INDC(IND)-35G - IAEA Nuclear Data Services

More documents

Recommendations

Info

- 14 - 1* T. Aatta, 8.K. SahaknnAu* 8.P. Daigt, I. Chakrurarty, R. Oaln Satya Peakaah, Phjrt. Bir. C. g, 7206 (1983). TABLE 1 fissioning Izoitation Angular ifcagMut Angular Batrer MoMntuB . Mcawnta 6.5 3-4 6.0 t ic5 5.9 ± 1.0 33.2 14.2 5.7 ± 1.0 7.3 ± 1.2
- 15 - Cumulative yielda of short-lived ruthenium iaotopea in the tbanial neutron induced fisaion of 233 U, ®% and 239 Pu. A.O.C. Hair, Alolt Srivaatava, A. Goawami and B.K. Srivastava Cumulative yielda of 107 Ru, 108 Ru and 109 Bu in the fission of S3A U, 256 D and Fu have teen determined using fast radioohemloal separation teohniquea followed by high resolution ^-ray speotrometry. The fissile material a ( 1OyUg) «ere irradiated in pneumatio oarrier faoility of CIRUS reaotox for 20 seo. The ruthenium isotopes were aepaxated from the irradiated target by distilling rathenitw as RuO. froa fission products in presence of NaBiO- and was oollected in ice cooled 1M HC1. Using this method a chemioal yield of 50^ and high de- contamination (>1000) fxoa teohnetiUB and halogens were obtained. Cunulatire yields of ^Eu, Ra and Ru were oaloulated from the experimentally obtained count rates whioh are corrected fox detection efficiency and -ray atandancea, using standard equations, further, these yields were converted into ohain yialda assuming normal charge distribution systematic a for comparison with the literature data on ohain yielda. The following table give a the values of cumulative yields and ohain yields. TAHfi 1 Cumulative Yialda of Ruthenium Isotopes lotope in the thermal neutron induoed fission of 253u, 233n. 235tf and Haas 233 U(y0 235 U(?S) "**&) Reference 107 0.111+0.012 0.145 ±0.032 3.068 ± 0.264 This work 0.13 ±0.01* 1OS 0.077 ± 0.005 0.067 ± 0.017 2.005 ± 0.165 This work 0.042 ± 0.002* 1.89 ± 0.05* 109 - 0.034 ±0.004 1.088 + 0.98 Thia work 0.027 ±0.003* * P. Pettwela, P. Sal Marmol, Z. Physik A. Z&, 359 (1975)< © J.K. Dickens, J.V. Mo Connell, K.J. Horthout, Kiol. Soi. Bngg. 21* 146 (1981).
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: - 13 - Stadias on fragment angular
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 and 34: - 25 - iBAHC35-A35 GROUP CROSS-SECT
Page 35 and 36: - 27 - 1. D.B. Cullen, SUMMIT of Pr
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

INDC(IND)-35G - IAEA Nuclear Data Services

Create successful ePaper yourself

Delete template?

Save as template?