Post-neutron mass yield distribution in the thermal neutron induced fission of $${}^{241}$$ 241 Pu
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Regular Article - Experimental Physics
Post-neutron mass yield distribution in the thermal neutron induced fission of 241 Pu H. Naik1,a , S. P. Dange1, W. Jang2 , R. J. Singh1 1 2
Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai 400 085, India Department of Physics, Kyungpook National University, Daegu 41566, Korea
Received: 15 April 2020 / Accepted: 23 June 2020 © Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2020 Communicated by Jose Benlliure
Abstract The cumulative and independent yields of various fission products within the mass range of 83–115 and 125–157 have been measured in the thermal neutron induced fission of 241 Pu by using radiochemical and off-line γ -ray spectrometric technique. From the cumulative yields, postneutron mass yields were obtained by using the charge distribution correction. From the mass yields data, full width at tenth maximum (FWTM) of light and heavy mass wings, the average light mass () and heavy mass () as well as the average neutrons number () were obtained. The mass yield data in the 241 Pu(nth , f) reaction was compared with the similar data of 229 Th(nth , f) reaction to examine the nuclear structure effect. Surprisingly, different trends of standard I and standard II asymmetric mode of fission were seen in the two fissioning systems due to the different nuclear structure effect.
1 Introduction Studies on mass yield distribution in the low energy neutron induced fission of actinides provides information on the nuclear fission mechanism [1,2]. The mass yield distributions in the neutron-induced fission are asymmetric with triple humps for light-Z actinides (Ac, Th, Pa), asymmetric with double humps for medium-Z actinides (U to Cf) and symmetric for the heavy-Z actinides (Es to Lr) [1,2]. Besides this, the mass yield distributions of actinides have fine structure around the higher mass yield region, which arises due to the effect of shell closure proximity [1–3] and even-odd effect [4–6]. The yields of fission products in the neutron induced fission of actinides are also needed for decay heat [7] calculation and thus are important for the design of various types of reactors. In particular, the yields of fission products a e-mail:
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in the neutron induced fission of 229,232 Th, 233,235,238 U and 238,239,240,241 Pu are important for the advanced heavy water reactor (AHWR) [8], conventional (LWR, BWR) and fast reactor [9,10]. It is a well-known fact that in conventional reactor, either natural or enriched 235 U along with 238 U is used as a fuel, whereas in AHWR 232 Th-233 U is used as a fuel. In the AHWR and conventional reactor, 233 U and 235 U are the respective fissile material, which undergo (n,f) reaction with low energy neutron to run the reactor. In the fast reactor, 238 U-239 Pu is used as a fuel in which the fissile isotope 239 Pu undergo (n,f) reaction to run the reactor. The fissile material 239 Pu also undergo (n,2n) reaction with the higher ener
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