原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2013年
z2期
562-567
,共6页
位金锋%李富%孙玉良%张竞宇
位金鋒%李富%孫玉良%張競宇
위금봉%리부%손옥량%장경우
高温气冷堆%球床%燃料循环%VSOP模型%蒙特卡罗方法
高溫氣冷堆%毬床%燃料循環%VSOP模型%矇特卡囉方法
고온기랭퇴%구상%연료순배%VSOP모형%몽특잡라방법
high-temperature gas-cooled reactor%pebble bed%fuel cycle%VSOP model%Monte Carlo method
VSOP程序广泛应用于高温气冷堆铀燃料堆芯设计，而对钚燃料堆芯未经充分验证。本文基于250MW球床模块式高温气冷堆示范电站HTR-PM铀钚循环乏燃料中的铀和钚，设计了PuO2和MOX燃料元件，将新设计的燃料元件重新装入与HTR-PM同样结构和尺寸的堆芯，分别形成纯钚燃料堆芯和MOX燃料堆芯。利用蒙特卡罗方法中规则的重复结构模拟包覆燃料颗粒在燃料球内的随机分布及燃料球在堆芯内的随机分布。针对同一参考堆芯，比较了VSOP模型和MCNP模型的有效增殖因数，并分析了产生差异的原因。结果显示，对于铀燃料堆芯，VSOP与MCNP程序计算结果符合较好；对于钚燃料堆芯，VSOP结果比MCNP结果小2％左右。初步验证了VSOP模型对钚燃料堆芯的可用性，提出了进一步改进VSOP程序的建议。
VSOP程序廣汎應用于高溫氣冷堆鈾燃料堆芯設計，而對钚燃料堆芯未經充分驗證。本文基于250MW毬床模塊式高溫氣冷堆示範電站HTR-PM鈾钚循環乏燃料中的鈾和钚，設計瞭PuO2和MOX燃料元件，將新設計的燃料元件重新裝入與HTR-PM同樣結構和呎吋的堆芯，分彆形成純钚燃料堆芯和MOX燃料堆芯。利用矇特卡囉方法中規則的重複結構模擬包覆燃料顆粒在燃料毬內的隨機分佈及燃料毬在堆芯內的隨機分佈。針對同一參攷堆芯，比較瞭VSOP模型和MCNP模型的有效增殖因數，併分析瞭產生差異的原因。結果顯示，對于鈾燃料堆芯，VSOP與MCNP程序計算結果符閤較好；對于钚燃料堆芯，VSOP結果比MCNP結果小2％左右。初步驗證瞭VSOP模型對钚燃料堆芯的可用性，提齣瞭進一步改進VSOP程序的建議。
VSOP정서엄범응용우고온기랭퇴유연료퇴심설계，이대비연료퇴심미경충분험증。본문기우250MW구상모괴식고온기랭퇴시범전참HTR-PM유비순배핍연료중적유화비，설계료PuO2화MOX연료원건，장신설계적연료원건중신장입여HTR-PM동양결구화척촌적퇴심，분별형성순비연료퇴심화MOX연료퇴심。이용몽특잡라방법중규칙적중복결구모의포복연료과립재연료구내적수궤분포급연료구재퇴심내적수궤분포。침대동일삼고퇴심，비교료VSOP모형화MCNP모형적유효증식인수，병분석료산생차이적원인。결과현시，대우유연료퇴심，VSOP여MCNP정서계산결과부합교호；대우비연료퇴심，VSOP결과비MCNP결과소2％좌우。초보험증료VSOP모형대비연료퇴심적가용성，제출료진일보개진VSOP정서적건의。
VSOP program package is widely used in the engineering design of the pebble bed high-temperature gas-cooled reactor with uranium fuel , but the applicability of VSOP code for pure plutonium fuel core is not completely proven . Uranium and plutonium were recycled from the 250 MW High-Temperature Gas-Cooled Reactor-Pebble-bed-Module (HTR-PM ) spent fuel from the U-Pu fuelled core ,and PuO2 and MOX fuel elements were designed based on this recycled plutonium and uranium .These fuel elements were used to build up a new PuO2 or MOX fuelled core with the same geometry of the original reactor .The random arrangement of coated fuel particles in the fuel pebbles and the random distribution of the fuel pebbles in the core were modeled as the repeated structure of regular shape in the Monte Carlo package MCNP .Based on the same reference of HTR reactor core ,the core effective multiplication factors from VSOP model and Monte Carlo model were compared ,and the causes of the differences were analyzed .Preliminary results show that the VSOP simulation result of the uranium fuel core accords well with the MCNP result ,and the VSOP result of the pure plutonium fuel core is about 2% lower than that of MCNP code .Preliminary results demonstrate the applicability of VSOP code for pure plutonium fuel core , and the improve suggestions of the VSOP code were given .
