Published 2019 | Version v1
Miscellaneous Restricted

SIMULATE5 analysis of a spent fuel pool

Description

This paper describes proof-of-principle fuel pool criticality calculations using the nodal diffusion code SIMULATE5, which is supplied with cross section data from CASMO5. The accuracy of SIMULATE5 is tested against CASMO5 and MCNP6.2 for several demonstration problems using PWR fuel and a mock rack geometry. These test problems include various features, such as fuel with different exposures, empty locations, and a water reflector. Most of the tests are in two dimensions, but one three-dimensional test is included. For all test problems, SIMULATE5 predicts the eigenvalue within 250 pcm of the reference. Without its sub-mesh model, these results are much worse for several of the cases (up to 2200 pcm error). As expected, CASMO5 and MCNP6.2 agree closely. For these examples, SIMULATE5 is 50 to 150 times faster than CASMO5 and 103 to 105 times faster than MCNP6.2. Given its accuracy for these demonstration problems, along with its computational efficiency and ease-of-use, SIMULATE5 could be a useful tool for fuel pool criticality analysis. (authors)

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Additional details

Publishing Information

Imprint Pagination
11 p.
Report number
INIS-FR--21-0125

Conference

Title
11. international conference on nuclear criticality safety
Acronym
ICNC 2019
Dates
15-20 Sep 2019
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
52011501
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; CRITICALITY; FUEL STORAGE POOLS; NEUTRON TRANSPORT THEORY; NODAL EXPANSION METHOD; S CODES; SPENT FUEL STORAGE
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; STORAGE; TRANSPORT THEORY

Optional Information

Notes
7 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses