Performance of Advanced Self-Shielding Models in DRAGON for the Estimation of CANDU-6 Safety Parameters

Karthikeyan, R.; Hébert, Alain

doi:10.13182/nt07-a3819

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C1 Californium Neutron Source1

Fuel and Moderator Unit Cell1

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2010

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(2 citation statements)

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“…In the first case, when experiments are performed, the beam tube is removed from the facility. Consequently, some of the results for the Cf neutron source have been calculated with the beam tube inserted (Table II, [75][76][77][78][79][80][81]118,120,122,125,127,129,132,134,136,138,[140][141][142][143]; these numerical results are compared with the numerical results from the D-D and the D-T neutron source), and the other results obtained without the beam tube (Table III, 81,[144][145][146][147][148][149][150][151][152][153][154][155]; these numerical results are compared with the experimental results).…”

Section: C1 Californium Neutron Sourcementioning

confidence: 99%

“…Karthikeyan and Hebert (one of the authors of the DRAGON computer program) have observed a 280 pcm difference between MCNP5 and DRAGON multiplication factors of a CANDU fuel unit cell. 75 The effective delayed neutron fraction calculated by MCNP/MCNPX and DRAGON with the k-ratio method [76][77] is 690±10 and 688 pcm, respectively. In the DRAGON calculation, two different WIMSD nuclear data libraries have been used, as described in Section 2.B.…”

Section: Fuel and Moderator Unit Cellmentioning

confidence: 99%

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