Published May 2001 | Version v1
Miscellaneous Metadata-only

Safety analysis on the irradiation of DUPIC fuel

Creators

  • 1. KAERI, Taejon (Korea, Republic of)

Description

In order to safety analysis of the DUPIC fuel to irradiate at HANARO, It has studied the characteristic of the thermal hydraulic on the normal operation at HANARO and has performed the evaluation of the hazardous degree in HANARO and the wholesome of DUPIC fuel. The results showed that the centerline temperature has maintained enough to temperature lower than the melting point and the surface temperature of cladding has also evaluated low the coolant maintain its to the level of the single phase flow. The conclusion has met the requirements of the limit on the normal condition. However, Even though the RIA and the Locked Rotor has satisfied the acceptance criteria of the centerline temperature of DUPIC fuel based upon overshooting of power, high linear power and high log rate must be arranged RPS trip setpoint low respectively on the provision against emergencies

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[6 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040479
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; EVALUATION; HANARO REACTOR; HYDRAULICS; IRRADIATION; SAFETY ANALYSIS; SPENT FUELS; THERMAL ANALYSIS
Descriptors DEC
DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUELS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; MECHANICS; NUCLEAR FUELS; POOL TYPE REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SURFACE COATING; TEST FACILITIES; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 7 figs, 3 tabs