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000827577 0881_ $$aJuel-Spez-0196
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000827577 245__ $$aThe KFA version of the high energy transport code hetc and the generalized evaluation code simpel
000827577 260__ $$aJülich$$bKernforschungsanlage Jülich GmbH Zentralbibliothek, Verlag$$c1983
000827577 300__ $$a105 p.
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000827577 4900_ $$aSpezielle Berichte der Kernforschungsanlage Jülich$$v196
000827577 520__ $$aFor spallation neutron source applications we are interested in theoretical methods that are capable of predicting a variety of different quantities related to radiation fields produced by proton beams and their associated effects, both in the vicinity of the target station and from beam losses which occur in the accelerator. It is also desirable that such calculational models be sufficiently general to allow investigations of potential applications of spallation sources for purposes in addition to providing an intense low-energy neutron source (e .g ., utilization as irradiation facility for radiation effects research, high-energy nuclear physics studies, research related to transmutation and power generation, etc .). To satisfy these needs requires rather general calculational methods which can incorporate numerous physics modules for treating the various types of interaction mechanisms that take place, and which are capable of accommodating complex geometries and material configurations. This necessarily leads to large Monte Carlo computer codes, which is the type of calculational method considered here. This report is primarily concerned with the programming and documentation aspects of the KFA-IRE system of ' Monte Carlo codes which have been prepared for use on the KFA IBM-3033 computer. The most essential ones are HETC, MORSE-CG and a newly developed general analysis code SIMPEL for event chains and particle data recorded by HETC. It is assumed here that the reader is familiar with HETC and MORSE-CG. Those readers who are not should read Refs. /1,2,3,4/ and /5/ in conjunction with the present report. Several modifications have been made to the high-energy radiation transport code HETC together with a detailed description of input data used by the intra-nuclear cascade (INC) and evaporation model (not presently available) to arrive at a new version of the code which we have designated HETC/KFA-l. Modifications to HETC are given in chapter 2, a modified input description in chapter 3. The documentation of input data to the intra-nuclear cascade and evaporation code is given in APPENDIX A and APPENDIX B. The analysis code SIMPEL -  together with its input description is outlined in chapter 4. The MORSE-CG modifications are described in chapter 5. A sample problem is described in APPENDIX E. The modified codes together with the SIMPEL code are available from Institut für Reaktorentwicklung, Kernforschungsanlage Jülich GmbH.
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000827577 7001_ $$0P:(DE-HGF)0$$aFilges, D.$$b1
000827577 7001_ $$0P:(DE-HGF)0$$aSterzenbach, G.$$b2
000827577 7001_ $$0P:(DE-HGF)0$$aArmstrong, T. W.$$b3
000827577 7001_ $$0P:(DE-HGF)0$$aColborn, B. L.$$b4
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