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Druck-Materie 20b.qxd - JUWEL - Forschungszentrum Jülich

Druck-Materie 20b.qxd - JUWEL - Forschungszentrum Jülich

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For the validation of these data sets the calculated neutron flux density spectra for different<br />

moderators at two experimental facilities were compared with corresponding measured spectra.<br />

Most results agree well within the reported accuracy of measurement. At the present<br />

status the generated MCNP library for the moderators ice, water, hydrogen, solid methane,<br />

and cold Al as a structure material can be seen as an adequate tool for neutron thermalisation<br />

studies in the low temperature range for these moderators. Further validation should be made<br />

by application for alternative experiments especially at JESSICA at <strong>Jülich</strong>. Furthermore, for<br />

some moderators like hydrogen new basic data were published recently, which could be used<br />

to improve the existing data. For the future, corresponding data for clathrates and further interesting<br />

moderator materials (e.g. mesitylene) as well as for mixtures of moderators should<br />

be available for extended optimisation of the moderator of pulsed neutron sources.<br />

REFERENCES<br />

[1] Briesmeister,J.F., Editor : MCNP – A General Monte Carlo N-Particle Transport Code –<br />

Version 4C. LA-13709-M (2000)<br />

[2] DOORS-3.2: One, Two and Three-Dimensional Discrete Ordinate Neutron and Photon<br />

Transport Code System. RSIC Code Package CCC-650, program DORT, TORT<br />

[3] P.F. Rose: "ENDF-201, ENDF/B-VI Summary Documentation," BNL-NCS 17541, 4th<br />

Edition (1991)<br />

[4] Nordborg, C.: Distribution of JEF-2.2, JEF/DOC-371 (Febr. 1992).<br />

The JEF-2.2 Nuclear Data Library, JEFF Report 17 (April 2000)<br />

[5] T. Nakagawa, S. Shibata, S. Chiba, T. Fukahori, Y. Nakajima, Y. Kikuchi, T. Kawano,<br />

Y. Kanda, T. Ohsawa, H. Matsunobu, M. Kawai, A. Zukeran, T. Watanabe, S. Igarasi,<br />

K. Kosako, T. Asami: "Japanese Evaluated Nuclear Data Library Version 3 Revision-2:<br />

JENDL-3.2", J. Nucl. Sci. Technol., 32(12), 1259-1271 (1995).<br />

[6] Mac Farlane,R.E.; Muir,D.W.: The NJOY Nuclear Data Processing System Version 91.<br />

LA-12740 (1994)<br />

[7] Koppel,J.U.; Triplett,J.R., Naliboff,Y.D.: GASKET, a Unified Code for Thermal<br />

Neutron Scattering. GA-7417 (1966) (at IKE modified from GASKET2 to generate<br />

ENDF-6 files)<br />

[8] Nakahara,Y.: Phonon Spectrum and Thermal Neutron Scattering in Light Water Ice.<br />

J. Nucl. Sci. Technol. 5, 31 (1968)<br />

[9] Prask,H.; Boutin,H.; Yip,S.: Frequency Spectrum of Hydrogeneous Molecular solids by<br />

Inelastic Neutron Scattering. Hexagonal H2O Ice. J. Chem. Phys. 48, 3367 (1968)<br />

[10] Burgman,J.O.; Sciesinski,J.; Sköld,K.: Proton Dynamics in Water and Ice Studied by<br />

Inelastic Scattering of Slow Neutrons. Phys. Rev. 170, 808 (1968)<br />

[11] Renker,B.: Gitterdynamik von D2O Eis Ih. KFK-1497 (1971)<br />

[12] Tewari.S.P.; Kothari,L.S.: A Study of the Pulsed Neutron Problem in ICE in the<br />

Temperature Range 273 to 21 °C. Nucl. Sci. Eng. 39, 193 (1970)<br />

[13] Kadotani,H.; Iijima,S.: On the Coherent Scattering of Slow Neutrons from Heavy Water.<br />

J. Nucl. Sci. Technol. 4, 625 (1967)<br />

[14] Keinert.J.: Neutronenthermalisierung in Polyäthylen. Diploma Thesis 1967<br />

[15] Koppel,J.U.; Houston,D.H.: Reference Manual for ENDF Thermal Neutron Scattering<br />

Data. GA-8774 (1968) , ENDF-269 (19<br />

[16] Giauque,W.F.; Stout,J.W. : The Entropy of Water and the Third Law of<br />

Thermodynamics. The Heat capacity of Ice fro 15 to 273 °K. J. Am. Chem. Soc. 58,<br />

1144 (1936)<br />

40

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