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- 26 - 2*? 9 Generation of Doppler broadened Cross Sections for Pu, 238 U. 2 3 V 2ft0 PU. 2ttl Pu. 2 * 2 Pu. Fe. Cr. Hi. Mn. Mo. Na for Hi^ier Temperature for use in Accident Analysis (M.M. Ramanadhan, V. Gopalakrishnan and S. Ganesan) Doppler broadened cross sections to temperatures varying from 300 K to 4500 K were generated for various fissile, fertile and structural materials usinp the preprocessing code LINEAR-RECENT and SJGMA1 . Self shielded 2 cross sections were obtained by using the program REX2 . Summarised below are the steps adapted for obtaining the cross sections for various elements* 1* Using: code * LINEAR 1 , the evaluated cross sections of the particular elements from the ENDF/B-IV file, were linearised to high precision (0.1$). 2. The above linearised data was reconstructed to a reasonable precision by using code 'RECENT 1 . 218 219 3. For materials like J V and J? Pu which had large data points, the output obtained from the code RECENT was further thinned using LINEAR code to an acceptable precision before going to step h. For the other materials step h was directly followed. k. Using the code SIGMA1 the above eross sections were Doppler broadened to 300 K with 0.0 thinning criteria. For broadening to temperatures higher than 300 K, one thinned output for 300 K was taken as input and cross sections were obtained at a number of temperatures. Since the running time of code SIGMA1 depends on the number of points input to it this method of going to higher temperatures was adapted. The preprocessing experience in the case of U-238 is detailed by • flow chart in Fig.l. The doppler broadened outputs were input to the program REX2 for obtaining the self shielded cross sections.
- 27 - 1. D.B. Cullen, SUMMIT of Preprocessing Codes, Report <strong>IAEA</strong> (MDS)-39 (1983). 2. V. Gopalafcriahnan and S. Ganesan, 'A Note oh the Program REX2 for Accurate Generation of Self Shieldfrig Factors fov Past Reactor Applications'* Internal Note REDG/RP-21»8(198V)»
Page 1 and 2: B.A.R.C.-1239 q as GOVERNMENT OF IN
Page 3 and 4: 1NIS Subject Cantenoryt A3*00 Descr
Page 5 and 6: PREFACE -i- CONTENTS I. HUCLEAR PIS
Page 7 and 8: -lii- II.8. Generation of Doppler b
Page 9 and 10: - 1 — I. NUCLEAR FISSION MASS. EN
Page 11 and 12: -• 3 -" ANo'ULAR DISTRIBUTION OF
Page 13 and 14: - 5 - Cumulative yields cf rare-ear
Page 15 and 16: • 7 " laotoplc yield attribution
Page 17 and 18: - 9 _ Effeot of excitation energy o
Page 19 and 20: - 11 - Studies on fragaent angular
Page 21 and 22: - 13 - Stadias on fragment angular
Page 23 and 24: - 15 - Cumulative yielda of short-l
Page 25 and 26: - 17 - TABIE 1 Fission Products Yie
Page 27 and 28: HEUTRON CAPTURE CROSS -SECTION OF 2
Page 29 and 30: and extracted the value of E for ev
Page 31 and 32: - 23 - MDMIOROUP PHOTON INTERACTION
Page 33: - 25 - iBAHC35-A35 GROUP CROSS-SECT
Page 37 and 38: - 29 - Generation of Activation Cro
Page 39 and 40: -31- (2) The emission of the first
Page 41 and 42: -33- iB level density parameter giv
Page 43 and 44: -34 A- References 1. M.L. Jhingan,
Page 45 and 46: - 36 - two multigroup Infinite dilu
Page 47 and 48: - 38 - Multigroup Constanta for Gal
Page 49 and 50: - 40 - The Program 'REX1 for Accura
Page 51 and 52: - 42 - The self shielding factor la
Page 53 and 54: - 44 - energy region particularly 3
Page 55 and 56: - 46 - COMPLOT : A Prorrain for Com
Page 57 and 58: Analysis of ZPR-9 Assembly 31. the
Page 59 and 60: - 50 - A Programme of Evaluation. P
Page 61 and 62: - 52 - Participation in IAEA Code V
Page 63 and 64: - 54 - Generation of Broad Group Er

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