Published October 2011 | Version v1
Miscellaneous

Criticality and Its Uncertainty Analysis of Spent Fuel Storage Rack for Research Reactor

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

For evaluating the criticality safety of spent fuel storage rack in an open pool type research reactor, a permissible upper limit of criticality should be determined. It can be estimated from the criticality upper limit presented by the regulatory guide and an uncertainty of criticality calculation. In this paper, criticalities for spent fuel storage rack are carried out at various conditions. The calculation uncertainty of MCNP system is evaluated from the calculation results for the benchmark experiments. Then, the upper limit of criticality is determined from the uncertainties and the calculated criticality of the spent fuel storage rack is evaluated

Part of:
Proceedings of Korean Nuclear Society, Daejeon (KR)

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2011 autumn meeting of the KNS
Dates
26-28 Oct 2011
Place
Kyoungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
43045330
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; CRITICALITY; REGULATORY GUIDES; RESEARCH REACTORS; SAFETY; SPENT FUEL STORAGE
Descriptors DEC
DOCUMENT TYPES; REACTORS; RESEARCH AND TEST REACTORS; STORAGE

Optional Information

Notes
4 refs, 1 fig, 2 tabs