Abstract
Using the continuous energy Monte Carlo code MCNP-4A with a combination of the evaluated nuclear data file JENDL-3.1, analyses have been made of the criticality experimental systems that were described as triangular arrays of 4.3wt% {sup 235}U-enriched uranium dioxide rods partially immersed in uranyl nitrate solution of the same {sup 235}U enrichment containing soluble gadolinium. The calculated neutron multiplication factors have had an average of 0.955. The reason to have such a smaller value than unity has been estimated to be mainly attributed to incorrect compositions of fuel solution and so on that were reported. Therefore, the specification of the international benchmark exercises proposed by OECD/NEA have been accepted for the composition of fuel pellet, fuel solution, stainless steel and gadolinium, as it has been considered they had supplied more appropriate values than originally reported after examination of the composition data, to calculate the neutron multiplication factors, which has resulted in an average of 0.986, fairly approached unity. (author).
Citation Formats
Kobayashi, Tomoya, Arakawa, Takuya, and Okuno, Hiroshi.
Analyses with MCNP code of the criticality experiment of pellet-solution coexisting low-enriched uranium fuel.
Japan: N. p.,
1994.
Web.
Kobayashi, Tomoya, Arakawa, Takuya, & Okuno, Hiroshi.
Analyses with MCNP code of the criticality experiment of pellet-solution coexisting low-enriched uranium fuel.
Japan.
Kobayashi, Tomoya, Arakawa, Takuya, and Okuno, Hiroshi.
1994.
"Analyses with MCNP code of the criticality experiment of pellet-solution coexisting low-enriched uranium fuel."
Japan.
@misc{etde_10121798,
title = {Analyses with MCNP code of the criticality experiment of pellet-solution coexisting low-enriched uranium fuel}
author = {Kobayashi, Tomoya, Arakawa, Takuya, and Okuno, Hiroshi}
abstractNote = {Using the continuous energy Monte Carlo code MCNP-4A with a combination of the evaluated nuclear data file JENDL-3.1, analyses have been made of the criticality experimental systems that were described as triangular arrays of 4.3wt% {sup 235}U-enriched uranium dioxide rods partially immersed in uranyl nitrate solution of the same {sup 235}U enrichment containing soluble gadolinium. The calculated neutron multiplication factors have had an average of 0.955. The reason to have such a smaller value than unity has been estimated to be mainly attributed to incorrect compositions of fuel solution and so on that were reported. Therefore, the specification of the international benchmark exercises proposed by OECD/NEA have been accepted for the composition of fuel pellet, fuel solution, stainless steel and gadolinium, as it has been considered they had supplied more appropriate values than originally reported after examination of the composition data, to calculate the neutron multiplication factors, which has resulted in an average of 0.986, fairly approached unity. (author).}
place = {Japan}
year = {1994}
month = {Dec}
}
title = {Analyses with MCNP code of the criticality experiment of pellet-solution coexisting low-enriched uranium fuel}
author = {Kobayashi, Tomoya, Arakawa, Takuya, and Okuno, Hiroshi}
abstractNote = {Using the continuous energy Monte Carlo code MCNP-4A with a combination of the evaluated nuclear data file JENDL-3.1, analyses have been made of the criticality experimental systems that were described as triangular arrays of 4.3wt% {sup 235}U-enriched uranium dioxide rods partially immersed in uranyl nitrate solution of the same {sup 235}U enrichment containing soluble gadolinium. The calculated neutron multiplication factors have had an average of 0.955. The reason to have such a smaller value than unity has been estimated to be mainly attributed to incorrect compositions of fuel solution and so on that were reported. Therefore, the specification of the international benchmark exercises proposed by OECD/NEA have been accepted for the composition of fuel pellet, fuel solution, stainless steel and gadolinium, as it has been considered they had supplied more appropriate values than originally reported after examination of the composition data, to calculate the neutron multiplication factors, which has resulted in an average of 0.986, fairly approached unity. (author).}
place = {Japan}
year = {1994}
month = {Dec}
}