XLACS A Program to Produce Weighted Multigroup Neutron Cross Sections from ENDF/B

Greene, N.M.; Lucius, J.L.; White, J. E.; Wright, R.Q.; Craven, C.W.; Tobias, M.L.

doi:10.13182/nse73-a26579

Cited by 6 publications

(2 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The cross-section processing code XLACS [8] was used to process the ENDF/B-3 data into a broad group energy structure consisting of one hundred groups with the top ninety-nine groups in the GAM-II [9] energy group structure and one thermal group. Resonance self-shielding of the niobium capture cross-section was computed by the method of Nordheim [10] as programmed in the XSDRN code.…”

Section: Blanket Model and Calculational Proceduresmentioning

confidence: 99%

Mikhail Shlyomovich Birman (on his 70th birthday)

Buslaev¹,

Вершик²

2000

Russ. Math. Surv.

View full text Add to dashboard Cite

The authors have examined the cross-section sensitivity of the tritium-breeding ratio in a fusion reactor blanket model which is representative of a large class of blanket configurations under current investigation. This blanket model exhibits the following tritium-breeding and neutronic characteristics: (1) liquid lithium of natural isotopic abundance is used for breeding; (2) the tritium-breeding ratio is in the "high" range, ~ 1. 5; (3) graphite is employed for neutron moderation; and (4) the neutron leakage from the blanket is relatively low, ~4% of the source neutrons. The sensitivity of the breeding ratio was evaluated by altering reference cross-section sets to reflect estimates of the uncertainties in the cross-section of the 6 Li(n,a)t, the 7 Li(n,n'a)t, and the 93 Nb(n,2n) reactions. Our analysis leads to the following observations:

show abstract

Section: Blanket Model and Calculational Proceduresmentioning

confidence: 99%

Mikhail Shlyomovich Birman (on his 70th birthday)

Buslaev¹,

Вершик²

2000

Russ. Math. Surv.

View full text Add to dashboard Cite

show abstract

“…BONAMI produces a Bondarenko-corrected master format library which is read by NITAWL-II. 13 For SCALE libraries the Bondarenko technique is used primarily to process unresolved region resonance data and for processing resonance nuclides which were not prepared by XLACS 14 (such as the SCALE 16-group Hansen-Roach library or ENDF/B-VI nuclides processed with NJOY 15 ). For the 27-group master cross-section library used in this validation, the primary purpose of the BONAMI functional module is to select the required material cross sections and to create a problem-dependent AMPX master cross-section library to be processed by NITAWL-II.…”

Section: Bonamimentioning

confidence: 99%

Guide to verification and validation of the SCALE-4 criticality safety software

Emmett¹,

Jordan²

1996

View full text Add to dashboard Cite

Whenever a decision is made to newly install the SCALE nuclear criticality safely software on a computer system, the user should run a set of verification and validation (V&V) test cases to demonstrate that the software is properly installed and functioning correctly. This report is intended to serve as a guide for this V&V in that it specifies test cases to run and gives expected results. The report describes the V&V that has been performed for the nuclear criticality safety software in a version of SCALE-4. 1 The verification problems specified by the code developers have been run, and the results compare favorably with those in the SCALE 4.2 baseline. 2 The results reported in this document are from the SCALE 4.2P version which was run on an IBM RS/6000 workstation. These results verify that the SCALE-4 nuclear criticality safely software has been correctly installed and is functioning properly. A validation has been performed for KENO V.a 3 utilizing the CSAS25 (ref. 4) criticality sequence and the SCALE 27-group cross-section library for ^U, 235 U, and 239 Pu fissile systems in a broad range of geometries and fissile fuel forms. The experimental models used for the validation were taken from three previous validations of KENO V.a. A statistical analysis of the calculated results was used to determine the average calculational bias and a subcriticai k,. ff criteria for each class of systems validated. Included in the statistical analysis is a means of estimating the margin of subcriticality in k^. This validation demonstrates that KENO V.a and the 27-group library may be used for nuclear criticality safety computations provided the system being analyzed falls within the range of the experiments used in the validation.

show abstract

Fast Reactor Cross-Section Processing Codes - Is There a Dollars Worth of Difference Between Them?

Weisbin¹,

Greene²,

Henryson³

et al. 1975

Advanced Reactors: Physics, Design and Economics

View full text Add to dashboard Cite

Since we do not live in an idealized world with infinite computational and monetary resources, the question of dollars worth of difference between ENDF/B cross-section processing codes for fast reactor calculations must be addressed with respect to both the accuracy required in the multigroup constants and the cost of obtaining that accuracy. Unfortunately, no single processing code is an obvious choice since the practical effect of different processing techniques on important reactor parameters is problem dependent* Therefore, it is the purpose of this paper to discuss the range of applicability of several multigroup averaging programs widely used in the United States, as well as the effort that must be expended in using them. Th° programs selected from the authors' experience include AMPX (1), MOIX( i 2 J .3)/SPHINX(4), ETOE-2/MC 2 -2/SDX(5), and ETGX(6) /1DX(2) • As is apparent these programs are often systems of linked computer codes and such distinctions will be highlighted in the discussion. Several articles (8-lfJ) have already been published which discuss the different techniques and computer programs employed in cross-section processing. Much of this work, however, is of a survey nature and without numerical detail sufficient to quantitatively contrast the differences between processing codes. Others (11)(12)(13)(14) are more quantitative but either do not involve all the programs considered herein, review only a limited number of reaction types, or contain integral results, but limited information on specific group-wise cress sections.In the next section, a brief summary is given of the status and current capabilities for the programs under discussion. This is followed by a section in which, some of the more important processed multigroup constants, obtained with the aforementioned codes (for a particular model of ZPR-6/7) are tabulated to illustrate the magnitude of the differences obtained for Individual cross sections and transfer matrix elements. It is essential to note that all of the programs involved have several options and no attempt was made to exploit these options to "fine-tune" or "optimize"

show abstract

XLACS A Program to Produce Weighted Multigroup Neutron Cross Sections from ENDF/B

Cited by 6 publications

References 1 publication

Mikhail Shlyomovich Birman (on his 70th birthday)

Mikhail Shlyomovich Birman (on his 70th birthday)

Guide to verification and validation of the SCALE-4 criticality safety software

Fast Reactor Cross-Section Processing Codes - Is There a Dollars Worth of Difference Between Them?

Contact Info

Product

Resources

About