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Volumn 32, Issue 1, 2005, Pages 29-62

Effect of high-density fuel loading on criticality of low enriched uranium fueled material test research reactors

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; HYDRAULICS; MATERIALS TESTING; NUCLEAR FUEL CLADDING; NUCLEAR FUEL ELEMENTS; OPTIMIZATION; THERMAL EFFECTS; URANIUM;

EID: 4944226178     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2004.07.003     Document Type: Article
Times cited : (14)

References (15)
  • 1
    • 4944242910 scopus 로고    scopus 로고
    • Effect of coolant channel width in MTR type fuel on group constants
    • Ahmad, N., Aslam, Khan, L.A., Hameed, T., 1998. Effect of coolant channel width in MTR type fuel on group constants. Sci. Int. (Lahore) 9 (3), 243-244.
    • (1998) Sci. Int. (Lahore) , vol.9 , Issue.3 , pp. 243-244
    • Ahmad, N.1    Aslam Khan, L.A.2    Hameed, T.3
  • 2
    • 0036489487 scopus 로고    scopus 로고
    • Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel
    • Aslam and Ahmed, N., 2002. Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel. Ann. Nucl. Energy 29, 477-488.
    • (2002) Ann. Nucl. Energy , vol.29 , pp. 477-488
    • Aslam1    Ahmed, N.2
  • 3
    • 0036885232 scopus 로고    scopus 로고
    • Analysis of reactivity induced accidents at Pakistan Research Reactor-1
    • Bokhari, I.H., Israr, M., Pervez, S., 2002. Analysis of reactivity induced accidents at Pakistan Research Reactor-1. Ann. Nucl. Energy 29, 2225-2234.
    • (2002) Ann. Nucl. Energy , vol.29 , pp. 2225-2234
    • Bokhari, I.H.1    Israr, M.2    Pervez, S.3
  • 6
    • 0004035693 scopus 로고
    • Nuclear reactor core analysis code-CTTATION
    • Revision 2. Oak Ridge National Laboratory
    • Fowler, T.B., Vondy, D.R.; Cunningham, G.W., 1971. Nuclear Reactor Core Analysis Code-CTTATION, USAEC Report ORNL-TM-2496, Revision 2. Oak Ridge National Laboratory.
    • (1971) USAEC Report , vol.ORNL-TM-2496
    • Fowler, T.B.1    Vondy, D.R.2    Cunningham, G.W.3
  • 8
    • 0346312111 scopus 로고    scopus 로고
    • Fuel management strategy for the new silicide core design of RSG GAS (MPR-30)
    • Hong, L.P., Arbie, B., Sembiring, Prayoto, T.M., Nabbi, R., 1998. Fuel management strategy for the new silicide core design of RSG GAS (MPR-30). Nucl. Eng. Des. 180, 207-219.
    • (1998) Nucl. Eng. Des. , vol.180 , pp. 207-219
    • Hong, L.P.1    Arbie, B.2    Sembiring Prayoto, T.M.3    Nabbi, R.4
  • 11
    • 0033900664 scopus 로고    scopus 로고
    • Reactor physics calculations and their experimental validation for conversion and upgrading of a typical swimming pool type research reactor
    • Khan, L.A., Ahmad, N., Ahmad, A., Zafar, M.S., 2000. Reactor physics calculations and their experimental validation for conversion and upgrading of a typical swimming pool type research reactor. Ann. Nucl. Energy 27, 873-885.
    • (2000) Ann. Nucl. Energy , vol.27 , pp. 873-885
    • Khan, L.A.1    Ahmad, N.2    Ahmad, A.3    Zafar, M.S.4
  • 13
    • 0342484421 scopus 로고    scopus 로고
    • Solution of neutron spectrum adjustment problem in a typical MIR type research reactor
    • Malkawi, S.R., Ahmed, N., 2001. Solution of neutron spectrum adjustment problem in a typical MIR type research reactor. Ann. Nucl. Energy 28, 25-51.
    • (2001) Ann. Nucl. Energy , vol.28 , pp. 25-51
    • Malkawi, S.R.1    Ahmed, N.2
  • 14
    • 0003949774 scopus 로고
    • PARET. A program for the analysis of reactor transients
    • IDO-1728
    • Obenchain, C.F., 1969, PARET. A Program for the Analysis of Reactor Transients. ACE Research and Development report, IDO-1728.
    • (1969) ACE Research and Development Report
    • Obenchain, C.F.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.