[논문]Nuclear fuel in generation II and III reactors: research issues related to high burn-up

Degueldre, C.; Bertsch, J.; Kuri, G.; Martin, M.

doi:10.1039/c0ee00476f

[해외논문] Nuclear fuel in generation II and III reactors: research issues related to high burn-up

Energy & environmental science, v.4 no.5, 2011년, pp.1651 - 1661

Degueldre, C. (NES, Paul Scherrer Institute) , Bertsch, J. (NES, Paul Scherrer Institute) , Kuri, G. (NES, Paul Scherrer Institute) , Martin, M. (NES, Paul Scherrer Institute)

Abstract ▼ AI-Helper

Nuclear fuel has a much higher energy density compared to conventional fuels like fossil and allows an almost green house emission free energy production. Despite its inherent advantages, the performance of nuclear fuel has to be amended due to economical as well as ecological reasons, without constricting its safe use. A higher performance of nuclear fuel means extracting more energy from the fuel. The higher energy yield also implies less volume of highly radioactive spent fuel per produced energy unit. The stronger energy extraction from nuclear fuel leads to a higher burn-up, which means pushing the limits, with the safety limitations fixed by the regulators. This has been carried out, for instance, in Switzerland for many years and has reached about 80 MW d kg−1 or about 8% of fission per initial metal atom “FIMA” in generation (GEN) II reactors. Nuclear fuels consist of different constituents which are the matrix, e.g. non-inert or inert, a fissile part, components such as burnable poisons, fertile isotopes or grain enlargers. The fuel matrix is currently described as the first barrier between fission products and the next nuclear barrier towards the environment. It must remain effective over years. The higher the burn-up the higher the concentration of fission products is in the fuel matrix. The fissile part in the fuel directly contributes to the energy production. The typical enrichment of fissile isotopes in a commercial nuclear fuel is around 5%. A higher enrichment followed by a respective higher burn-up may affect the fission product retention capability of the fuel matrix and its interaction with the cladding. The doping with grain enlargers leads to bigger fuel grains, implying longer diffusion paths, retaining gaseous fission products in the matrix under certain temperature conditions. This shall allow a better pressure control at higher burn-up in GEN II and III reactors. To reach very high burn up >100 MW d kg−1 (equivalent), the only possibilities are offered by inert matrix fuels. This is investigated in the last part of this study. The zirconia inert matrix concept could be used in a last cycle e.g. to burn plutonium excess and minor actinides prior to geological disposal. Prior to and after burn-up, the fuel material is characterized by micro- or nano-beam analysis to gain information on the dispersity of the system, the presence of defect and segregated phases as well as to track fission products. These studies can be performed through a multiscale approach. The fuel structure can be revealed at the macro-, micro-, nano- and sub-nano-level. Graphic AbstractNuclear fuels that have much higher energy density compared to conventional fuels may be analysed after burn-up at multiscale levels.

참고문헌 (73)

Prog. Nucl. Energy Forsberg 51 192 2009 10.1016/j.pnucene.2008.04.002

상세보기
Energy Weisser 32 1543 2007 10.1016/j.energy.2007.01.008

상세보기
Ann. Nucl. Energy Ekholm 5 507 1978 10.1016/0306-4549(78)90027-0

상세보기
Energy Policy Guentcheva 12 439 1984 10.1016/0301-4215(84)90108-3

상세보기
J. Nucl. Mater. Strasser 106 3 1982 10.1016/0022-3115(82)90328-2

상세보기
Math. Comput. Simul. Kemeny 24 194 1982 10.1016/0378-4754(82)90101-X

상세보기
Energy Policy Verbruggen 36 4036 2008 10.1016/j.enpol.2008.06.024

상세보기
Prog. Nucl. Energy Lee 49 397 2007 10.1016/j.pnucene.2007.05.002

상세보기
Reliab. Eng. Syst. Saf. Warner North 59 123 1998 10.1016/S0951-8320(97)00132-4

상세보기
Prog. Nucl. Energy Kessler 40 309 2002 10.1016/S0149-1970(02)00024-0

상세보기
J. Nucl. Energy, Parts A/B Koryakin 19 707 1965 10.1016/0368-3230(65)90026-1

상세보기
J. Nucl. Sci. Technol. Blair 45 639 2008 10.3327/jnst.45.639
J. Nucl. Mater. Noirot 372 318 2008 10.1016/j.jnucmat.2007.04.037

상세보기
J. Nucl. Mater. Kinoshita 252 71 1998 10.1016/S0022-3115(97)00280-8

상세보기
J. Nucl. Mater. Mogensen 264 99 1999 10.1016/S0022-3115(98)00474-7

상세보기
J. Nucl. Mater. Lassmann 226 1 1995 10.1016/0022-3115(95)00116-6

상세보기
J. Nucl. Mater. Matzke 208 18 1994 10.1016/0022-3115(94)90193-7

상세보기
J. Less Common Met. Matzke 121 537 1986 10.1016/0022-5088(86)90573-4

상세보기
J. Nucl. Mater. Szuta 58 278 1975 10.1016/0022-3115(75)90119-1

상세보기
J. Nucl. Mater. Robertson 7 225 1962 10.1016/0022-3115(62)90243-X

상세보기
Prog. Nucl. Energy Lombardi 50 944 2008 10.1016/j.pnucene.2008.03.006

상세보기
Nucl. Eng. Des. Herring 203 65 2001 10.1016/S0029-5493(00)00297-1

상세보기
Nucl. Eng. Des. Vapirev 167 105 1996 10.1016/S0029-5493(96)01285-X

상세보기
Energy Convers. Manage. Núñez-Carrera 49 47 2008 10.1016/j.enconman.2007.05.016

상세보기
J. Alloys Compd. Degueldre 444-445 36 2007 10.1016/j.jallcom.2006.11.203

상세보기
J. Nucl. Mater. Oversby 245 17 1997 10.1016/S0022-3115(96)00751-9

상세보기
J. Nucl. Mater. Carmack 352 276 2006 10.1016/j.jnucmat.2006.02.098

상세보기
J. Nucl. Mater. Medvedev 342 48 2005 10.1016/j.jnucmat.2005.03.017

상세보기
Nucl. Eng. Des. Chirayath 239 1916 2009 10.1016/j.nucengdes.2009.05.019

상세보기
J. Nucl. Mater. Riella 178 204 1991 10.1016/0022-3115(91)90387-M

상세보기
Ann. Nucl. Energy Galperin 22 317 1995 10.1016/0306-4549(94)00053-H

상세보기
Ann. Nucl. Energy Franceschini 36 1201 2009 10.1016/j.anucene.2009.04.005

상세보기
Ann. Nucl. Energy Talamo 33 794 2006 10.1016/j.anucene.2006.04.009

상세보기
Nucl. Eng. Des. Durmazuçar 203 57 2001 10.1016/S0029-5493(00)00296-X

상세보기
J. Nucl. Mater. Minato 288 57 2001 10.1016/S0022-3115(00)00578-X

상세보기
Nucl. Eng. Des. Rogers 239 1019 2009 10.1016/j.nucengdes.2009.02.005

상세보기
J. Nucl. Mater. Stanculescu 274 146 1999 10.1016/S0022-3115(99)00082-3

상세보기
J. Nucl. Mater. Pistner 352 268 2006 10.1016/j.jnucmat.2006.02.088

상세보기
J. Nucl. Mater. Baranaev 319 154 2003 10.1016/S0022-3115(03)00211-3

상세보기
Prog. Nucl. Energy Porta 38 355 2001 10.1016/S0149-1970(00)00134-7

상세보기
Ann. Nucl. Energy Yilmaz 33 439 2006 10.1016/j.anucene.2005.11.011

상세보기
Prog. Nucl. Energy Porta 38 347 2001 10.1016/S0149-1970(00)00132-3

상세보기
Ann. Nucl. Energy Ronen 37 201 2010 10.1016/j.anucene.2009.11.002

상세보기
Ann. Nucl. Energy Nikitin 26 1319 1999 10.1016/S0306-4549(99)00027-4

상세보기
J. Nucl. Mater. Chang 385 157 2009 10.1016/j.jnucmat.2008.08.062

상세보기
J. Nucl. Mater. Killeen 58 39 1975 10.1016/0022-3115(75)90164-6

상세보기
J. Nucl. Mater. Sengupta 325 141 2004 10.1016/j.jnucmat.2003.11.006

상세보기
J. Nucl. Mater. Killeen 88 177 1980 10.1016/0022-3115(80)90272-X

상세보기
Nucl. Eng. Des. Rodriguez 222 299 2003 10.1016/S0029-5493(03)00034-7

상세보기
Prog. Nucl. Energy Peddicord 18 265 1986 10.1016/0149-1970(86)90036-3

상세보기
J. Nucl. Mater. Stehle 153 3 1988 10.1016/0022-3115(88)90187-0

상세보기
J. Nucl. Mater. Spino 346 131 2005 10.1016/j.jnucmat.2005.06.015

상세보기
J. Nucl. Mater. Walker 345 192 2005 10.1016/j.jnucmat.2005.05.010

상세보기
J. Nucl. Mater. Spino 375 8 2008 10.1016/j.jnucmat.2007.10.007

상세보기
J. Nucl. Mater. Walker 275 56 1999 10.1016/S0022-3115(99)00108-7

상세보기
J. Nucl. Mater. Bourgeois 297 313 2001 10.1016/S0022-3115(01)00626-2

상세보기
J. Nucl. Mater. Leenaers 317 62 2003 10.1016/S0022-3115(02)01693-8

상세보기
J. Nucl. Mater. Blair 350 232 2006 10.1016/j.jnucmat.2006.01.006

상세보기
J. Nucl. Mater. Degueldre 2011
J. Alloys Compd. Cobos 271-273 610 1998 10.1016/S0925-8388(98)00170-4

상세보기
J. Alloys Compd. Martin 444-445 410 2007 10.1016/j.jallcom.2007.01.032

상세보기
Appl. Phys. A: Mater. Sci. Process. Degueldre 73 489 2001 10.1007/s003390100798

상세보기
J. Solid State Chem. Conradson 178 521 2005 10.1016/j.jssc.2004.09.029

상세보기
J. Nucl. Mater. Lee 274 7 1999 10.1016/S0022-3115(99)00094-X

상세보기
Prog. Nucl. Energy Ledergerber 38 301 2001 10.1016/S0149-1970(00)00122-0

상세보기
J. Nucl. Mater. Degueldre 319 6 2003 10.1016/S0022-3115(03)00127-2

상세보기
J. Nucl. Mater. Degueldre 320 96 2003 10.1016/S0022-3115(03)00175-2

상세보기
J. Nucl. Mater. Lumkin 274 206 1999 10.1016/S0022-3115(99)00066-5

상세보기
Prog. Nucl. Energy Pouchon 38 443 2001 10.1016/S0149-1970(00)00155-4

상세보기
Radiochim. Acta Curti 90 801 2002 10.1524/ract.2002.90.9-11_2002.801

상세보기
J. Solution Chem. Ekberg 33 47 2004 10.1023/B:JOSL.0000026645.41309.d3

상세보기
Russ. J. Inorg. Chem. Kovalenko 6 272 1961
Ceram. Trans. Adair 1 135 1987

내보내기 구분	파일저장 인쇄 메일전송
구성항목	기본정보 상세정보 관리번호, 논문명, 저널/프로시딩명, 저자 , 발행년, 권, 호, 시작페이지, 끝페이지, 발행기관 관리번호, 논문명, 대등논문명, 저자 , 저널/프로시딩명, 발행기관, 발행년, 발행언어, 권, 호, 시작페이지, 끝페이지, ISBN, ISSN, 주제분야, 키워드, 초록(한글), 초록(영문), 저자(소속기관)
저장형식	Text(ASCII format) Excel format RefWorks Direct Export RIS format (for Reference Manager, ProCite, EndNote), Scholar's Aids, Mendeley
메일정보	받는사람 (필수) @ 보내는사람 (선택) @ 제목 내용 KISTI 검색결과 이메일 서비스
안내	총 건의 자료가 검색되었습니다. 다운받으실 자료의 인덱스를 입력하세요. (1-10,000) 검색결과의 순서대로 최대 10,000건 까지 다운로드가 가능합니다. 데이타가 많을 경우 속도가 느려질 수 있습니다.(최대 2~3분 소요) 다운로드 파일은 UTF-8 형태로 저장됩니다. 파일의 내용이 제대로 보이지 않을실 때는 웹브라우저 상단의 보기 -> 인코딩 -> 자동선택 여부를 확인하십시오. ~ Text(ASCII format) Excel format

연합인증

[해외논문] Nuclear fuel in generation II and III reactors: research issues related to high burn-up

Abstract ▼ AI-Helper

참고문헌 (73)

이 논문을 인용한 문헌

관련 콘텐츠

원문 URL 링크

이 논문과 함께 이용한 콘텐츠

AI-Helper ※ AI-Helper는 오픈소스 모델을 사용합니다.

선택된 텍스트