations were identified for {sup 59}Co(n,2n) in the threshold region, for {sup 59}Co(n,p) below 13 MeV neutron energy and for {sup 59}Co(n,{alpha}) over the entire energy range.